ML19312C247

Annual Operating Rept,1977, Vol 1,2 & 3

ML19312C247
Person / Time
Site:	Oconee
Issue date:	12/31/1977
From:	DUKE POWER CO.
To:
References
NUDOCS 7912120585
Download: ML19312C247 (900)

Text

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STEAM PRODUCTION DEPARTMENT OCONEE NUCLEAR STATION ANNUAL OPERATING REPORT l 1977 .

VOLUME 1

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STEAM PRODUCTION DEPARTMENT OCONEE NUCLEAR STATION ANNUAL OPERATING REPORT 1977 VOLUME 1 l

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DUKE POWER COMPANY OCONEE NUCLEAR STATION ANNUAL REPORT l

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l PERIOD ENDING DECEMBER 3L 1977

TABLE OF CONTENTS VOLUME I

1. Non-Radiological Environmental Surveillance Report

1. Introduction

1. l ' Station Cooling Water Systems Thermal Limits 1.2 Chemical Discharge Limits 1.3 General Aquatic Surveillance 1.3.1 Water Quality 1.3.2 Fish-Population Dynamics and Reproduction 1.3.3 Periphyton ' ,

l.3.4 Phytoplankton-Zooplankton Receiving Water Study 1.3.5 Benthos 1.4 Fish Impingement on Intake Screens and Entrainment of Fish Eggs and Larvae 1.5 Phytoplankton-Zooplankton Entrainment Mortality Study 1.6 Plume Mapping for Temperature and Dissolved Oxygen 1.7 Gas-Bubble Disease Study II. Annual Operating Report

2. Introduction 2.1 Report for January,1977 2.2 Report for February, 1977 2.3 Report for March, 1977 ,

2.4 Report for April, 1977 2.5 Report for May, 1977 2.6 Report for June, 1977 2.7 Report for July, 1977 2.8 Report for August, 1977 )

j 2.9 Report for September, 1977 2.10 Report for October, 1977 2.11 Report for November,1977 2.12 Report for December,1977 2.13 Environmental Monitoring s

j 2.14 Personnel Exposure and Monitoring l

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TABLE OF CONTENTS VOLUME II Appendix A - Tabulated Water Quality Data Lakes Keowee and Hartwell 4

Appendix B - Tabulated Biological Data (Section 1,2,3)

VOLUME III Appendix B - Tabulation Biological Data (Section 3,4,5)

Appendix C - SERI Highlights of Activities for Fiscal Year 1977 Appendix D - SERI Report of Progress and Evaluation for Fiscal Year 1978 and Excerpts from Proposed Annual Work Plan for Fiscal Year 1979 Appendix E - Oconee Nuclear Station Plume Mapping Studies 1

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SECTION I NON-RAD 1'0 LOGICAL ENVIRONMENTAL SURVEILLANCE REPORT i

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1. INTRODUCTION This section of the Annual Report is submitted pursuant to the Non-Radiological Environmental Technical Specifications, Appendix B, to Operating Licenses DPR-38, DPR-47, and DPR-55. This section summarizes the Non-Radiological Envi-ronne.ntal Surveillance Program for Oconee Nuclear Station from Ja. aary 1 through December 31, 1977.

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1.1 STATION COOLING WATER SYSTDfS THERMAL LIMITS Specification: A. The cooling water effluent temperature at the discharge shall not exceed 100 F for a time period in excess'of two hours. In the event of the once-in-20 years com-bination of extreme natural conditions the station's generating capacity shall be' limited as necessary to keep the discharge temperature from exceeding 100 F unless there is a serious need for the lost power.

A serious need for lost power is defined here as a condition which would result in voltage reductions or load shedding (except contracted interruptable loads). Under these circumstances, the licensee '

shall notify AEC/ DOL immediately by telephone and *l the discharge temperature shall not be allowed to exceed 103 F.

B. Temperat'tre rises from the condenser intake to the discharge shall not exceed 28 F. Further, the  !

l temperature rise should not exceed 22 F when the~

inlet temperature is greater than 68 F.

i C. Normal station operations shall be programmed so l that effluent temperatures shall not decrease more than 6 F per hour during the winter and 10 F per ,

hour during the spring, summer, and fall (Duke l Power Company 1973a). i l

I. INTRODUCTION l

The noted specifications were established to minimize the effects of l thermal discharges on aquatic life in the vicinity of Oconee Nuclear Station. The limits on station discharge temperature, temperature rise across the condensers, ad the rate of decrease of the discharge temper-ature permit sufficier- operational flexibility to allow for the starting or shutdown of a cirr.lation water pump during unit load changes. Under normal operation, station procedures incorporate the programming of load changes to minimize the resulting transient thermal change.

II. METHODS AND MATERIALS The ONS daily average Condenser Cooling Watet -(CCW) intake and discharge temperatures and flow rates for the period January 1 through December 31, 3977 are presented in Table 1.1-1 and Figure 1.1-1. These. data represent a summary of the Environmental Monitoring Report (EMR) computer program.

The EMR computes the station flow rate, inlet temperature and outlet temperature continuously (intervals less than one minute) and prints hourly maximum, minimum, and average values. During periods of equip-ment failure, representative data readings are recorded manually.

1.1-1 ONS 12/77 i

III. RESULTS AND DISCUSSION With respect to Specification A, Table 1.1-1 and Figure 1.1-1 show that the maximum allowable discharge temperature of 100.0 F (37.8 C) was not exceeded at any time during the year 1977. The maximum daily average discharge temperature of.87.3 F (30.7 C) and the maximum hourly average discharge temperature of 88.1 F (31.2 C) both occurred on September 26.

The daily average inlet temperature ranged from a low of 42.8 F (6.0 C) on February 12 to a high of 75.7 F (24.3 C) on October 2.

With respect to Specification B, the temperature rise (AT) within the CCW system did not exceed 28.0 F (15.6 C ) nor did it exceed 22.0 F (12.2 C )

when the inlet temperature was greater than 68.0 F (20.0 C). The maximum '

hourly average AT when the inlet temperature was greater than 68.0 F (20.0 C) was 16.2 F (9.0 C ) which occurred on August 3. When the inlet temp-erature was less than 68.0 (20.0 C) the maximum hourly average AT was 25.1 F (13.9 C ) which occurred on January 3.

With respect to Specification C, the maximum allowable temperature decrease at the discharge was not exceeded during normal station operations or any other time. The maximum hourly temperature decrease at the CCW outlet for the winter period was 4.5 F (2.5 C ) whiti occurred on February 16.

The maximum hourly decrease in outlet temperature for the remainder of the year was 5.8 F (3.2 C ) which occurred on September 21.

A comparison of inlet and outlet temperatures in 1977 with previous years show temperatures to be cooler than both 1975 and 1976 (Figures 1.1-2 and 1.1-3). Inlet temperatures in February were 3-4 C colder than in any of the previous years (1973-1376) due to the extremely cold winter. The mean monthly discharge temperature during the summer months was also 3-4 C cooler than the two previous summers primarily because of the reduced thermal capacity of ONS due to refueling outages.

IV.

SUMMARY

AND CONCLUSIONS The operation of ONS in 1977 was well within the thermal limits for maxi-mum discharge temperature, maximum AT, and the maximum hourly decrease in AT. Temperature regimes both at the inlet and outlet were consider-ably cooler than in the past two years due to meteorology and ONS oper-ations.

l REFERENCES CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR-38 DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear i Station Units 1, 2 and 3, Duke Power Company, U.S. Atomic Energy Com--

mission, Docket Nos. 50-259, 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC) Washington D.C.

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1.1-2 ONS 12/77 i

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i-i, Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION '

January, 1977 DAY FLOW INLET TEMP. OUTLET TEMP.

x103 cpg AT g3/ min OF OC OF O C F' CO 1 1514.7 (5733.1), 49.3 (9.6) 71.9 (22.2) 22.6 (12.6) 2 1433.7 (5426.6) 49.1 (9.5) 72.8 (22.6) 23.7 3 1392.6 (13.1)

(5271.0) 49.0 (9.4) 73.0 (22.8) 24.0 (13.4) 4 1392.3 (5269.9) 49.0 (9.4) 73.0 (22.8) 24.0 (13.4) 5 1391.9 (5268.3) 49.1 (9.5) 73.1 (22.8) 24.0 6 1394.8 (13.3) -

(5279.3) 49.0 (9.4) 73.0 (22.8) 24.0 (13.4) -

7 1392.2 (5269.5) 49.0 (9.4) 73.0 (22.8) 24.0 8 1392.1 (13.4)

' (5269.1) 48.8 (9.4) 72.7 (22.6) 23.9 (13.2) 9 1392.6 (5271.0) 48.4 (9.1) 72.3 (22.4) 23.9 10 1396.9 (13.3)

(5287.3) 48.5 (9.2) 72.4 (22.4) 23.9 (13.2) 11 1393.5 (5274.4) 48.2 12 1392,2 (9.0) 72.0 (22.2) 23.8 (13.2)

(5269.5) 47.9 (8.8) 71.7 -(22.0) 23.8 (13.2) 13 1392.0 (5268.7) 47.7 (8.7) 71.7 (22.0) 24.0 14 1392.4 (13.3)

(5270.2) 47.4 (8.6) 71.3 (21.8) 23.9 (13.2) 15 1392.0 (5268.7) 47.3 (8.5) 70.1 (21.2) 22.8 16 1384.9 (12.7)

(5241.8) 41.4 (8.6) '63.3 (17.4) 15.9 ( 8.8) 17 1173.2 (4440.6) 47.5 (8.6) 66.6 (19.2) 19.1 18 1174,0 (10.6)

(4443.6) 47.1 (8.4) 66.2 (19.0) 19.1 (10.6) 19 1173.4 (4441.3) 46.7 (8.2) 66.0 20 (18.9) 19.3 (10.7) 1179.6 (4464.8) 46.5 (8.0) 65.6 (18.6) 19.1 (10.6) 21 1172.2 (4436.8) 46.5 (8.0) 65.6 19.1 22 1172.9 (18.6) (10.6)

(4439.4) 46.0 (7.8) 65.2 (18.4) 19.2 (10.6) 23 1172.8 (4439.0) 45.3 (7.4) 64.6 24 (18.1) 19.3 (10.7) 1172.7 (4438.7) 44.8 (7.1) 64.7 19.9 25 1172.2 (18.2) (11.1)

(4436.8) 44.9 (7.2) 64.9 (18.3) 23.0 (11.1) 26 1336.9 (5060.2) 45.2 (7.4) 67.4 -22.2 (19.6) (12.2) 27 1392.2 (5269.5) 45.3- (7.4) 69.2 (20.6) 23.9 28 1391.4 (13.2)

(5266.4) 44.9 * (7.2) 69.6 (20.9) 24.7 (13.7) 29 1390.3 (5262.3) 45.3 (7.4) 69.9 (21.0) 24.6 30 1390.2 (13.6)

(5261.9) 45.2 (7.4) 69.6 (20.9) 24.4 (13.5) 31 1421.4 (5380.0) 44.1 (6.7) 68.1 -(20.0) 24.0 (13.3)

Avg. Avg. Avg. Avg.

1333.1 47.2 69.6 22.4 ,

(5045.8) (8.4) (20.9) (12.5) 1.1-3 i

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Tabl e 1.1-1 "N _f.dRA. ORE MONITORING oCONEE hJCLEAR STATION Februa y, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 GPM M3 / min DF OC OF C F 8 ""' C 1 1275.9 (4829.3) 43.8 (6.6) 62.6 (17.0) 18.8 (10.4) 2 1340.8 (5074.9) 43.3 (6.3) 60.4 (15.8) 17.1 ( 9.5) 3 1390.3 (5262.3) 43.2 (6.2) 59.6 (15.4) 16.4 ( 9.2) 4 1177.8 (4458.0)- 43.5 (6.4) 63.4 (17.4) 19.9 (11.0) .

5 1195.3 (4524.2) 44.4 (6.9) 64.1 (17.8) 19.7 (10.9) 6 1390.7 (5263.8) 43.9 (6.6) 60.5 (15.8) 16.6 ( 9.2) 7 1390.6 -(5263.4) 43.6 (6.4) 60.3 (15.7) 16.7 ( 9.3).

8 1516.4 (5739.6) 43.3 (6.3) 64.1 (17.8) 20.8 (11.5) 9 1604.0 (6071.1) 43.5 (6.4) 64.7 (18.2) 21.2 (11.8) 10 1506.3 (5701.3) 43.3 (6.3) 66.2 (19.0) 22.9 (12.7) 11 1391.7 (5267.6) 43.1 (6.2) 67.6 (19.8) 24.5 (13.6) 12 1389.6 (5259.6) 42.8 (6.0) 67.2 (19.6) 24.4 (13.6) 13 1389.0 (5257.4) 42.9 (6.0) 67.0 (19.4) 24.1 (13.4) 14 1262.1 (4777.0) 42.9 (6.0) 64.2 (17.9) 21.3 (11.9) 15 1165.9 (4412.9) 43.1 (6.2) 62.6 (17.0) 19.5 (10.8) 16 1165.1 (4409.9) 43.3 (6.3) 62.8 (17.1) 19.5 (10.8) 17 1164.6 (4408.0) 43.3 (6.3) 62.7 (17.0) 19.4 (10.7) 18 1165.9 (4412.9) 43.4 (6.4) 62.9 (17.2) 19.5 (10.8) 19 1166.4 (4414.8) 43.8 (6.6) 63.3 (17.4) 19.5 (10.8) 20 1166.1 (4413.7) 45.4 (7.4) 64.9 (18.3) 19.5 (10.9) 21 1166.4 (4414.8) 44.5 (7.0) 64.1 (17.8) 19.6 (10.8) 22 1166.2 (4414.1) 44.6 (7.0) 64.2 (17.9) 19.6 (10.9) 23 1229.4 (4653.3) 44.9 . (7.2) 65.3 (18.5) 20.4 (11.3) 24 1390.0 (5261.2) 45.7 (7.6) 66.8 (19.4) 21.1 (11.8) 25 1390.9 (5264.6) 46.5 (8.0) 64.1 (17.8) 17.6 ( 9.8) 26 1390.6 (5263.4) 45.8 (7.6) 64.9 (18.3) 19.1 (10.7) 27 1389.7 (5260.0) 45.6 (7.6) 69.8 (21.0) 24.2 (13.4) 28 1540.7 (5831.5) 45.6 (7.6) 67.3 (19.6) 21.7 (12.0)

Avg. Avg. Avg. Avg.

1317.1 44.0 64.3 20.3 (4985.2) (6.6) (18.0) (11.4) 1.1-4

i Table 1.1-l' oCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION March, 1977

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DAY FLOW INLET TEMP. OUTLET TEMP. AT' x103 cpg g3/ min OF OC OF OC F0 CO 1 1576.2 (5965.9) 45.5 (7.5) 61.3 (16.3) 15.8 ( 8.8) 2 1406.6 (5324.0) 45.5 (7.5) 63.4 (17.4) 17.9 ( 9.9) 3 1362.9 (5158.6) 45.5 (7.5) 63.9 (17.7) 18.4 (10.2) 4 1362.2 s. 9) 45.6 (7.6) 63.9 (17.7) 18.3 (10.1) 5 1361.1 (5151.8) 45.6 (7.6) 64.0 (17.8) 18.4 (10.2) 6 1361.3 (5152.5) 45.6 (7.6) 64.1 (17.8) 18.5 (10.2) 7 1361.2 (5152.1) 45.5 (7.5) 63.5 (17.5) 18.0 (10.0) -

8 1362.2 (5155.9) 45.5 (7.5) 62.7 (17.0) 17.2 ( 9.5) 9 1362.6 (5157.4) 45.1 (7.5) 62.7 (17.0) 17.2 ( 9.5) 10 1227.1 (4644.6) 45.5 (7.5) 64.1 (17.8) 18.6 (10.3)-

11 1170.0 (4428.5) 45.4 (7.4) 64.6 (18.1) 19.2 (10.7) ,

12 1169.6 (4426.9) 45.4 (7.4) 64.8 (18.2) 19.4 (10.8) i 13 1219.1 (4614.3) 46.1 (7.8) 66.3 (19.0) 20.2. (11.2) 14 1553.8 (5881.1) 47.0 (8.4) 67.0 (19.4) 20.0 (11.0) l 15 1572.0 (5950.0) 47.2 (8.4) 66.9 (19.4) 19.7 (11.0)  ;

16 1387.9 (5253.2) 47.0 (8.4) 67.8 (19.9) 20.8 (11.5) 1 17 1388.1 (5254.0) 46.8 (8.2) 69.6 (20.9) 22.8 (12.7) 18 1388.5 (5255.5) 47.0 (8.4) 70.2 (21.2) 23.2 (12.8) 19 1388.3 (5254.7) 47.3 (8.5) 70.5 (21.4) 23.2 (12.9) 20 1387.9 (5253.2) 47.4 (8.6) 70.5 (21.4) 23.1 (12.8) 21 1387.7' (5252.4) 47.0 (8.4) 70.9 (21.6) 23.9 (13.2) 22 1387.6 (5252.1) 47.1 (8.4) 70.9 (21.6) 23.8 (13.2) 23 1385.5 (5244.1) 47.1 (8.4) 60.6 (15.9) 13.5 ( 7.5) 4 24 1295.2 (4902.3) 47.5 (8.6) 62.8 (17.1) 15.3 ( 8.5) l 25 1366.6 (5172.6) 47.8 (8.8) 64.4 (18.0) 16.6 ( 9.2) 26 1365.8 (5169.6) 48.0 (8.9) 64.7 (18.2) 16.7 ( 9.3) 27 1365.8 (5169.6) 48.1 (9.0) 65.0 (18.4) 16.9 ( 9.4) 28 1312.8 (4968.9) 48.1 (9.0) 64.6 (18.1) 16.5 ( 9.1) 4 29 1269.7 (4805.8) 48.4 (9.1) 64.6 (18.1) 16.2 ( 9.0)  ;

30 1247.0 (4719.9) 48.4 (9.1) 65.1 (18.4) 16.7 ( 9.3) l 31 1127.3 (4266.8) 48.8 (9.4) 66.8 (19.4) 18.0 (10.0) l Avg. Avg. Avg. Avg.

1351.0 46.7 65.6. 18.9 l (5113.5) ( 8.2) (18.6) (10.4) 1.1-5

m Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION April, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 CPM M3 / min OF OC OF C F0 CO 1 1157.7 (4382.0) 49.4 ( 9.6) 68.8 (20.4) 19.4 (10.8) 2 1159.9 -(4390.2) 49.1 ( 9.5) 68.5 (20.3) 19.4 (10.8) 3 1274.5 (4824.0) 48.9 ( 9.4) 67.4 (19.6) 18.5 (10.2) 4 1546.1 (5852.0) 50.0 (10.0) 70.5 (21.4) 20.5 (11.4) 5 1547.1 '(5855.8) 51.1 (10.6) 72.7 (22.6) 21.6 (12.0) -

6 1549.5 (5864.9) 51.0 (10.6) 71.9 (22.2) 20.9 (11.6) 7 1554.7 (5884.5) 51.5 ~(10.8) 71.7 (22.0) 20.2 (11.2) 8 1563.8 (5919.0) 51.4 (10.8) 73.4 (23.0) 22.0 (12.2) 9 1567.2 (5931.9) 50.5 (10.3) 72.6 (22.6) 22.1 (12.3) 10 1567.7 (5933.7) 50.5 (10.3) 72.5 (22.5) 22.0 (12.2) 11 1683.1 (6370.5) 50.9 (10,5) 71.6 (22.0) 20.7 (11.5) 12 1737.0 (6574.5) 51.2 (10.6) 71.5 (22.0) 20.3 (11.4) 13 1611.5 (6099.5) 51.4 (10.8) 69.9 (21.0) 18.5 (10.2) 14 1564.0 (5919.7) 51.4 (10.8) 73.0 (22.8) 21.6 (12.0) 15 1614.2 (6109.7) 51.6 (10.9) 73.4 (23.0) 21.8 (12.1) 16 1754.4 (6640.4) 52.2 (11.2) 72.5 (22.5) 20.3 (11.3) 17 1754.0 (6638.9) 52.3 (11.3) 72.8 (22.6) 20.5 (11.3) 18 1686.8 (6384.5) 52.3 (11.3) 73.3 (23.0) 21.0 (11.7) 19 1611.9 (6101.0) 52.6 (11.4) 74.0 (23.4) 21.4 (12.0) 20 1540.7 (5831.5) 52.8 (11.6) 74.8 (23.8) 22.0 (12.2) 21 1562.5 (5914.1) 52.5 (11.4) 74.6 (23.6) 22.1 (12.2) 22 1564.3 (5920.9) 52.7 (11.5) 74.3 (23.5) 21.6 (12.0) 23 1563.5 (5917.8) 52.9 (11.6) 72.5 (22.5) 19.6 (10.9) 24 1472.5 (5573.4) 53.2 (11.8) 70.2 (21.2) 17.0 ( 9.4) 25 1479.4 (5599.5) 52.9 (11.6) 72.3 (22.4) 19.4 (10.8) 26 1703.8 (6448.9) 53.2 (11.8) 72.5 (22.5) 19.3 (10.7) 27 1759.3 (6659.0) 53.5 (12.0) 72.2 (22.4) 18.7 (10.4) 28 1784.1 (6752.8) 54.1 (12.3) 73.8 (23.2) 19.7 (10.9) 29 1803.9 (6827.8) 54.3 (12.4) 74.6 (23.6) 20.3 (11.2) 30 1926.5 (7291.8) 53.7 (12.0) 72.8 (22.6) 19.1 (10.6)

Avg. Avg. Avg. Avg.

1588.8 51.9 72.3 20.4 (6013.6) (11.0) (22.4) (11.4) 1.1-6

i Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION May, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT

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x103 GPM M3 / min 9F OC OF OC F' CO 1 1924.6 (7284.6) 53.9 (12.2) 73.0 (22.8) 19.1 (10.6) 2 1922.1 (7275.1) 54.4 (12.4) 73.6 (23.1) 19.2 (10.7) 3 1909.8 (7228.6) 54.7 (12.6) 74.4 (23.6) 19.~7 (11.0) 4 1907.6 (7220.3) 54.9 (12.7) 75.0 (23.9) 20.1 (11.2) 5 1916.6 (7254.3) 54.8 (12.6) 74.3 (23.5) 19.5 (10.9) 6 1916.3 (7253.2) 55.1 (12.8) 74.2 (23.4) 19.1 (10.6) .

7 1819.4 (6886.4) 54.8 (12.6) 71.4 (21.9) 16.6 ( 9.3) 8 1752.0 (6631.3) 55.0 (12.8) 69.1 (20.6) 14.1 ( 7.8) 9 1663.0 (6294.5) 54.9 (12.7) 69.9 (21.0) 15.0 ( 8.3' 10 1548.7 (5861.8) 54.8 (12.6) 70.7 (21.5) 15.9- (8 11 1551.2 (5871.3) 55.2 (12.9) 71.0 (21.6) 15.8 (C 12 1552.5 (5876.2) 55.3 (13.0) 71.3 (21.8) 16.0 ( 8.6) 13 1552.6 (5876.6) 55.3 (13.0) 71.3 (21.8) 16.0 ( 8.8) i 14 1552.3 (5875.5) 55.2 (12.9) 71.1 (21.7) 15.9 ( 8.8) 15 1552.1 (5874.7) 55.4 (13.0) 71.4 (21.9) 16.0 ( 9.9) 16 1569.0 (5938.7) S5c6 (13.1) 71.4 (21.9) 15.8 ( 8.8) 17 1553.6 (5880.4) 55.9 (13.3) 71.9 (22.2) 16.0 ( S.9) 18 1552.8 (5877.3) 56.1 (13.4) 72.0 (22.2) 15.9 ( 8.8) 19 1546.0 (5851.6) 55.9 (13.3) 71.8 (22.1) 15.9 ( 8.8) 20 1542.3 (5837.6) 56.2 (13.4) 72.1 (22.3) 15.9 ( 8.9) 21 1540.6 (5831.2) 56.3 (13.5) 72.2 (22.4) 15.9 ( 8.9) 22 1540.2 (5829.7) 56.5 (13.6) 72.6 (22.6) 16.1 ( 9.0) 23 1579.6 (5978.8) 56.5 (13.6) 74.0 (23.4) 17.5 ( 9.8) 24 1761.4 (6666.9) 56.9 (13.8) 74.0 (23.4) 17.1 ( 9.6) 25 1754.5 (6640.8) 57.3 (14.0) 75.3 (24.0) 18.0 (10.0) 26 1794.3 (6791.4) 57.7 (14.3) 75.4 (24.1) 17.7 ( 9.8) 27 1759.5 (6659.7) 57.5 (14.2) 76.0 (24.4) 18.5 (10.2) 28 1712.1 (6480.3) 57.8 (14.4) 75.5 (24.2) 17.7 ( 9.8) 29 1418.4 (5368.4) 57.5 (14.2) 72.7 (22.6) 15.2 ( 8.4) 30 1400.0 (5299.0) 57.4 (14.1) 73.1 (22.8) 15.7 ( 8.7) 31 1551.8~ (5873.6) 57.8 (14.4) 73.6 (23.1) 15.8 ( 8.7)

Avg. Avg. Avg. Avg.

1665.1~ 55.9 72.8 16.9 (6302.4) (13.3) (22.6) (9.3)

.1.1-7

Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION June, 1977 4 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 CPM M3 / min OF OC OF OC FC CO 1 1551.8 (5873.6) 58.1 (14.5) 73.9 (23.3) 15.8 ( 8.8) 2 1570.8 (5945.5) 58.2 (14.6) 73.6 (23.1) 15.4 ( 8.5) 3 1560.8 (5907.6) 58.3 (14.6) 74.0 (23.4) 15.7 ( 8.8) 4 1558.1 (5897.4) 58.6 (14.8) 74.6 (23.6) 16.0 ( 8.8) 5 1559.5 -(5902.7) 59.0 (15.0) 75.2 (24.0) 16.2 ( 9.0) .

6 1425.4 (5395.1) 59.3 (15.2) 72.3 (22.4) 13.0 ( 7.2) 7 1119.9 (4238.8) 59.5 (15.3) 76.3 (24.6) 16.8 ( 9.3) 8 1283.0 (4856.2) 59.4 (15.2) 77.9 (25.5) 18.5 (10.3) 9 1319.4 (4993.9) 60.0 (15.6) 79.0 (26.1) 19.0 (10.5) 10 1318.8 (4991.7) 59.6 (15.4) 77.6 (25.4) 18.0 (10.0) 11 1020.8 (3863.7) 59.5 (15.3) 73.1 (22.8) 13.6 ( 7.5) 12 905.7 (3428.1) 60.0 (15.6) 75.0 (23.9) 15.0 ( 8.3) l 13 900.7 (3409.1) 59.7 (15.4) 74.5 (23.6) 14.8 ( 8.2) 14 -896.0 (3391.4) 59.9 (15.5) 74.3 (23.5) 14.4. ( 8.0) 15 894.5 (3385.7) 60.0 (15.6) 74.5 (23.6) 14.5- ( 8.0) 16 893.5 (3381.9) 59.9 (15.5) 74.4 (23.6) 14.5 ( 8.1)

+

17 893.0 (3380.0) 60.2 (15.6) 74.6 (23.6) 14.4 ( 8.0) 18 892.4 (3377.7) 60.3 (15.7) 74.8 (23.8) 14.5 ( 8.1) 19 891.1 (3372.8) 60.6- (15.9) 75.1 (24.0) 14.5 ( 8.1) 20 891.3 (3373.6) 60.6 (15.9) 75.0 (23.9) 14.4 -( 8.0) 21 894.1- (3384.2) 61.0 (16.1) . 75.3 (24.0) 14.3 ( 7.9) 22 1078.2 (4081.0) 60.5 (15.8) 72.4 (22.4) 11.9 ( 6.6) 23 1117.7 (4230.5) 61.1 (16.2) 72.8 (22.6)' 11.7 ( 6.4) 24 1113.1 (4213.1) 61.2 (16.2) 72.8 (22.6) 11.6 ( 6.4) 25 1112.6 (4211.2) 61.5 (16.4) 73.1 (22.8) 11.6 ( 6.4) 26 1113.3 (4213.8) 61.4 (16.4) 73.1 (22.8) 11.7 ( 6.4) 27 1111.8 (4208.2) 61.6 (16.4) 77.8 (25.4) 16.2 ( 9.0) -

28 1282'.7 (4855.0) 61.6 (16.4) 78.9 (26.0) 17.3 ( 9.6) 29 1293.0 (4894.0) 62.1 (16.7) 80.3 (26.8) 18.2 (10.1) 30 1294.6 (4900.1) 62.0 (16.6) 80.4 (26.9) 18.4 (10.3)

Avg. Avg. Avg. Avt.

1158.6 60.1 75.3 15.2 (4385.3) (15.6) (24.0) (8.4)

W 1.1-8

• 4 + ~ ,

Table 1.1-1 CCW TEMPERATURE MONITORING

, OCONEE NUCLEAR STATION July, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT

~"'

x103 GPM M3 / min 9F OC OF O C F' CO 1 1296.6 (4907.6) 62.3 (16.8) 81.5 (27.5) 19.2 (10.7) 2 1300.9 (4923.9) 62.3 (16.8) 81.7 (27.6) 19.4 (10.8) 3 1305.1 (4939.8) 62.1 (16.7) 81.4 (27.4) 19.3 (10.7) 4 1306.0 (4943.2) 63.0 (17.2) 82.4 (28.0) 19.4 (10.8) 5 1303.6 -(4934.1) 63.1 (17.3) 76.5 (24.7) 13.4 ( 7.4) 6 1302.4 (4929.6) 63.3 (17.4) 78.4 (25.8) 15.1 ( 8.4) 7 1424.4 (5391.4) 63.5 (17.5) 76.6 (24.8) 13.1 ( 7.3) ~

8 1658.5 (6277.4) 63.8 (17.6) 75.4 (24.1) 11.6 ( 6.5) 9 1742.7 (6596.1) 64.2 (17.9) 75.5 (24.2) 11.3 ( 6.3) 10 1406.2 (5322.5) 64.1 (17.8) 77.8 (25.4) 13.7 ( 7.6) 11 1549.1 (5863.3) 64.4 (18.0) 77.3 (25.2) 12.9 ( 7.2) 12 1542.4 (5838.0) 64.6 (18.1) 79.1 (26.2) 14.5 ( 8.1) 13 1547.6 (5857.7) 64.6 (18.1) 79.3 (26.6) 15.2 ( 8.5) 14 1547.5 (5857.3) 64.9 (18.2) 79.4 (26.4) 14.5 ( 8.2) 15 1389.4 (5258.9) 65.1 (18.4) 73.8 (23.2) 8.7 ( 4.8) 16 1139.1 (4311.5) 65.5 (18.6) 76.0 (24.4) 10.5 ( 5.8) 17 1139.5 (4313.4) 65.6 (18.6) 76.1 (24.5) 10.5 ( 5.9) 18 1167.0 (4417.1) 65.8 (18.8) 76.0 (24.4) 10.2 ( 5.6) 19 1139.2 (4311.9) 66.0 (18.9) 76.6 (24.8) 10.6 ( 5.9) 10 1138.7 (4310.0) 66.1 (19.0) 76.7 (24.8) 10.6 ( 5.8) 21 1138.5 (4309.2) 66.3 (19.0) 77.1 (25.0) 10.8 ( 6.0) 22 1218.9 (4613.5) 66.3 (19.0) 76.7 (24.8) 10.4 ( 5.8) 23 1274.3 (4823.2) 66.3 (19.0) 76.0 (24.4) 9.7 ( 5.4) 24 1155.5 (4373.6) 66.8 (19.4) 77.8 (25.4) 11.0 ( 6.0) 25 1143.1 (4326.6) 66.9 (19.4) 78.1 (25.6) 11.2 ( 6.2) 26 1142.3 (4323.6) 67.1 ' (19.5) 78.3 (25.7) 11.2 ( 6.2) 27 1333.0 (5045.4) 66.7 (19.3) 80.8 (27.1) 14.1 ( 7.8) 28 1.353.9 (5162.4) 67.2 (19.6) 81.6 (27.6) 14.4 ( 8.0) 29 1364.2 (5163.5) 67.1 (19.5) 81.6 (27.6) 14.5 ( 8.1) 30 1361.8 (5154.4) 67.6 (19.8) 81.9 (27.7) 14.3 ( 7.9) 31 1426.8 (5400.4) 67.7 (19.8) 82.2 (27.9) 14.5 ( 8.1)

Avg. Avg. Avg. Avg.

1331.2 65.1 78.4 23.3 (5038.6) .(18.4) (25.8) (7.4) 1.1-9

Table 1.1-1 <

CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION August, 1977 )

DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 GPM M3 / min OF OC OF OC F' CO 1- - 1742.2 (6594.2) 68.0 (20.0) 80.8 (27.1) 12.8- (7.1) 2 1747.8 (6615.4) 68.2 (20.1) 81.6 (27.6) 13.4 (7.5) 3 - 1747.7 (6615.0) 68.3 (20.2) 81.8 (27.6) 13.5 (7.4) 4 1747.8 (6615.4) 68.5 (20.3) 82.0 (27.8) 13.5 (7.5) 5 1707.9 (6464.4) 68.9 (20.5) 79.5 (26.4) 10.6 (5.9) -

~

6 1661.3 (6288.0) 69.0 (20.6) 76.5 (24.7) 7.5 (4.1) 7' 1662.8 (6293.7) 69.6 (20.9) 77.0 (25.0) 7.4 (4.1) 8 1662.0 (6290.7) 69.5 (20.8) 76.8 (24.9) 7.3 (4.1) 9 1605.8 (6078.0) 69.8 (21.0) 77.2 (25.1) 7.4 (4.1) 10 1663.3 (6295.6) 70.0 (21.1) 77.2 (25.1) 7.2 (4.0) 11 1665.5 (6303.9) 70.4 (21.4) 77.7 (25.4) 7.3 (4.0) 12 1666.7 (6308.5) 70.4 (21.4) 77.6 (25.4) 7.2 (4.0) 13 1300.2 (4921.3) 70.6 (21.4) 79.8 (26.6) 9.2 (5.2) 14 1209.3 (4577.2) 70.7 (21.5) 80.7 (27.0) 10.0 (5.5) 15 1204.1 (4557.5) 70.6 (21.4) 80.7. (27.0) 10.1 (5.6) 16 1202.3 (4550.7) 70.9 (21.6) 81.0 (27.2) 10.1 (5.6) 17 1200.4 (4543.5) 71.1 (21.7) 81.1 (27.3) 10.0 (5.6) 18 1198.4 (4535.9) 71.1 (21.7) 81.1 (27.3) 10.0 (5.6) 19 1265.3 (4789.2) 71.0 (21.6) 80.4 (26.9) 9.4 (5.3) 20 1398.1 (5291.8) 71.3 (21.8) 76.6 (24.8) 5.3 (3.0) 21 938.9 (3553.7) 71.6 (22.0) 72.1 (22.3) 0.5 (0.3) 22 1173.3 (4440.9) 71.5 (22.0) 76.1 (24.5) 4.6 (2.5) 23 1284.7 (4862.6) 71.6 (22.0) 77.2 (25.1) 5.6 (3.1) 24 1514.2 (5731.2) 71.6 (22.0) 78.0 (25.6) 6.4 (3.6) 25 1598.3 (6049.5) 71.8 (22.1) 78.2 (25.6) 6.4 (3.5) 26 1567.3 (5932.2) 71.8 (22.1) 79.0 (26.1) 7.2 (4.0) 27 1653.2 (6257.4) 72.2 (22.4) 79.7 (26.5) 7.5 (4.1) 28 1661.9- (6290.3) 72.6 (22.6) 80.9 (27.2) 8.3 (4.6) 29 1663.9 (6297.9) 72.7 (22.6) 82.9 (28.3) 10.2 (5.7) 30 1665.8 (6305.1) 72.8 (22.6) 82.9 (28.3)- 10.1 (5.7) 31 1778.3 -(6730.9) 72.8 (22.6) 83.3 (28.5) 10.5 (5.9)

Avg. Avg. Avg. Avg.

1508.3 70.6 79.4- 8.8 (5708.9) (21.4) (26.4) (5.0) 1.1-10

_ _ _ _ _ _ _ .- .=

l Table 1.1-1 CCW TEMPERATURE MONITORING

, OCONEE NUCLEAR STATION September, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. ~AT x103 CPM M3/ min 9F IC OF OC F' CO 1 1826.9 (6914.8) 73.1 (22.8) 84.4 (29.1) 11.3 (6.3) 2 1795.7- (6796.7) 73.2 (22.9) 82.5 (28.0) 9.3 (5.1) 3 1710.7 (6475.0) 73.3 (23.0) 83.2 (28.4) 9.9 (5.4) 4 1731.1 (6552.2) 73.4 (23.0) 83.2 (28.4) 9.8 (5.4) 5 1800.7 (6815.6) 73.5 (23.0) 84.8 (29.4) 11.3 (6.4) 6 1857.0 (7028.7) 73.8 (23.2) 85.3 (29.6) 11.5 7 1899.9 (7191.1) 73.9 (23.3) 85.5 11.6 (6.4) '

(29.7) (6.4) 8 1895.3 (7173.7) 74.0 (23.4) 84.8 (29.4) 10.8 (6.0) 9 1844.2 (6980.3) 73.8 (23.2) 84.0 (28.9) -10.2 (5.7) 10 1896.0 (7176.4) 74.5 (23.6) 85.9 (30.0) 11.3 (6.4) 11 1864.0 (7055.2) 74.6 (23.6) 84.8 (29.4) 10.2 (5.8) 12 1671.0 (6324.7) 74.2 (23.4) 81.7 (27.6) 7.5 (4.2) 13 1672.8 (6331.5) 74.2 (23.4) 81.6 (27.6) 7.4 (4.2) 14 1659.0 (6279.3) 74.5 (23.6) 81.8 (27.6) 7.3 (4.0) 15 1671.1 (6325.1) 74.5 (23.6) 81.7 (27.6) 7.2 (4.0) 16 1667.0 (6309.6) 74.5 (23.6) 81.6 (27.6) 7.1 (4.0) 17 1667.5 (6311.5) 74.8 (23.8) 82.0 (27.8) 7.2 (4.0) 18 1749.3 (6621.1) 74.8 (23.8) 81.6 (27.6) 6.8 (3.8) 19 1855.3 (7022.3) 74.9 (23.8) 81.4 (27.4) 6.5 (3.6) 20 1854.6 (7019.7) 74.7 (23.7) 81.3 6.6 (27.4) (3.7) 21 1951.3 (7385.7) 74.6 (23.6) 80.9 (27.2) 6.3 (3.6) 22 1949.9 (7380.4) 74.6 (23.6) 80.8 (27.1) 6.2 (3.5) 23 1961.1 (7422.8) 74.6 (23.6) 81.0 (27.2) 6.4 (3.6) 24 1910.8 (7232.4) 74.7 (23.7) 81.1 (27.3) 6.4 (3.6) 25 1881.0 (7119.6) 74.9 (23.8) 84.9 (29.4) 10.0 (5.6) 26 1827.5 (6917.1) 75.0 (23.9) 87.3 (30. 7) 12.3 (6.8) 27 1871.1 (7082.1) 75.1 (24.0) 87.1 (30.6) 12.0 (6.6) 28 2053.7 (7773.3) 75.3 (24.0) 84.6 (29.2) 9.3 (5.2) 29 2097.6 (7939.4) 75.3 (24.0) 84.6 (29.2) 9.3 (5.2) 30 2102.4 (7957.6) 75.4 (24.1) 84.7 (29.3) 9.3 (5.2)

Avg. Avg. Avg. Avg.

1839.9 74.4 83.4 9.0 (6964.0) (23.6) (28.6) (5.0) j f

+

1.1-11

Table 1.1-1 CCW TEMPERATUP.E MONITORING OCONEE NUCLEAR STATION October, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 'GMi 'M3 / min 9F OC OF OC F# "" CO 1 2101.8 (7955.3) 75.4 (24.1) 84.6 (2s.2) 9.2 (5.1) 2 2098.0 (7940.9) 75.7 (24.3) 84.7 (29.3) 9.0 (5.0) 3 2104.9 (7967.0) 75.5 (24.2) 84.4 (29.1) 8.9 (4.9) 4 2110.5 (7988.2) 75.4 ("4.1) 84.1 (29.0) 8.7 (4.9) 5 2115.1 (8005.7) 75.3 (24.0) 83.8 (28.8) 8.5 (4.8) 6 2116.6 (8011.3) 75.2 (24.0) 83.9 (28.8) 8.7 (4.8) .

7 2061.0 (7800.9) 74.9 (23.8) 83.2 (28.4) 8.3 (4.6) 8 1884.7 (7133.6) 74.6 (23.6) 80.3 (26.8) 5.7 (3.2) 9 1860.8 (7043.1) 74.5 (23.6) 80.3 (26.8) 5.8 (3.2) 10 1883.4 (7128.7) 74.0 (23.4) 79.7 (26.5) 5.7 (3.1) 11 1084.6 (7133.2) 73.7 (23.2) 79.3 (26.3) 5.6 (3.1) 12 1884.4 (7132.5) 73.4 *

(23.0) 79.1 (26.2) 5.7 (3.2) 13 1754.3 (6640.0) 72.7 (22.6) 76.1 (24.5) 3.4 (1.9) 14 1885.9 (7138.1) 72.4 (22.4) 76.5 (24.7) 4.1 (2.3) 15 1887.7 (7144.9) 71.9 (22.2) 77.3 (25.2) 5.4 (3.0) 16 1888.6 (7146.4) 71.3 (21.8) 76.8 (24.9) 5.5 (3.1) 17 1886.9 (7141.9) 70.5 (21.4) 77.3 (25.2) 6.8 (3.8) 18 1890.6 (7155.9) 70.1 (21.2) 76.9 (25.0) 6.8 (3.8) 19 1890.1 (7154.0) 69.7 (21.0) 77.9 (25.5) 8.2 (4.5) 4 20 1874.7 (7095.7) 69.3 (20.7) 77.1 (25.0) 7.8 (4.3) 21 1679.0 (6355.0) 69.0 (20.6) 76.8 (24.9) 7.8 (4.3) 22 1450.1 (.' 488. 6) 68.6 (20.4) 72.0 (22.2) 3.4 (1.8) 23 1372.9 (1196.4) 68.3 (20.2) 71.6 (22.0) 3.3 (1.8) 24 1373.6 (5139.1) 68.0 (20.0) 71.2 (21.8) 3.2_ (1.8) 25 1427.4 (5402.7) 67.7 (19.8) 71.5 (22.0) 3.8 (2.2) 26 1492.1 (5647.6) 67.6 (19.8) 71.7 (22.1) 4.1 (2.3) 27 1489.2 (5636.6) 67.4 (19.6) 71.0 (21.6) 3.6 (2.0) 28 1491.3 (5644.6) 67.2 (10.6) 73.0 (22.8) 5.8 (3.2) 29 1493.5 (5652.9) 67.0 (19.4) 77.7 (25.4) 10.7 (6.0) 30 1493.9 (5654.4) 66.9 (19.4) 78.1 (25.6) 11.2 (6.2) 31 1494.0 (5654.8) 66.7 (19.3) 77.9 (25.5) 11.2 -('.2) 6 Avg; Avg. Avg. Avg.

1784.6 71.7 78.5 6.8

.(6754.7) (22.0) (25.8) (3.8)

-1.1-12

1 l

l Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION I November, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 CPM M3 / min OF 6'C OF OC F0 CO 1 1412.7 (5347.1) 66.7 (19.3) 78.3 (25.7) 11.6 (6.4) 2 1298.8 (4916.0) 66.6 (19.2) 79.5 (26.4) 12.9 (7.2) 3 1298.9 (4916.3) 66.6 (19.2) 78.7 (26.0) 12.1 (6.8) 4 1298.5 (4914.8) 66.5 (19.2) 70.6 (21.4) 4 '.1 (2.2) l 5 1002.1 (3792.9) 66.4 (19.1) 70.6 (21.4) 4.2 (2.3) 6 947.6 (3586.7) 65.9 (18.8) 72.6 (22.6) 6.7 (3.8) 7 917.3 (3472.0) 65.8 (18.8) 74.9 (23.8) 9.1 (5.0) .

8 917.2 (3471.6) 65.7 (18.7) 75.3 (24.0) 9.6 (5.3) 9 917.3 (3472.0) 65.7 (18.7) 75.4 (24.1) 9.7 (5.4) 10 917.2 (3471.6) 65.7 (18.7) 75.2 (24.0) 9.5 (5.3) 11 919.3 (3479.6) 65.2 (18.4) 75.2 (24.0) 10.0 (5.6) 12 947.8 (3587.4) 64.5 (18.0) 77.0 (25.0) 12.5 (7.0) 13 918.3 (3475.8) 63.9 (17.7) 76.3 (24.5) 12.2 (6.8) 14 918.5 (3476.5) 63.3 (17.4) 78.4 (25.8) 15.1 (8.4) 15 918.8 (3477.7) 63.0 (17.2) 79.1 (26.2) 16.1 (9.0) 16 919.0 (3478.4) 62.7 (17.0) 78.4 (25.8) 15.7 (8.8) 17 1155.6 (4373.9) 62.6 (17.0) 75.5 (24.2) 12.9 (7.2) 18 1582.9 (5991.3) 62.6 (17.0) 72.3 (22.4) 9.7 (5.4) 19 1582.7 (5990.5) 62.3 (16.8) 72.1 (22.3) 9.8 (5.5) 20 1583.3 (5992.8) 62.0 (16.6) 71.8 (22.1) 9.8 (5.5) 21 1584.3 (5996.6) 61.9 (16.6) 71.6 (22.0) 9.7 (5.4) 22 1582.6 (5990.1) 61.8 (16.6) 71.5 (22.0) 9.7 (5.4) 23 1582.7 (5990.5) 61.7 (16.5) 71.7 (22.0) 10.0 (5.5) 24 1581.9 (5987.5) 61.6 (16.4) 73.0 (22.8) 11.4 (6.4) 25 1581.0 (5984.1) 61.5 (16.4) 73.4 (23.0) 11.9 (6.6) 26 1505.8 (5699.5) 61.1 (16.2) 74.0 (23.4) 12.9 (7.2) 27 1357.3 (5137.4) 60.5 (15.8) 75.1 (24.0) 14.6 (8.2) 28 1358.6 (5142.3) 60.0 (15.6) 74.9 (23.8) 14.9 (8.2) '

29 1368.0 (5177.9) 59.8 (15.4) 74.4 (23.6) 14.6 (8.2) 30 1358.4 (5141.5) 59.6 (15.3) 73.4 (23.0) 13.8 (7.7) ,

Avg. Avg. Avg. Avg.

1241.1 63.2 74.4 11.2 (4697.6) (17.4) (23.6) (6.2) j l

l I

l l

l 1.1-13

Table 1.1-1 CCW TEMPERATURE MONITORING OCONEE NUCLEAR STATION December, 1977 DAY FLOW INLET TEMP. OUTLET TEMP. AT x103 cp3 g3/ min OF OC OF C FO "~ CO 1 1359.2 (5144.6) 59.6 (15.4) 73.8 (23.2) 14,2 ( 7.8) 2 1352.3 (5118.5) 59.6 (15.4) 69.0 (20.6) 9.4 ( 5.2) 3 1358.4- (5141.5) 59.3 (15.2) 68.6 (20.4) 9.3 ( 5.2) 4 1570.0 (5942.5) 59.5 (15.3) 69.4 (20.Ph . 9.9 ( 5.5) 5 1580.2 (5981.1) 59.3 (15.2) 69.3 (20.7) 10.0 ( 5.5) 6 1484.1 (5617.3) 59.1 (15.0) 67.7 (13.8) 8.6 ( 4 8) 7 1456.0 (5511.0) 58.4 (14.6) 66.9 (19.4) 8.5 ( 4.8) -

8 1579.7 (5979.2) 57.7 (14.3) 68.4 420.2) 10.7 ( 5.9) 9 1379.4 (5221.0) 57.6 (14.2) 69.3 (20.7) 11.7 ( 6.5) 10 1165.3 (4410.7) 57.4 (14.1) 66.6 '(19.2) 9.2 ( 5.1) 11 1224.2 (4633.6) 56.2 (13.4) 69.4 (20.8) 13.2 ( 7.4) 12 1480.0 (5601.8) 55.8 (13.2) 70.2 (21.2) 14.4 ( 8.0) 13 1581.2 (5984.8) 55.7 (13.2) ~ 71.3 (21.8) 15.6 ( 8.6) 14 1581.1 (5984.5) 55.4 (13.0) 71.3 (21.8) 15.9 ( 8.8) 15 1579.0 (5976.5) 55.3 (13.0) 72.8 (22.6) 17.5 ( 9.6) 16 1701.3 (6439.4) 55.2 (12.9) 72.3 (22.4) 17.1 ( 9.5) 17 1719.5 (6508.3) 55.1 (12.8) 72.2 (22.4) 17.1 ( 9.6) 18 1729.0 (6544.3? 54.9 (12.7) 72.4 (22.4) 17.5 ( 9.7) 19 1735.2 (6567.7) 54.8 (12.6) 72.5 (22.5) 17.7 ( 9.9) 20 1760.1 (6662.0) 54.6 (12.6) 71.6 (22.0) 17.0 ( 9.4) 21 1571.1 (5946.6) 54.7 (12.6) 67.6 (19.8) 12.9 ( 7.2) 22 1452.6 (5498.1) 54.8 (12.6) 68.4 (20.2) 13.6 ( 7.6) 23 1569.8 (5941.7) 54.5 (12.5) 67.2 (19.6) 12.7 ( 7.1) 24 1570.5 (5944.3) 54.3 (12.4) -

68.0 (20.0) 13.7 ( 7.6) 25 1569.6 (5940.9) 54.2 (12.4) 71.7 (22.0) 17.5 ( 9.6) 26 1570.4 (5944.0) 53.8 (12.1) 72.0 (22.2) 18.2 (10.1) 27 1760.3 (6662.7) 53.2 (11.8) 70.8 (21.6) 17.6 ( 9.8) 28 1767.8 (6691.1) 52.8 (11.6) 68.7 (20.4) 15.9 ( 8.8) 29 1762.2 (6670.0) 52.3 (11.3) 69.0 (20.6) 16.7 ( 9.3) 30 1456.7 (5513.6) 51.9 (11.0) 66.3 (19.0) 14.4 ( 8.0) 31 1525.3 (5773.3) 51.7 (11.0) 66.9 (19.4) 15.2 ( 8.4)

Avg. Avg. Avg. Avg.

1546.8 55.6 69.8 14.2 (5854.6) (13.1) (21.0) (7.9) l

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1.2 CHDfICAL DISCHARGE LIMITS Specification:

A. Limits for certain chemical wastes and pH of water released from the

' Waste Water Treatment System and the Low Level Radwaste System shall not exceed the concentrations indicated in Table 1.2-1, " Limits and Monitoring Requirements on Certain Chemicals and pH of Water Released from Oconee Nuclear Station."

-B. Chlorine or other chemical biocides will not be used for condenser

cleaning.

I. INTRODUCTION The noted specifications were, established to insure that chemical concentrations in the river resulting from station discharges are not toxic to aquatic organisms. A chemical inventory is maintained to determina what quantities of environmentally significant chemicals are ur_ed and thus to estimate the quantities which are discharged over the period of interest. In addition, the pH of the waste water collection basin and effluent from the plant site is determined and recorded daily, and corrective measures are initiated as necessary.

II. RESULTS AND Colm SIONS Table 1.2-2 lists the dates on which discharges from the yard drains were outside the specified chemical or pH limits.

i l

l 1.2-1

Table 1.2-1

, Limits and Monitoring Requirements on Certain Chemicals and pH of i

Water Released from Oconee Nuclear Station Type Waste Water Treatment System, Low Level Rad Waste System Monitoring Frequency b Limit Frequency Limit pH Daily 6.0 - 9.0 Hydrazine Daily 0.7 ppm Prior to Release 0.1 ppm Boron Prior to Release 1.0 ppm ,.

" Monitored at point of release to Hartwell Reservoir, b

Concentrations are measured prior to point of discharge. Limits apply on downstream incremental increases in concentration in the Hartwell Reservof

following dilution in the Keovee tailrace.

0 3

1 6

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1.2-2

TABLE 1.2-2 January - December, 1977 Time d 3/15/77- 1715 8.5 (Note 1) 2000 8.4 2200 8.5 ~'

2240 8.4 J

3/16/77 0010' 8.5 0120 9.2 0400 8.4 0530 8.5 0600 8.3 1 4/18/77 1500 9.3 (Note 2 & 3).

1625 9.7 1730 8.8

. l 4

5/1/77 1740 9.1 (Note 4) 1 1920 9.1 2015' 7.2 Notes:

(1) Incident Report B-595 (2) Effective March 17, 1977, yard drain pH limits 6.'0

.9.0.

(3) . Incident Report B-615

~(4) Incident Reprot B-620 D

l.'2-3

a. -

1.3 ' GENERAL AQUATIC SURVEILLANCE Specification: Surveillance programs shall be conducted to detect and quantify Oconee's effects on water quality, fish, periphyton, plankton, and benthos (Duke Power Company, 1973a).

I. I'NTRODUCTION The objective of the aquatic surveillance program is to determine the effects of Oconee Nuclear Station's (ONS) operation on the aquatic ecosystem of Lake Keowee and the area of Lake Hartwell influenced by ONS thermal and chemi- "

cal discharges. The current environmental monitoring programs on Lakes Keowee -

and Hartwell are summarized in Table 1.3-1. Sampling locations are shown in Figures 1.3-1 and 1.3-2.

l This annual report covers the third full year in which all three Oconee Nu-clear Station (ONS) units were commercially operational and the fifth year of the non-radiological aquatic surveillance program (Section 1.3) and re-lated studies (Sections 1.4 through 1.7).

The ONS " Environmental Summary Report 1971 - 1976" (Duke Power Company 1977) described the effects of ONS operation on the aquatic environment and con-cluded that no major adverse environmental impacts had occurred. The information gathered in 1977 supports this conclusion. For the year, ONS average condenser cooling water flows and AT's (Section 1.1) were similar to 1976 and somewhat lower than in 1975. Intake temperatures in January through March,1977, were three to four degrees (C) colder than in previous years (1973 - 1976) due to the unusually cold winter. During the summer months, the monthly mean ONS discharge temperatures were 3 to 4 C* colder than in 1975 or 1976, primarily because of the reduced operation of ONS due to re-fueling outages. At the same time, however, exceptionally warm weather in July caused surface temperatures in areas of Lake Keowee not influenced by ONS to be slightly higher this summer than in previous summers.

II. GENERAL CONCLUSIONS Detailed descriptions and results of the General Aquatic Surveillance studies and other related~ studies are presented in Subsections 1.3.1 through 1.3.5 and Sections 1.4 through 1.7, respectively. . Some general conclusions bssed on the data presented in Sections 1.3 through 1.7 of this report art as follows:

l

1. As concluded in the ONS Environmental Summary Report 1971 - 1976 (Duke Power Company 1977), Lake Keowee is inhabited by an aquatic community whose species composition is typical of a piedmont reservoir. The over-l all abundance of aquatic organisms is relatively low, as would be ex-pected because of the reservoir's low nutrient concentrations.

2. Water quality characteristics of Lakes Keowee and Hartwell (Subsection

.1.3.1) were very similar this year compared to previous reporting per-iods. .Both lakes exhibited thermal stratification in Spring, Summer

.and early Fall. As a result of this,.the bottom waters exhibited lower dissolved oxygen and pH and higher ammonia, iron and manganese concen-trations during stratification.

l.3-1 ONS 12/77

3. The effects of ONS operation on temperature ud dissolved oxygen concentrations in the lake were documented during the twelve monthly synoptic water quality surveys (Subsection 1.3.1) and six plume mapping surveys (Section 1.6). ONS discharge temperatures were high-er than " ambient" surface temperatures for the periods January through March,and October through December. A " thermal plume" was not evident from April through September, however, due to the use of cool bottom layers of the lake for condenser cooling water.

Weekly monitoring of dissolved oxygen (Subsection 1.3.1) near ONS and Keowee Hydro' showed spatial and tempora 1' patterns similar to those reported previously. The minimum ONS intake and discharge concentrations were 4.4 and 4.6 mg/1, respectively, which occurred .

on September 8. Values at the Keowee Hydro intake and tailrace and at Location 605.0 never dropped below 5 mg/1.

4. Periphyton (Subsection 1.3.3) community composition was similar to previous years except that chrysophytes were more abundant at all locations in 1977. Organic accumulation rates and densities were somewhat lower during the mid-summer of 1977 than in previous years.

This was a lake-wide phenomenon, and may have been related to the surface water temperatures, which were higher than those in previous years. Blue-greens cor,tinued to comprise only a small percentage of the periphyton community.

5. Phytoplankton (Subsection 1.3.4) taxonomic composition and standing crops showed patterns similar to those reported previously. Green algae (espec-ially desmids) were more abundant in the Little River arm of the lake this summer than in previous years. During thermal stratification, Phytoplank-ton were much lesc abundant in the bottom waters of Lake Keowee than in surface waters. As a result, ONS intake and discharge waters had lower standing crops than sampling stations in the plume, which were, in turn, lower than at areas not directly influenced by the ONS discharge plume.

6. Zooplankton (Subsection 1.3.4) abundance showed trends which directly parallel the temporal and spatial distribution described for phyto-plankton. Zooplankton densities in 1977 were, however, generally lower than in previous years.

7. The benthic community (Subsection 1.3.5), as in previous reports, was dominated by chironomid larvae, ceratopogonid larvae, Chaoborus larvae, and oligochaetes. Benthic sampling revealed a pattern of increasing diversity from deep waters to shallow waters, with chironomids being the most diverse group. Dredge sampling showed benthic populations at 508 (Discharge station) to have reduced den-sity, biomass, and diversity, when compared to other stations; how-ever, littoral samples in the discharge showed no such pattern.

Unsuitable substrate and scouring, rather,than temperature appear to be the limiting factors. A specimen of the Asiatic clam, Corbicula, was collected from Lake Keowee this year. Corbicula will probably become an important component of the benthos in future years.

1.3-2 ONS 12/77

. 8. Fish impingement (Section 1.4) in 1977 was similar to that observed in previous years. Rates of impingen(at were high-est in Winter and early Spring, and were dominated by thread-fin shad. Bluegill and yellow perch dominated the much lower

. impingement observed during the remainder of the year.

Almost 2000 m3 of ONS condenser cooling water was filtered in l 1 1977 to detect entrainment of fish eggs and larvae. No eggs i or larvae were collected. Supplemental sampling in the intake l

)

1 canal confirmed that few, if any, fish eggs or larvae are drawn l' into the intake canal from the lake, and that there is no appreci-4 able fish reproduction in the canal itself. These results are ,

similar to those reported previously.

9. Studies of Phyloplankton and Zooplankton Entrainment (Section 1.5) confirmed previous conclusions that passage through ONS has an effect on these communities which is of little ecological signifi-cance. As a result Oconee's use of bottom waters for CCW, relatively I few organisms are entrained, and the AT's and discharge temperatures to which the organisms are exposed, are moderate.

10. Monitoring by SERI fisheries biologists detected no gas-bubble disease in any Lake Keovee fishes (Section 1.7). No symptoms of this disease have yet been detected since ONS began operating. Nitrogen super-saturation (4105%) has been observed quite often.

11. Fish population dynamics and reproduction studies are continuing to be carried out by the Southeast Reservoirs Investigations group, Fish and Wildlife Service, U. S. Department of the Interior. See Subsection 1.3.2 and Appendices C and D for information on these studies.

REFERENCES CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47, and DPR-55, Technical Specificacitna for the Oconee Nuclear Station Units 1,.2, and 3, Duke Power CompanJ. U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, D. C.

. 1977. Oconee Nuclear Station. Environmental Summary Report 1971 - 1976.

1.3-3 ONS 12/77

v TABLL 5.)-1

$UtetARY OF CL;tRENT ENVIRONMENTAL IGJitTIOR11tG PROGRAMS ON LAEE EEDisTE AND LAKE NAATIEll. DTCENSEE. 1977 8AMPLINC LOCATION $

LAEE EEOW5E LAEE BARTWELL Pre- Post- Istake Discharge SA MLING .

60I 602 603 604 605 606 500 501 501.5 502 50) 504 505 506 507 508 508.5 509 509.5 549 Cond. Cond. Structure st ruc t ure Pe =

WATER Qt1ALITY M M M M M M Temperature MM M N M M M M M M M M M M M JI N N Dissolved Oxygen MM N M M M M N M M N M M M M M M M N M M M M M Conductivity N N M M M N N M M M M M M MM M M N N M M

ORP~

MM N N M M M M N M M M M M M M pu N MM N N M M M_ M M M M Surface Li$h t N N N M N N

. Euphotic Depth MM M M M M M M M N N N N M M Alkalinity N. M M N N M N. M M M M M M M- M N N N Terbidity N N N M M M N M N N M M M M .M M M M N N Q Q Q Q Q Cbleride M' N N M M M M M kW M M M MM M N N N M M M M M M M N N Q Q Q Q Q N02 -NO3 Nitrogen IGij Nitrogen MM M N M N M M M N N M Q Q Q.Q Q MM N N N N M M M M M N Q Q Q Q Q Ortho P Q Q Q Q Tots! P MN N M M M M N N M N M Q MM N. M M N N N N N N N Q Q Q Q Q 5111com M M M M M Iron MM N N N N M M M .M M M M M M N M .A Manganese MM M M N N M M N N M M M M M M Calcium MN N N N N N M M M M M M M M N N N M M M M M M M M Magnesium N N N Aluminum Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Cadetan Q Q Chromium Q Q Q Q Q Q Q Q Q F Copper Q Q Q Q Q Q Q Q Q

• Lead Q Q Q Q Q Q Q Q Q M M M N

'b Potasetum .MN N. M M M M M M M M M M M M N Sodium MN N M N N N N N N M M 21u 4 Q- Q Q Q Q Q Q Q Mercury Q Q Q q Q Q Q Q Q PLUME STUDIES - +

Continuous Temp. C C C Q Q Q Q Q , Q MsPP l a8 (2).

PLAIE7011 Entratament- BN Zooplaaktda BM BN DIE get est Phytoplanktoe Surveillance Zooplanktaa 30s het BN BM BM 3 81 B00 BN Sgt 3 86 Phytoplankton SIE Est get BM BM BIG pet Ret Set PERIPNY10N - M N N M M M BENTIIDS Q Q Q Q Q Q Q Q DIS $0LVED CASES . W W W W W- W W W PlsNg$ III e

. 3 (1) See Section 1.3.1 (2) Approntmately 25 addittomat stations will be sampled.

(3) See southeast Reservoir lavestigatione Reporte (Appendices C & D)

LEY: M-htbly (Mieluun of 10 times per year with a period not to exceed 45 days between samples); Chtinuouslyg Q-Quartertyg DM-Bi-Monthly (6 times per year)s W-Winter period monthly (Nov.-April).

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• gll m DAM FIGURE I.3-2 MONTORING STATIONS 1.3-6 ONS 12/7' o2 4 6 a l SCALE IN KILOhETERS

1.3.1 Water Quality Specification: A. Synoptic water quality surveys at nine (9) sampling stations on Lahe Keowee, four (4) stations on Lake Hartwell and a station on the Keowee River between the lakes shall be conducted. Sampling locations are shown on Figure 1.3-1 and Figure 1.3-2, and required sampling parameters are listed in Table 1.0-1.

Temperature and dissolved oxygen measurements shall be made at 0.3, 1.5, 5.0, 6.5, 8.0, 10.0 meters and thereafter every 2.5 meters to one meter off the bottom for lake ,

samples. BOD measurements on Lake Keowee shall be taken at 0.3 meters, 3.0 meters, and bottom depths. BOD measure-ments on Lake Hartwell shall be made on samples which are a composite of water from 0.3 meters, mid depth and bottom depths. All other specified parameters shall be measured at a minimum of three depths for each lake sampling station. 1 At sampling station 605 (Figure 1.3-2), the Keowee River shall be sampled from 0.3 meters. (buke Power Company 1973a)

I. INTRODUCTION A discussion of the importance of a synoptic water quality program has been presented previously by Duke Power Company (1973b). A summary of l preoperational and operational monitoring and the impact from ONS has l been presented by Duke Power Company (1977).

II. METHODS AND MATERIALS

. Frequency and Locations for Sampling Profile measurements of temperature, dissolved oxygen, pH, oxidation-reduction potential, and specific conductance were conducted at monthly intervals at twelve (12) sampling locations on Lake Keowee and five (5) locations on Lake Hartwell from January 1977 through December 1977.

These irt situ measurements were made at depths of 0.3 m,1.5 m, 3.0 m, 5.0 m, 6.5 m, 8.0 m, 10.0 m, and at 2.5 m intervals to 1 m above the bottom.

Samples to _ be analyzed in the laboratory were collected at 5 m intervals from 0.3 m to 1 m from bottom. Examination of past data indicated that more samples than necessary were being withdrawn in order to characterize the water column. On June 1, 1977, the depth interval was increased from five (5) to ten (10) meters. However, duplicates of all samples were withdrawn. This change increased the data-handling capability for the water chemistry program. Due to the shallow depth (s10 m) at Locations 508.0, 603.0, and 604.0, samples were taken from only two depths for each location.

On March 1,1977, sampling was discontinued at Locations 500.5 and 508.5.

Past data indicated these locations were adequately characterized by the remaining locations. Light meter readings were not obtained during 9

1.3.1-1 ONS 12/77-

August and December at Location 505.0 nor during August, November, and December at Locations 506.0 and 507.0 due to late evening sampling.  ;

Sampling locations, frequency, and chemical constituents monitored are presented in Table.l.3-1. Data for Lakes Keovee and Hartwell appear in Appendix A, Sections I-IV.

Laboratory Procedures Analytical methods, preservation techniques, references, detection limits and reporting units for each chemical constituent measured on Lakes Keowee and Hartwell are presented in Table 1.3.1-1. All analytical methods either conform to 40 CFR 136 (USEPA 1976a) and/or are considered best available technique by the scientific community. The detection limits employed were at the " state-of-art" level for the type of analysea being performed.

In May 1977, the method used to measure ammonia nitrogen was changed from the Salicylate /nitroprusside method to the Berthelot meth6d. The technical problem that occurred in March 1976 while using the Berthelot reaction method was corrected (Duke Power Company 1976). The Berthelot mettod provided improved sensitivity and detection limits. Based on variability observed in past studies, all minerals and heavy metals, except iron and manganese, were analyzed as location composites. The frequency of sampling for major mineral elements (sodium and potassium) previously classed as heavy metals was increased to monthly. Beginning in June 1977, the locations for quarterly heavy metals sampling were reduced to the following: 501.0, 504.0, 506.0, 508.0, 549.0, 601.0, 602.0, 603.0, and 605.0. Evaluation of past data indicated that the heavy metals composition of the areas studied "on Lakes Keowee and Hartwell are adequately characterized by these locations. Manganese concentrations were not determined during June 1977.

The precision and accuracy of the data were affirmed in accordance with the procedures recommended by the USEPA (1972).

Data Analysis i

Sampling locations were grouped into three areas; Little River arm (500.0, '

501.0, 502.0), near field (508.0, 504.0, 505.0)- and far field (506.0, 507.0,.549.0). Means were calculated for the area subgroups and used to graphically illustrate temporal and spatial variation between areas during.this study period.

The. monthly' data were used to calculate volume-weighted averages and total' lake content (metric tons).for Lake Keowee for selected constitu ~

~

ents. -All sampling depths at' Locations 500.0, 501.0, 502.0, 503.0,-

504.0, 505.0,.506.0, and 507.0 were used to calculate a mean lake con-centration for each depth sampled. The mean' concentration for each:

'1'3 1-2

.. ONS 12/77 ,

6

constituent at each depth was multiplied by the lake volume for that stratum. The constituent contents for the various strata were summed to obtain total content for Lake Keowee during each month. This was then divided by total lake volume to yield a volume-weighted average of each constituent in Lake Keewee for each sampling date. A summary i

of the volume-veighted averages are presented in Table 1.3.1-2.

Data were subjected to selected statistical procedures as outlined in Barr et al. (1976) . Water chemistry data were subjected to Pearson's correlation analysis with the hydrological data.

III. RESULTS AND DISCUSSION -

Lake Keovee ,

i Temperature Isotherms for Lake Keosee during 1977 are presented in Figures 1.3.1-1 )

through 1.3.1-4. The coldest temperatures existed during February with l a volume-weighted average of 7.9 C (Table 1.3.1-2). The lowest surface temperature (5.4 C) was observed at Location 500.0. As surface water temperatures increased during the spring months, the lake gradually stratified. By July, Location 501.0 exhibited a vertical thermal ,

gradient of 21.2 C'. During July, temperatures ranged from 9.9 C to l 31.7 C (year maximum) with a monthly mean of 21.8 C (Table 1.3.1-3).

4 The highest volume-weighted average lake temperature (25.0 C) existed during September (Table 1.3.1-2). As air temperatures decreased in the fall, the lake cooled rapidly and was nearly isothermal by December (Figures 1.3.1-1, 1.3.1-2, and 1.3.1-4).

Surface temperatures at Locations 501.0, 506.0 and 508.0 are cospared

in Figure 1.3.1-5. Location 501.0 typifies the Little River arm and Location 506.0 typifies the Keowee River arm. Location 508.0 is in the discharge cove. Location 501.0 generally was cooler than Locations 506.0 and 508.0, except during the summer. The annual maximum temperatures observed at Locations 501.0 (31.0 C), 506.0 (30.2 C), and 508.0 (30.7 C) occurred at the surface during July. Location 508.0 had the highest surface temperatures during the winter (Figure 1.3.1-5). The greatest difference in surface temperatures between the two arms (Locations 501.0 and 506.0) was 4.5 C', measured during February'.

As documented in the ONS Summary Report (Duke Power Company 1977), mixing by ONS operations resulted in bottom water temperatures exhibiting greater yearly increases than during preoperational years. The effects observed during 1977 were of approximately the same magnitude as observed during other operational years.

Dissolved Oxygen The highest volume-weighted average DO concentration (11.1 mg/l) in Lake Keowee occurred during February, and decreased to a minimum 1.3.1-3 ONS 12/77

value of 5.8 mg/L in September (Table 1.3.1-2). The temporal pattern for DO for 1977 was, consistent to that previously reported (Duke Power 1 Company 1977). Maximum DO concentrations occurred from January through April. As stratification commenced, DO concentrations decreased in the lower strata until minimum values were observed during August, September, and October (Figures 1.3.1-6 through 1.3.1-9).

The minimum DO content in each year from 1973 through 1977 was progres-sively higher than the preceeding year (Figure 1.3.1-10). The occur-rence of the minimum D0 content changed from September, 1971-1975 to August, 1976 and 1977. Figure 1.3.1-10 indicates that the DO content curve was flatter during August through October 1977 than during pre-vious years. The flatter curve and higher DO content for 1977 was attributed to the unusually cold weather that occurred during the win-ter of 1976-1977.

pH Lake Keowee remained mildly acidic with a volume-weighted lake average pH ranging from 6.0 to 6.5 for 1977 (Table 1.3.1-2). During August, pH values ranged from 6.1 to 8.3 with a mean of 6.5 (Table 1.3.1-3). The

, higher values (28.0) were observed in the Little River arm (Locations 500.0, 501.0 and 501.5) in the upper strata (0.3 through 3.0 m) . Values above 7.0 were attributed primarily to phytoplankton productivity (Section 1.3.4).

Specific Conductance Very little spatial or temporal change occurred in specific conductance values in Lake Keowee. The annual mean specific conductance was 18.6 pmhos/cm with a minimum value of 12 pmhos/cm observed during April and December. The highest single value (92 umhos/cm) and highest monthly lake mean (22 umhos/cm) were observed during October (Table 1.3.1-3).

The higher specific conductance values during October coincided with increased ionic constituent concentrations (e.g. iron and manganese) in the lake (Table 1.3.1-3) . The mean specific conductance of the lake returned to 18 umhos/cm in November.

Turbidity Turbidity values throughout the lake were generally below 10 JTU and were similar to previous observations (Duke Power Company 1977).

Turbidity values ranged from 2 to 100 JIU with an annual mean of 6.2 '

l l

JTU. The highest monthly mean (10 JTU) occurred during April and July (Table 1.3.1-3) . The higher turbidity values during April and July were attributed primarily to a period of increased rainfall preceding sampling. Abnormally high turbidities (100 JTU at Location 500.0 during April) were attributed to sample contamination by bottom i sediment disturbed during the sampline process.

I I

1.3.1-4 ONS 12/77 l

j

Oxidation-Reduction Potenti 4 0xidation-reductiv2 potential (w.tP) varied with respect to the equilib-rium between the ionic constituents in the lake. In natural waters the state of equilibrium f' .astantly shifting and the ORP may be controlled by the most rapid of u..e several possible reactions (Hem 1971). Conse-quently, a steady state is assumed for the given instant during which measurement is made.

The maximum ORP (450 mv at Location 504.0) and the minimum ORP (-190 mv at Location 506.0) occurred during October (Appendix A,Section I). The .

negative ORP indicated the shift of equilibrium toward reduced conditions due to anoxia. This anoxic condition was a result of the inability of the bottom strata to mix with the upper strata due to thermal gradients which naturally occur as the lake warms during spring and summer. These reduced conditions also enhance formation of annonia nitrogen, release of sedi-ment phosphorus, and solubilization of iron and manganese. In lower strata, the toxic form of sulfide (H 2 S) may also be formed under these reducing conditions.

Biochemical Oxygen Demand Biochemical oxygen demand (BOD i g) measurements ranged from 0.1 to 4.2 mg/4 with an annual mean of 1.5 mg/4. Monthly means indicated that maximum biochemical oxygen demand occurred during April (2.9 mg/4). The maximum value (4.2 mg/4) occurred at the bottom depth of Location 507.0 during April. The lowest monthly mean (0.8 mg/4) occurred during February and November. Based on frequency distribution, 33% of the BOD ig values were less than 1.2 mg/4 and 47% fell below 1.8 mg/4. Even though Lake Keowee BOD i g values were slightly higher than previously, the 1977 study period (X = 1.5 mg/4) compared favorably with the January 1971 through December 1976 period (X = 1.1 mg/4). Data from the 1977 study period reaffirmed the conclusion of the Summary Report (Duke Power Company 1977) that BODi g values were low enough to be of little value in characterizing Lakes Keowee and Hartwell water chemistry.

Minerals The annual mean hardness (6 mg/4-CACO3 ) and e w tar percentages of the major mineral constituents were equal to or ./ the same as the 1976 observations (Duke Power Company 1976). Mol- r,tcentages indicated bicarbonate (32%) was the major constituent tuliowed by silica (24%),

sodium (13%), chloride (9%), calcium (8%), magnesium (5%), potassium (4%),

aluminum (3%), iron (1%) and manganeae (1%). Furthermore, these mineral data were similar to that observed during the 1973 through 1976 operational period (Figure 1.3.1-11).

The average annual silica concentration (3.1 mg//-Si). indicated that silica, a major component of Lake Keovee mirarals, continued to decrease

.l.3.1-5 ONS 12/77

slightly (Duke Power Company 1977). Except during August, silica showed very little spatial change during the study period. During August, silica ranged from 0.64 mg/4-Si (yearly minimum) to 7.3 mg/4-Si (yearly maximum) with a monthly mean of 1.8 mg/4-Si (Table 1.3.1-3). The maxi-mum concentrations occurred at Locations 500.0 and 505.0 (Appendix A-Section III). The wide variation was attributed to heavy rainfall (7.8 inches) and runoff prior to the sample date.

Iron (i = 0.37 mg/L) and manganese (i = 0.16 mg/4) exhibited similar seasonal trends both spatially and temporally (Figures 1.3.1-12 and 1.3.1-13). The monthly variation in iron and manganese concentrations -

during the 1977 study period and the operational period 1973 through 1976 were similar (Figures 1.3.1-14 and 1.3.1-15). Maximum concentrations continued to be observed during late summer and fall with the Little River locations exhibiting the maximum concentrations at this time. The near-field and far-field locations continued to show a decline in iron concen-trations during the fall. This concentration decrease was attributed to increased mixing and higher DO concentrations caused by ONS and Jocassee Pumped Storage operations (Duke Power Company 1977).

Aquatic Nutrients Minimal temporal and spatial variations in orthophosphate concentrations were observed due to extremely low concentration levels. Soluble ortho-phosphate ranged from 0.005 to 0.026 mg/4-P with an annual mean of 0.006 mg/f-P. The monthly means of the different lake areas revealed that from July through November the Little River area exhibited slightly lower orthophosphate concentrations than the near-field and far-field areas (Figure 1.3.1-16). This was attributed to higher biological productivity in the Little River area during this period (Section 1.3.4).

Total phosphorus concentrations en Lake Keowee enntinued to decrease during 1977 (Figure 1.3.1-17) . This steady decrease has also been observed in other newly impounded reservoirs (Weiss 1975). The high-est total phosphorus concentrations occurred in August.. No explana-tion is offered for this maximum as it did not follow the trend of anoxic conditions in the bottom waters and it did not seem to be associated with a number of other possible causative factors. Total phosphorus ranged from 0.005 to 0.53 mg/1-P with an annual mean of ,

0.010 mg/1-P (Table 1.3.1-3). Temporal and spatial variations in total phosphorus concentrations are shown in Figures 1.3.1-18 and 1.3.1-19.

l l

Temporal variation of nitrate-nitrite concentrations was directlyThe i associated with seasonal DO concentrations (Figure 1.3.1-20). '

Little River area generally exhibited slightly higher nitrate-nitrite concentrations than the near-field and far-field areas (Figure 1.3.1-21).

This was attributed to nutrient enrichment as noted in previous reports l (Duke Power Company 1976, 1977). The far-field area continued to exhibit the lowest nitrate-nitrite concentrations due to dilution with water from l

( l.3.1-6 ONS 12/77 l

i Lake Jocassee containing lower nutrient concentrations. Nitrate-nitrite l concentrations ranged from 0.010 to 0.46 mg/f-N with an annual mean of I 0.11 mg/4-N. The maximum mean monthly nitrate-nitrite concentration (0.17 mg/4-N) occurred during the period of highest DO (February) . The minimum mean monthly concentration (0.062 mg/4-N) occurred during September and cas associated with the period of lowest DO concentration (i = 5.1 mg/4) and increased reducing conditions that naturally occur at this time.

During March and April 1977, an increase in ammonia concentrations was recorded (Tigure 1.3.1-22). An increase during these months had not been recorded in previous years. The 1977 increase in ammonia concentrations corresponded to increased rainfall that began two weeks prior to the March -J sampling date (3.0 in) and continued until one week preceding the April  ;

sampling date (an additional 11.0 in). Further, the highest monthly 1 mean turbidity occurred during April. Both of these conditions were indicative of runoff inputs. Ammonia concentrations diminished in May and June as the excess ammonia was removed by hydrological 6nd biological actions. The November peak followed the period of maximum I anoxia and the December values indicated that the fall overturn was com- l pleted. Ammonia concentrations ranged from 0.013 to 1.2 mg/4-N with an 1 annual mean of 0.16 mg/4-N. I As noted in the ONS Summary Report (Duke Power Company 1977), operation of ONS continued to stabilize the spatial variations of ammonia (Figure 1.3.1-19). As a result of nutrient enrichment (Duke Power Company 1977),

the Little River area exhibited slightly higher ammonia concentrations than the near-field and far-field areas (Figure 1.3.1-23). Ammonia con-centrations were directly correlated with chloride (r=0.51, p<0.05) indicating a relationship to wastewater inputs.

In order to evaluate nutrient loading and to more clearly define the temporal and spatial variations in selected nutrient concentrations, volume-weighted averages for nitrate-nitrite, ammonia, orthophosphate and total phosphorus were determined and are presented in Table 1.3.1-2.

Orthophosphate comprised from 12% of the total phosphorus concentration during August to 100% during March and December with a monthly average of 68%. Percentages below 20% were due to an increase in particulate phosphorus as a result of increased rainfall. This was substantiated by a significant correlation between percent orthophosphate and total rainfall for the two week period preceding the sampling (r=0.56, p<.001) .

Nitrate to ammonia ratios (0.36 to 1.18) indicated that ammonia was the dominant form of inorganic nitrogen during the study period (Figure 1.3.1-22). Inorganic N/P ratios calculated from the monitoring data were in agreement with previous findings that Lake Keowee was a phosphorus-limited system (USEPA 1975 and Duke Power Company 1977). l Inorganic nitrogen content for Lake Keowee ranged from 196 to 461 metric tons with a monthly mean of 330 metric tons (Table 1.3.1-2). Orthophos-phate ranged from 4.7 to 9.1 metric tons with a mean of 6.3 metric tons.

- 1.3.1-7 'ONS 12/77 L

Total phosphorus content ranged from 5.6 to 70 metric cons and averaged 14 metric tons. Total inorganic nitrogen to orthophosphate ratios (N/P) l l

were calculated using these contents and ranged from 36 to 76 with a mean l of 51. Values above the mean were recorded in the spring and fall which have previously been noted as seasons when nitrogen inputs typically occur.

The absence of temporal uniformity in the N/P values indicated that factors other than biological activity were responsible for nutrient fluctuations.

Correlation analyses of the content data indicated these factors were rain-fall and dissolved oxygen.

A correlation coefficient of 0.83 (p<0.001) was I obtained between rainfall and total phosphorus content indicating runoff to be the major controlling factor of total phosphorus. Additional total ,

phosphorus.was input by sediment release during anoxia as evidenced by a correlation of -0.51 (p<0.1) with D0. A correlation of 0.50 (p<0.1) was obtained between total inorganic nitrogen and rainfall, however, the correlation between inorganic nitr' ogen and DO was only -0.16 (p>0.1).

These-results indicated that nitrogen and phosphorus fluctuations in Lake Keowee can be explained from meteorological and hydrological data. The operation of Oconee Nuclear Station affected these nutrient concentrations by altering the hydrological processes (mixing) which controlled their fluctuations.

Heavy Metals Although no requirements exist for analysis of heavy metals, copper, cadmium, lead, mercury and zine were monitored during this study period.

The objective was to determine if concentrations of these metals were detrimental to aquatic life or to consumers of Lake Keowee water. This was ascertained by comparing the measured concentrations to criteria developed by the USEPA (1976b).

Copper concentrations continued to be well below the recommended USEPA limit for domestic water supply (1 mg/4). The highest copper concen-trations occurred during the winter with a minimum value of 0.003 mg/L occurring in the far-field area and a maximum of 0.014 mg/L in the near-field area (Appendix A,Section IV). These values were well below the values reported as harmful to bluegill (USEPA 1976b).

Cadmium concentrations were generally below the 0.4 pg/L limit set by the USEPA (1976b) for a soft water system. During the winter and spring I

l of 1977, the near-field and the far-field areas exhibited concentrations l

higher than 0.4 pg/L with area means ranging from 0.5 to 4.3 ug/l (Appendix l A.Section IV). The higher values were observed in the near-field area during the winter.

. Lead concentrations ranged from 0.8 to 5.7 pg/L with a mean of 2.1 pg/L (Appendix A,Section III). Concentrations below 6.0 to 11.9 pg/L have not shown any adverse effects on salmonids, the most sensitive soft water species (USEPA 1976b).

1.3.1-8 ONS 12/77 m

Mercury concentrations in Lake Keowee during 1977 were consistent with findings from 1974 through-1976 and were below the detection limit of 0.1 pg/L (Appendix A,Section III).

1 Recorded zine values never exceeded 0.18 mg/4 (Appendix A,Section IV).

A mean of 0.031 mg/4 indicated that zinc concentrations were sufficiently below a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> TL50 for bluegill (2.58 mg/4) for waters with similar pH, hardness and alkalinity as Lake Keowee (USEPA 1976b). Zinc values were

! observed to be highest during the winter and lowest during fall seasons.

Little spatial variation in zinc concentrations was observed during this study period.

During the 1977 study period, only cadmium displayed occasional concen-trations that exceeded the limit set by the USEPA (1976b). Further, the operation of ONS did not appear to have any effect on heavy metal concen-trations in Lake Keovee.

Lake Hartwell

! Temperature The operation of ONS had minimal thermal impact on Lake Hartwell waters.

Temperature and dissolved oxygen isopleths are presented in Figures 1.3.1-24 through 1.3.1-26. The coldest temperature (4.4 C) recorded on Lake Hartwell occurred during February at Location 601.0 and the highest surface temperature (31.0 C) occurred at Location 602.0 during July (Appendix A,Section I). From May through September, surface temperatures at Location 605.0 were lower than at Locations 603.0 and 601.0 (Figure 1.3.1-27).

Dissolved Oxygen The operation of ONS had minimal effect on Lake Hartwell dissolved oxygen concentrations. Monthly variations in surface (0.3 m) DO concentrations on Lake Hartwell are presented in Figure 1.3.1-28. The lowest and highest monthly mean DO concentrations occurred during September and February, respectively (Table 1.3.1-4). Location 605.0 (Keowee tailrace) exhibited i maximum and minimum DO concentrations in March and August, respectively.-

Biochemical Oxygen Demand Lake Hartwell BOD i g values were slightly higher than those observed on Lake Keowee ranging from 0.3 to 4.3.mg/4 with an annual mean of 1.9.mg/4.

The temporal trend closely resembled that observed on Lake Keowee with the highest monthly mean (2.6 mg/4) occurring during April and the lowest (0.9 mg/4) during December. -Based on frequency distribution, 63% of the

' BOD values were less than 2.0 mg/4 and 82% fell below 2.5 mg/4. The higher values were attributed to higher nutrient loading a result of more point sources on Lake Hartwell than on Lake Keowee.

Minerals The annual mean hardness (8 mg/4-CACO 3 ) and the molar percentages of the major mineral ~ constituents were the same as or closely resembled the 1976 1.3.1-9 'ONS 12/77

~ _

observations (Duke Power Company 1976). The annual molar percentages indicated bicarbonate (32%) was the major component followed by silica (21%), sodium (15%), chloride (11%), cricium (8%), magnesium (4%),

potassium (4%), aluminum (2%), iron (2%) and manganese (1%) .

The annual mean silica concentration was 3.4 mg/4-Si. Except durir.g August, monthly means showed very little deviation from the mean during the study period. The low monthly mean of 2.7 mg/f-Si during August was attributed to heavy rainfall prior to the sampling date.

Aquatic Nutrients

~

Phosphorus concentrations during 1977 were similar to concentrations reported during 1976 (Duke Power Company 1976). Soluble orthophosphate ranged from 0.005 to 0.048 mg/4-P with an annual mean of 0.008 mg/4-P (Table 1.3.1-4). Total phosphorus ranged from 0.005 to 0.078 mg/4-P with an annual mean of 0.017 mg/4-P. The highest phosphorus concentrations were observed during August when monthly means for soluble orthophosphate and total phosphorus were 0.022 and 0.044 mg/4-P, respectively. The elevated phosphorus concentrations during August were attributed to increased rainfall prior to sampling.

Temporal variation of nitrate-nitrite was directly associated with seasonal DO content. Nitrate-nitrite concentrations ranged from 0.021 to 0.44 mg/4-N with an annual mean of 0.15 mg/4-N. Ammonia concentrations ranged from 0.027 to 7.1 mg/f-N with an annual mean of 0.37 mg/4-N. Increased ammonia concentrations in the hypolimnion at Locations 601.0 and 602.0 were observed during periods of anoxia. Nitrate-nitrite to ammonia ratios indicated that ammonia was the dominant form of inorganic nitrogen from July through November (0.02 to 0.47) and that nitrate-nitrite was the dominant form of inorganic nitrogen from January through May and during December (2.5 to 2.7). Total inorganic nitrogen to phosphorus ratios ranged from 18 during August to 236 during September.

Comparison of Lake Keowee and Hartwell Stratification and turnover occurred at approximately the same time on Lakes Keowee and Hartwell. The water chemistry of both lakes was similar with temporal and spatial distribution of both nutrients and minerals following classical patterns (Hutchinson 1957) . As a result of more point sources on Lake Hartwell than on Lake Keowee, Lake Hartwell had slightly higher concentrations of nutrients. The effects of ONS operation on Lake Keowee were due to transport of hypolimnetic water from the Little River arm to the epilimnion of the Keowee River arm, and included effects on the thermal regime, dilution and mixing due to station operation as previously discussed (Duke Power Company 1976, 1977). The effect'of ONS on the water chemistry of Lake Hartwell was minimal and was restricted to Location'605.0.

IV.

SUMMARY

AND CONCLUSIONS Water chemistry of Lake Keowee and Lake Hartwell was monitored at monthly intervals from January through December 1977. The highest DO content 1.3.1-10. ONS 12/77

l occurred during February and the lowest during September. Anoxic conditions existed in the hypolimnion during late summer and fall.

Meteorology and hydrology were primary factors influencing the water chem. try of Lake Keowee during 1977. After periods of high rainfall, chemical variation due to runoff was evident. The biochemical oxygen l demand (B0D i g) values obtained from Lake Keowee and Lake Hartwell were low and showed no significant change. The mineral composition of Lakes Keovee and Hartwell was similar to the composition previously reported. A continued decrease in lake-wide total phosphorus concen-tration was observed. Spatial and temporal variation of all nutrients were similar to that previously reported. An exception was the effect

• of high rainfall and the resulting runoff on ammonia, silica, and turbidity. In March an unusual increase in ammonia concentrations was noted. Consequently, ammonia was the dominant form of inorganic nitrogen during the study period. Inorganic N/P ratios indicated Lake Keowee to be a phosphorus-limited system. Of the heavy metals measured, only cadmium showed occasioral concentrations above the recommended USEPA limit.

The effects of ONS operacions on the water chemistry of Lake Keowee was similar to that previously reported and included a shif t in the date of the chemical overturn, stabilization of nutrient variations and increased mixing of the lake. These impacts are primarily the result of the pumping component of ONS operation. The effect of ONS on the water chemistry of Lake Hartwell was minimal and was restricted to Location 605.0. Although the water chemistry of Lakes Keowee and Hartwell was influenced by ONS operation, no major impact was noted.

1.3.1-11 ONS 12/77

LITERATURE CITED

'American Public Health Association (APRA), American Water Works Association (AWWA),

Water Pollution Control Federation (WPCF). 1975. Standard methods for the examination of war.er and wastewater. 14th ed., Amer. Pub. Health Assn.,

NY. 1193 pp.

Barr, A. J., J. H. Goodnight, J. P. Sall, and J. T. Helwig. 1976. A user's guide to SAS 76. Sparks Press. Raleigh, NC. 329 pp.

Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic -

Energy Commission (revised August 1, 1975, NRC), Washington, DC.

l 1973b. Oconee Nuclear Station. Semi-Annual Report. Period Ending December 31, 1973. Charlotte, NC.

1976. Oconee Nuclear Station. Annual Report. Period Ending December 31, 1976. Charlotte, NC.

1977. Oconee Nuclear Station. Environmental Summary Report. Period 1971-1976. Charlotte, NC.

Hem, J. D. 1970. Study and interpretation of the chemical characteristics of natural water. Geological Survey Water-Supply Paper 1473. U. S. Government Printing Office, Washington, DC. 363 pp.

Hutchinson, G. E. 1957. A treatise on limnology. Vol. I. John Wiley and Sons, Inc., NY. 1015 pp.

Hydrolab Corporation. 1973. Instructions for operating the Hydrolab Surveyor Model 6D iyt situ water quality analyzer. Austin, TX. 146 pp.

Monitor Technology, Inc. 1973. Monitek-laboratory turbidimeter - Model 150 -

operating and maintenance instructions. Redwood City, CA. 13 pp.

Montedoro-Whitney Corporation. 1974. Operating instructions and paintenance manual for solar illuminance meters. Models LMA-8A, LMD-8A, LMT-8A.

San Luis Obispo, CA. 5 pp.

Perkin-Elmer Corporation. 1976. Analytical methods for atomic absorption spectrophotometry. L rwalk, CT. n.p.

. 1977. Analytical methods for atomic absorption spectrophotometry using the HCA graphite furnace. Norwalk, CT. n.p.

Technicon Industrial Systems. 1972. Operation manual for the Technicon Auto-n.p analyzer II System. Technical Publication No. IAl-0170-20. Tarrytown, NY.

. 1973. Operation manual for the Technicon Autoanalyzer II System.

Technical Publication- No. TAl-0170-20. .Tarrytown, NY. n.p.

_ l.3.1-12 ONS 12/77

. 1974. Operation manual for the Technicon Autoanalyzer II System.

Technical Publication No. Tal-0170-20. Tarrytown, NY. n.p.

United States Environmental Protection Agency. 1972. Handbook for analytical quality control in water and wastewater laboratories. Technology Transfer, Cincinnati, OH. n.p.

. 1974. Methods for chemical analysis of water and wastes. Technology Transfer, Washington, DC. 298 pp.

. 1975. Repo,rt on Lake Keowee, Oconee Working Paper No. 433. National Enviromnental Research Center, Corvallis, OR. .

. 1976a. Title 40, Protection of environment. . Chapter 1, Subchapter D, Part 136. U. S. Federal Register, 41(232): 52780-52786.

. 1976b. Water quality criteria 1976. USEPA, Washington, DC. 501 pp.

Weiss, C. M. 1975. An assessment of the environmental stabilization of Belews Lake - Year IV and comparisons with Lake Hyco, North Carolina -

July 1973 - June 1974. University of North Carolina--Chapel Hill. 500 pp.

I 1.3.1-13 ONS 12/77

1.3.1 WATER QUALITY Specification: A. (Continued)

Dissolved oxygen will also be measured weekly from May through November at three locations: (1) the Oconee discharge, (2) the lake surface (0.3 meter depth) at the Keowee intake structure, and (3) the Keowee tailrace during hydroelectric plant operation (Duke Power Company, 1973a).

1. INTRODUCTION The utilization of hypolimnetic withdrawal of water from Lake Keowee for the ONS condenser cooling water has been discussed previously (Duke Power Company 1974a, 1977). During lake stratification (May through November) ,

the withdrawal of cool bottom water low in dissolved oxygen (DO) and its subsequent discharge to the surface of Lake Keowee is the basis for the above specification.

II. METHODS AND MATERIALS Dissolved oxygen concentrations and water temperatures were measured weekly (duplicate samples) in Lake Keowee and the Keowee Hydro tailrace from the following structures: ONS intake. and discharge, Keowee Hydro Station intake and discharge, and S.C. Highway 183 bridge (Location 605).

The modified "Winkler" method described previously (Duke Power Company,1973b) was employed for DO analysis.

III. RESULTS AND DISCUSSION 1he results of the weekly D0 monitoring program are presented in Table 1.3.1 - 5 Figure 1.3.1 -29 illustrates the DO concentrations for the five i monitoring stations for the 1977 reporting period. Dissolved oxygen con-centrations for the ONS intake ranged from a low of 4.4 mg/l on September 2 and 8 to a high of 9.1 mg/l on May 5 (Table 1.3.1-5) . Dissolved oxygen values for the ONS discharge ranged from a low of 4.6 mg/l on September 8 to a high of 8.7 mg/l on May 5 (Table 1.3.1-5). The lowest value recorded at the Keowee Hydro Station intake was 5.3 mg/1, recorded on September 8 (Table 1. 3.1-5) . Lows of 6.7 mg/l and 6.8 mg/l were recorded at the Keowee Hydro St ation discharge and Location 605 respectively, on September 2.

Continuous DO concentrations less than 5.0 mg/l for the CNS intake extended from August 24 through September 8. From September 2 through September 8, DO concentrations less than 5.0 mg/l were recorded at the ONS discharge.

Dissolved oxygen values for the Keowee Hydro Station intake were never lower than 5.3 mg/1.

The gradual improvement in DO concentrations continued in the intake canal in 1977 as in past years with respect to both minimal DO concen-trations (4.4 mg/l in 1977, 4.2 mg/l in 1976, 3.6 mg/l in 1975, and 3.4 mg/l in 1974, Figure 1.3.1-30) and the period in which DO concentrations were less than 5.0 mg/1'(3 weeks in 1977, 5 weeks in 1976, 5 weeks in 1975, and 9 weeks in 1974) (Duke Power Company 1974b,1975, and 1976) .

1.3.1 - 14 ONS 12/77

The gradual improvement in DO concentrations also continued in the ONS discharge in 1977 as in past years with respect to both minimal DO conditions (4.6 mg/l in 1977, 4.3 mg/l in 1976, 3.8 mg/l in 1975, and 3.4 mg/l in 1974, Figure 1.3.1 -31) and in the period in which DO concentrations were less than 5.0 mg/l (1 week in 1977, 3 weeks in 1976, 5 weeks in 1975, and 6 weeks in 1974) (Duke Power Company 1974b, 1975, and 1976).

e IV.

SUMMARY

AND CONCLUSIONS An Laprovement in DO concentrations of ONS condenser cooling water discharged to the surface of Lake Keowee and subsequently to Lake Hartwell can be attributed to the following: 1) ONS discharge water mixing with lake water in the discharge cove; 2) aeration in the discharge cove; 3) mixing and aeration in the Keowee Hydro tailrace during the operation of the Keowee -

Hydro Station; and 4) the increased DO concentrations of water entering the intake canal.

A gradual increase in DO concentrations in the ONS intake and discharge for the eummer months has been documented annually since 1974. The hypo-limnetic withdrawal of water from Lake Keowee and the subsequent discharge  !

to the lake surface has allowed surface waters to mix to lower depths, thus  ;

allowing water higher in DO concentrations to be drawn into the ONS intake by the operation of the Condenser Cooling Water (CCW) pumps.

l The discharge cf water relatively low in dissolved oxygen is Itaited to the immediate vicinity cf the ONS discharge. The short duration of DO concen-trations less than 5.0 mg/l and the small area of Lake Keowse affected should not adversely affect the aquatic biota of the lake.

REFERENCES Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47, and DPR-55. Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Com-mission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, D.C.

. 1973b. Oconee Nuclear Station. Semi sinual Report.

Period endinE June 30, 1973.

. 1974a. Oconee Nuclear Station. Semi-Annual Report.

Period ending June 30, 1974.

. 1974b. Oconee Nuclear Station. Semi-Annual Report.

Period ending December 31, 1974.

. 1975. Oconee Nuclear Station. Semi-Annual Report.

Period ending December 31, 1975.

. 1976. Oconee Nuclear Station. . Annual Report.

Period ending December 31, 1976.

.- 1977. Oconee Nuclear Station. Environmental Summary Report. 1971-1976.

1.3.1 - 15 ONS 12/77

1.3.1 WATER QUALITY Specification: B. Water temperature recording stations shall be established )

at Stations 502, 503, and 504. Temperature shall be monitored in a multi-point vertical profile, accurate to 0.5'C. Sensors shall be placed at depth of 0.3 meters  ;

below the surface, on the bottom, and at a minimum of six (6) intervals to describe the temperature profile.

A fourth temperature recording station shall be established to monitor the waters discharged from Lake Keowee through the Keowee Hydro Plant (Duke Power Company, 1973a). .

1. INTRODUCTION Discussion of the significance of continuous temperature monitoring has been presented (Duke Power Company 1973b).

II. METHODS AND MATERIALS Locations 502.0, 503.0, 504.0, Keovee Tailrace The methods and materials used in monitoring the water temperature profile f

' at these locations have been described (Duke Power Company 1973c).

Data Reduction The method of dcta reduction used for Locations 502.0, 503.0, 504.0, and Keowee Tailrace have been described (Duke Power Company 1973c).

III. RESULTS AND DISCUSSION A comparison of the water temperature data from 1972 through 1977 (Duke Power Company , 1973b , 1973c , 1974 a , 1974b , 1975 a , 1975b , 1976) reveals that both the maximum and minimum surface temperatures occurred during 1977. The minimum surface temperature (6.9 C) occurred at Location 502.0 on February 14, 1977, and the maximum temperature (33.0 C) occurred at Location 503.0 on July 20, 1977. The previous maximum surface temperature (32.8 C) was recorded at Location 502.0 during July 1972 and the previous minimum surface temperature (7.2 C) was recorded at Location 503.0 during January 1972.

Using the data in Appendix A,Section V, the following temperature trends were observed for Locations 502.0 and 504.0. From April through September 1977,-the mean monthly temperature for Location 502.0 (at the skimmer wall) was warmer for each corresponding depth than Location 504.0 (in the DNS discharge plume). This was due to the CCW discharge temperature of ONS being colder than the surface receiving waters. There was a colder than usual supply of hypolimnetic water that was pulled under the skimmer wall and utilized for the entire summer by the CCW system. This resulted from a very cold winter combined with lower than usual CCW 1

1.3.1-16 ONS 12/77

flow rates and AT's during the summer. CCW flow rates and AT's are presented in Table 1.1-1. In previous years of ONS operation, the hypolimnatic temperatures were increased enough by early August that pcasage through the CCW system raised the discharge water to a temperature higher than the surface receiving water.

1 Frca January through March 1977, and October through December 1977, I Location 504.0 was warmer than 502.0 for each corresponding depth. The '

ONS thermal plume was very evident in the top 3 meters at Location 504.0 )

during January. This column of surface water was 5.0 C' warmer than j at Location 502.0 as shown in Figure 1.3.1-32.

The Keowee Tailrace temperature data are presented in Appendix A,Section V and summarized as shown in Table 1.3.1-6. The monthly means of the changes in temperature between periods of hydro generation and "no-generation" revealed that operation of the Keowee Hydro consistently resulted in raising the tailrace temperature. These changes ranged between 0.1 C' and 2.4 v* and the maximum daily change observed was 5.0 C* for this reporting period.

Comparison of the Keowee Hydro tailrace temperatures with those of Location 504.0 during periods of power generation indicates that the hydro drawe a layer of water from Lake Keowee ac a depth of 5 to 8 m.

IV.

SUMMARY

AND CONCLUSIONS The maximum (33.0 C) and the minimum (6.9 C) surface temperatures recorded for the past six years occurred during this reporting period. The maximum (33.0 C) was recorded during July and is a result of climatic conditions rather than ONS operation as can be seen from the fact that the ONS Condenser Cooling Water discharge temperatures were cooler than the surface receiving water for the summer months. The maximum discharge temperature for the month of July was 28.0 C and averaged 25.8 C for that month.

The Keowee Hydro generation resulted in a 1.1 C* increase in mean tailrace temperature compared to tailrace temperatures when Keowee was not generating.

1.3.1-17 ONS 12/77

REFERENCES CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuc1 car Station Units 1, 2, and 3, Duke Power Company, U. S.

Atomic Energy Commission, Docket nos. 50-269, 50-270, and 50-287 (revised August 1,1975, NRC), Washington, D. C.

. 1973b. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1973.

. 1973c. Oconee Nuclear Station. Semi-Annual Report, ~

Period Ending December 31, 1973.

1974a. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1974.

1974b. Oconee Nuclear Station. Semi-Annual Report, Period Ending December 31, 1974.

1975a. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1975.

1975b. Oconee Nuclear Station. Semi-Annual Report, Period Ending December 31, 1975.

. 1976. Oconee Nuclear Station. Annual Report, Period Ending December 31, 1975.

1.3.1-18 ONS 12/77

Table 1.3.1-1 Analytical N thoda for Chemical and Physical Constituents Measured on Lake Keowes and Lake Hartwell Parameter M6thod Reference Preservative Detection Limit Alkalinity. total Mettod 403 A.P.H.A. et al., 1975 4C 1 mg/1-CACO 3

Aluminum Atomic Absorption Perkin-Elmer Corp., 1976 0.5% HNO 3

0.1 ag/l Atomic Absorption /HCA Perkin-Elmer Corp., 1977 0.5% HNO 3

0.01 93/1 Ammonia Nthod 329-74 W/A Technicon Ind. Systems. 1972 4 C, filtration 0.008 mg/1-N Method 98-70 W Technicon Ind. Systems, 1973 4 C, 111tration 0.005 1 /1-N Biochemical Oxygen. Method 507 A.P.H.A. et al., 1975 4C 0.5 mg/l Demand (BOD)g4 Cadmium Atomic Absorption /HCA Perkin-Elmer Corp., 1977 0.5% HNO 3

0.1 63/1 Calcium Atomic Absorption /DA Perkin-Elmer Corp., 1976 0.5% HNO 0.01 mg/l 3

Method 99-70 W Tecluicon InJ. Systems, 1974 4 C, filtration 0.3 mg/l Chloride Conductance, specific Nthod 205 A.P.H.A. et al., 1975 4C 1 patros/cm temperature compensated nickel electrode Hydrolab Corp., 1973 In Situ 1 pahos/cm Copper Atomic Absorption Perkin-Elmer Corp., 1976 0.5% HNO 0.1 mg/l Atomic Absorption /HCA Perkin-Elmer Corp., 1977 0.5% HNO)3 1.0 kg/l N thod 309 A A.P.H.A. et al., 1975 none 1 ag/1-CACO Hardnessftotal 3

. 13 Incident Light Photometer Mostedoro-Whitney Corp., 1974 In Situ 0.5 m Iron, total Atomic Absorption /DA Perkin-Elmer Corp., 1976 4C 0.01 mg/l g-Method 01045 U.S.E.P.A., 1974 4C L

*;" Lead Atomic Absorption /HCA Perkin-Elmer Corp., 1977 0.5% HNO 1 pg/l 3

E Ngnesium Atomic Absorption /DA Perkin-Elmer Corp., 1976 0.5% HNO 0.01 mg/l 3

Manganese. Atomic Absorption /DA Perkin-Elmer Corp., 1976 0.5% HNO 3

0.01 ag/l N rcury, total Flameless Atomic Absorption /N thod 71900 U.S.E.P.A., 1974 1.0% HNO 0.1 p /1 3

Nitrate-Nitrite N thod 158-71 W Technicon Ind. Systems, 1972 4 C, filtration 0.02 mg/1-N Orthophosphate, solubim N thod 155-71 W Technicon Ind. Systems, 1973 4 C, filtration 0.005 mg/1-P

. Oxidation-Reduction Silver-Silver chloride electrode Hydrolab Corp., 1973 in Situ -1000 av Potential (ORP) .

Oxygen, dissolved N thod 422 B A.P.H.A. et al., 1975 in Situ (pumoed sample) 0.0 mg/l temperature compensated polarottaphic cell Hydrolab Corp., 1973 In Situ 0.0 mg/l pli Method 424 A.P.H.A. et al., 1975 4C 0.1 pH unit temperature compensated glass electrode Hydrolsh Corp., 1973 In Situ 0.1 pH unit Phosphorus, total Method 00665 U.S.E.P.A., 1974 4C 0.005 mg/1-P g Potassium Atomic Absorption /DA Perkin-Elmer Corp., 1976 0.5% HNO 3

0.1 ag/l Silica, soluble N thod 105-71 W Technicon Ind. Systems, 1973 4C 0.02 mg/1-Si g

.} Sodium

. Surface Illumination Atomic Absorption /DA Photometer Perkin-Elmer Corp., 1976 Montadoro-Whitney Corp., 1974 0.5% HNO in Situ 3

0.1 mg/l 0.01 ly/ min Temperature Nthod 212 A.P.H.A. et al., 1975 in Situ -1.0 C

' thermistor thermometer Hydrolab Corp., 1973 J_n Situ -5.0 C Turbidity Monitek Turbidimeter Monitor Tech. Inc., 1973 4C 1 JTU Zine Atomic Absorption /DA Perkin-Elmer Corp., 1976 0.5% HNO ,, 10 pg/1 3

Atomic Absorption /HCA Perkin-Elmer Corp., 1977 0.5:: 12:0 3 1 pg/l e

Table 1.3.1-2 Susenary of volume-weighted averages and content of selected aquatic cheatstry constituente for Lake Keowee 1977.

June July August September October November December January February March April  !}al Temperature 25.0 22.8 17.6 13.8 10.4 7.9 10.4 13.0 16.6 19.9 22.0 23.4 Average (C)13 1.49 1.88 2.23 2.39 2.60 3.18 2.82 2.23 1.77 Content (10 k cal) 1.12 .80 1.15 I

y Dissolved Oxygen 10.1 9.4 8.6 7.4 6.4 5.6 6.0 7.4 8.9 y Average (ag/1) 10.4 11.1 10.9 1100 2200 1100 960 800 710 740 740 930 Content (metric tone) 1100 1100 1200 g

Nitrate-nitrite

.13 .12 .11 .10 .10 .062 .11 .13 .13 Average (ag/1-M) .097 .17 .11 152 129 107 149 76 1';,9 153 163 Content (metric tons) 103 159 119 154

' Ammonia

.093 .14 .19 .16 .24 26 .083 Average (ag/1-N) .087 .10 .19 .26 .18 237 109 149 276 203 292 307 101 Content (metric tons) 93 94 196 307 Ortho-phosphate .005 .006 .005' .006 .007 .005 Average (ag/1-P) .005 .005 .005 .005 .005 .005 6.5 6.0 5.5 9.1 6.2 7.3 8.2 6.1 Content (metric tons) 5.4 4.7 5.0 6.0 g Total phosphorus .005 .008 .007 .006 .009 .048 .009 .008 .014 .005 V- Average (as/1-P) .006 .006 5.6 9.5 8.9 7.0 9.3 70 11 10 16 6.1 g Content (metric tons) 6.9 5.6 D" 83 56 12 56 63 50 100 20rthophosphate 83 83 100 63 71 Total Phosphorus nitrate-nitrite + a m nia 37 p 77 Orthophosphate PE 6.5 6.5 6.4 6.5 6.5 6.2 6.0 6.1 6.2 Average 6.3 6.1 6.4 Conductivity 15.4 17.7 17.5 16.8 15.1 17.5 20.0 20.7 17.6 18.6 20.3 17.5 Average (puhoice) 4

Table 1.3.1-3 Descriptive Statistics for Lake Keowee. 1977 February hrch April January Hean h ximum Minimum _Mean h ximum Minimum Mean h almum Minimum han Maximum Minimum 7.8 13.4 10.t 17.3 6.8 ~13.1 20.2 7.3 Temperature (C) 10.4 15.7 8.0 4.4 11.0 12.3 9.7 10,9 12.2 9.1 10.1 11.4 7.8 Dissolved Oxygen (ag/1) 10.4 11.4 8.9 6.2 6.8 5.4 6.5 7.0 6.3 6.7 7.4 6.3 PN 6.3 6.9 5.5 16.9 23 13 15.2 18 12 Specific Conductance (puhos/cm) 17.7 42 14 17.8 23 15 8.1 4 7.7 12 5

.[e Alkalinity (eg/1-CACO )

3 7.4 8 7 7.8 9 7 13 4

U ' Turbidity (JTU) 5.0 35 3 5.2 14 3 10.2 100 5.1 7 3

.068 .126 .21 .066 .137 .34 .092

Nitrate-nitrite (mg/1-M) .104 .16 . .071 .168 .46

.26 .041 .182 .50 042 .245 1.2 .084 Amonia (ag/1-M) .125 44 .023 .109

.009 .005 .005 .007 .005 .005 .007 .005

' Ortho-phosphate (ag/1-P) .005 .007 .005 .005 Total Phosphorus (ag/1) .007 .027' .005 .006 .016 .005 .009 .062 .006

.008 .025 .005

.98 .15 .231 .80 .10 494 3.3 .22 Iron (ag/1)' .154 .23 08 . .267 Manganese (ag/1) .*2 .05 .050 .07 .05 .075 1.0 .05

.051 .07 .05 .055 1.8 .91 1.54 2.0 1.0 1.48 2.3 1.2 Calci m (as/1) 1.31 1.6 .79 1.18 e

.43 .551 .72 .45 .562 .68 .46 .525 1.1 '40 R Magnesium (ag/1) ~ .549 .62 0 4.6 3.4 3.39 3.9 3.0 3.12 3.4 2.8 3.12 3.4 2.8 Silica (ag/1-S1)' 4.11 100 375 420 280 363 410 260 Outdation Reduction Potential (sv) 335 350 300 303 370 7.8 1.2 1.51 2.7 1.0 1.68 5.7 1.1 Chloride (mg/1) 1.51' 3.6 1.0 1.56 s

g. - - - . . - . . . _ - - _ - - - - -

Table 1.3.1-3 (Cont.)

by June July August Mean Maximum _, Minimum Mean haimum Minimam han kainum Minimaan Mean . Maimum Minimum Temperature (C) 16.7 23.2 8.7 19.0 26.2 9.4 21.8 31.7 9.9 - 22.6' 29.7 10.8 Diseolved Oxygen (mg/1) 9.3 11.2 5.8 8.2 10.8 1.4 7.1 10.2 .9 6.1 9.1 .0' pH 6.4 7.3 5.9 6.4 7.4 5.9 6.5 7.9 6.1 6.5 8.3 6.1 y g Specific Conductance (puhos/ca) 17.7 21 15 20.3 28 16 20.7 46 17 17.8 31 14 L[. Alkalinity (ag/1-CACO)J 3 .6. 9 8 6 5.6 24 3 6.1 8 3 7.7 21 6 e

U' Turbidity (JTU) - 3. 4 - 12 2 6.1 14 3 10.2 66 2 5.8 37 2 Nitrate-nitrite (ms/1-N) .123 .26 .072 .115 .26 .033 .106 .27 .024 .103 .27 .037 Ammonia (ag/1-M) '.116 1.1 .028 .086 .23 .013 .149 .36 .065 .177 .73 . .064 Ortho-phosphate (ag/1-P) .005 .005 .005 .005 .009 .005 .006 .016 .005 .006 .023 .005

' Total Phosphorus (mg/1) .008 039 .005 .006 .017 .005 010 .026 .005 .026 .53 003

. Iron (ag/1) .274 2.0 .06 .159 .86 .03 .413 6.0 .04 .479 5.1 .10 Manganese (mg/1) .021 .15 .01 .C80 .70 .01 .203 2.4 0.3 h' Calcium (mg/1)- 1.64 2.2 1.4 1.65 1.9 1.5 1.65 2.0 1. 4 '

Magnesium (mg/1) .524 81 .42 .520 .62 .45 .593 .71 '.4 7

" ' Silica (mg/1-S1) l 3.19 3.5 2.8 3.27 3.8 2.9 3.10 3.7 2.9 1.74 7.3 64 Oxidation geduction Potential (av) 359 400 270 386 420 270 290 380 130 353 400 20 Chloride (mg/1) 1.16 2.6 .9 1.25 3.1 .9 1.20 2.7 .8 1.75 3.8 1.3 e

s Table 1.3.1-3 (Cont.)

September October hvember December Mean Maximum Minimum Mean Maximum Minimum Mean Naimum Minimus _Me.?m halmum Minimum

' Temperature (C)I 23.9 28.6 11.2 22.1 27.5 12.6 17.9 21.4 T.1.1 12.8  !! .: 11.3 '

. Dissolve 3 0xygen (ms/1) 5.1 8.2 .0 5.7 7.8 .0 7.4 8.6 .1 8.9 9.4 8.0 pH - 6.2 7.0 5.7 6.1 7.1 5.6 6.4 6.6 5.8 6.2 6.4 6.1

~

\] .pSpec1EicConductance(puhoe/ca) 18.8 62 15 21.5 92 15 17.7 46 14 17.4 - 35 12

'(Alkalinity (ag/1-CACO) 3 8.4 - 33 6 9.9 22 6 7.7 22 6 5.8 8 3 Tu bidity (JTU) 6.7 40 2 6.1 35 2 4.5 23 2 4.9 10 .3 Nitrate-mitrite (ag/1-N) .062 .24 .0?O .089 .29 .037 .107 .24 .051 .124 .21 .078

- Ammonia (ag/1-N) .170 .44 .075 .211 .86 .058 .276 .94 .091 .078 .17 .030

' Ortho-phosphate (ms/1-F) ' .005 .010 .005 006 .012 .005 .007 .026 .005 .005 .005 .005 Total Phosphorus (ag/1) .009 .034 .005 .008 .019 .005 .015 .031 .008 .005 .005 .005 1ros'(mg/1) .482 9.4 .05 .709 13 .07 .400 4.3 .10 .208 .34 31

Manganese (mg/1), .352 3.1 01 .550 4.2 .02 .134 4.0 .01 .056 .14 .C 1 hCalcium(ag/1) 1.93 2.5 1.6 1.92 2.9 1.5 1.35 1.5 1.1 1.34 1.5 .93

.'kMagnostam(ms/1) .648 .78 .54 .603 .78 .49 . 49t' .>8 .40 .481 .56 .35 0

Silica (mg/1-51) -3.07 3.8 2.8 3.25 4.0 3.0 3.35 3.5 3.0 3.15 3.4 2.8 l Omidation seduction Potential (av) 377 430 -70 363 450 -190 393 440 100 387 430 280 Chloride (ag/1). 1.47 2.50 1.2 1.68 2.4 1.2 2.18 4.5 1.6 1.58 3.6 1.3 W? .__ -_ ., . - - _ ___

Table 1.3.1-4 Descriptive Statistics for take Bartwell,1977.

February March April January Maximum Minimum Mean Maximum Minimum Mean- Maximum Minimum 7 _

.Mean- Maximum Minimum Mean 6.8 6.5 6.8 9.3 4.4 10.2 13.8 6.7 13.8 19.5~ 8.2' Temperature (C) '7.0 Dissolved Oxygen (ms/1)'

11.4' 10.2 11.6 12.6 10.7 11.0 12.1 9.8 8. 9 ' 11.1 6.7

-10.8 7.2 6.6 6.2 6.7 5.8 6.7 7.0 6.4 6.9 7.6 6.2 pH 6.9

.. Specific Conductance (puhos/ca) 19.5 22 - 17 25.0 31 19 24.0 27 21 20.0 24 16 8.4 7 9 8.0 8 8 10.4 5 15 ~ 9.4 12 7

- $,.Alkaltaity(mg/1-CACO). 3 U.' Tusbidity (JTU). 7. 3 - 15 4 6.6 9 6 5.4 11 3 19.5 60 5

- Nitrate-nitrite (eg/1-M) .28 .44 .15

.' Ammonia (mg/1-N) .11 .20 .067 Ortho-phosphate (eg/1-P) .005 .007 .005 Total Phosphorus (ag/1) .015 .021 .009

.46 .16 .29 .42 .19 .32 1.0 .14 .83 1.9 .37 Iron (mg/1) .30 Manganese (ag/1) .05 . .05 .05 .05 .05 .05 .05 .09 .05 .05 .12 .05 1.4 1.7 1.1 1.6 1.9 1.3 1.9 2.5 1.6 1.7 1.9 1.5

l. Calcium (ag/1)

.64 .70 .56 .63 .68 .59 .70 .94 .57 .62 .73 .53

.! Magnesium (ag/1)

" 3.7 4.1 3.4 9111ca (ag/1-Si) 280 250 285 330 240 325 390 260 390 430 350

' Oxidation Reduction Potential (ev) 265 Chloride (ag/1) 2.1 3.4 1.4 4

4 r ___.L_--_.

_ ..m._ _ . . _ . .. _ ._ . . _ _ _ _ _ ..

.r Table 1.3.1-4 (Cont.)

July August Nay June Minimum Mean Maximum Minimum Mean Maximum Minimum Mean Maximus Minimum Mean Nazimum Temperature (C) 19.6 26.5 12.7 22.3 31.0 13.6 22.5 30.4 14.6 17.2 .23.2 11.2 Dissolved Oxygen'(ag/1) 5.3 10.5 0.3 4.6 9.1 0.1 4.4 8.8 0.0 6.4 10.4 2.4 8.5 5.9 7.0 8.0 6.0 7.1 8.1 - 6.1 PH 7.2 8.0 6.3 7.2 Specific Conductance (pehos/ca) 29.0 38 20 37.0 52 22 46.0 71 21

y. 23.0 27 19 w'

. Alkalinity (mg/1-CACO ) 7.8 10 7 10.9 18 7 14.2 34 6

3. 8.1 ' 10 7

• 9.5 24 3 14.9 30 4 12.5 38 3 Turbidity (JTU) 9.0 280 3

.20 .37 .027 .14 .35 .035 .065 1.5 .028 Nitrate-nitrite.(mg/1-N) .24 ,4 .095 Ammonia (eg/1-N) .08 .19 .027 .28 .53 .074 .33 .90 .058

. 09 . .20 .035 Ortho-phosphate (mg/1-P) .007 .010 .005 .006 .018 .005 .022 .052 .006

.005 .005 .005

.024 .005 .015 .025 .009 .044 .19 .013 Total Phosphorus (mg/1) .017 .078 .009 .012

.36 1.1 .10 .83 4.9 .10 1.5 6.3 .16

.1ron (ms/1) .64 1.9 .26

.35 1.3 .01 .51 1.7 .06 Manganese (ms/1) . .07 .34 .01 1.9 2.2 1.6 1.9 2.2 1.7 2.3 2 1.8

. Calcium (ms/1) 2.0 12.5 1.8

.69 .79 .57 .80 .87 .63

k Magnesium (ag/1) .66 .94 .54 .63 .74 .52 0 3.8 3.2 3.4 4.3 2.7 2.7 3.3 2.3 Silica'(ag/1-S1) 3.3 3.7 2.5 3.5 380 280 170 300 40 90 340 -160 Outdation Reduction Potential (av) 290 '360 220 330 1.1 -1.2 2.3 3.7 1.4 2.5 4.1 1.6 Chloride (ms/1) 1.7 2.1 2.0 2.8 4

. 'j a

Table 1.3.1-4 (Cont.)

September October November Dec dser Maximum Minimum Mean Maatsum Minimum Mean Maximum Minimus Mean . maimum Minimum

'Mean c1 Temperature (C) 22.0 27.3 16.6 21.8 23.7 19.8 17.4 18.8 16.0 12.8 14.9 10.8

, Dissolved Oxygen (ag/1) 3.5 7.0 0.0 3.9 7.8 0.0 7.8 8.8 6.7 9.2 9.8 8. 6 .-

6.2 6.5 5.8 6.4 6.8 6.1 6.7 7.0 6.4 6.4 6.9 6.0

_pH.

Specific conductance (puhos/ca) 48 77 18 45 74 16 24 30 18 26- 32 19

y Alkalinity (m&/1-CACO3) 15.4 40 4 10.9 18 8 9.0 11 6 6.0 7 6.

5 Turbidity (JTU) 10.5 135 4 11.0 31 4 9.7 25 4 s.9 27 5' Nitrate-nitrite'(ag/1-N) .04 .28 .021 .10 .13 .072 .16 .24 .091 .16 .24 .097 Ammonia (mg/1-N) 1.6 7.1 .11 .24 .068 .60 .38 .89 .10 .058 .11 .030 Ortho-phosphate (ag/1-P) 007 .025 .005 .006 .009 .005 .006 .012 .005 .006 .007 .005

' Total Phosphorus (ag/1)' .021 .054 .009 .006 .013 .005 .G15 .042 .005 .006 .010 .005 Iron (ag/1) 2.2 8.3 .16 .36 .95 .15 .74 2.2 .30 .35 .65 .18 Manganese (mg/1)' .65 2.6 .06 .16 .84 .05 .06 .45 .03 .05 .11 .02 Calcium (ag/1) 2.7 3.3 2.2 1.9 2.3 1.6 1.6 1.8 1.4 1.6 '1.7 1.4 h~

.90 1.1 .77 .67 .84 .57 .58 .65 .50 59 .66 .49

.- . Magnesium'(mg/1)

-Silica (ag/1-S1) 3.7 4.6 3.1 3.5 4.4 3.1 3.5 4.0 3.2 3.3 3.6 3.1 380 -120 200 410 -10 415 430 -400 375 410 340

. Oxidation Reduction Potential (av) 130 2.4 4.1 1.3 2.3 3.0 1.2 2.8 5.0 1.6 1.9 2.3 1.3 Chloride (as/1) i 1

4 7

0 0-

Page 1 of 5 Table 1. 3.1- 5 . Summary of weekly dissolved oxygen monitoring for May through November, 1977 Date Station

• Temp. C DO mg/l l

S/05/77 Oconee Intake 13.3 9.2-9.0 l Oconee Discharge 21.3 8.7-8.7 Keowee Hydro Intake 21.7 9.0-9.0 -l Keowee Hydro Discharge 19.1 9.4-9.5 Station 605 19.8 9.8-9.8 {

1 5/ 12 /77 Oconee Intake 14.9 8.5-8,5 Oconee Discharge 21.6 8.5-8.7 Keowee Hydro Intake 21.8 8.7-8.8.

~

Keowee Hydro Discharge 20.4 9.4-9.4 Station 605 20.7 9.5-9.6 5/19/77 Oconee Intake 14.0 8.8-8.5 ,

Oconee Discharge 22.8 8.5-8.6 l Keowee Hydro Intake 24.6 8.6-8.7 Keowee Hydro Discharge 21.7 9.2-9.3 Station 605 22.1 9.5-9.6 5/26/77 Oconee Intake 15.0 7.9-8.0 Oconee Discharge 22.6 7.9-8.0 Keowee Hydro Intake 22.6 8.2-8.2 Keowee Hydro Discharge 22.0 9.2-9.1 Station 605 22.1 9.1-9.3 6/02/77 Oconee Intake 15.8 7.6-7.6 Oconee Discharge 23.4 7.7-7.8 Keowee Hydro Intake 25.2 8.2-8.3 Keowee Hydro Discharge 21.7 9.0-9.0 Station 605 22.3 9.1-8.9 6/09/77 Oconee Intake 17.3 - 7. 5-7. 6 Oconee Discharge 25.4 8.0-8.1 Keowee Hydro Intake 25.1 8.3-8.0 Keowee Hydro Discharge 23.1 8.5-8.4 Station 605 24.2 9.2-9.2 6/16/77 Oconee Intake 17.2 7.3-7.1 Oconee Discharge 25.0 8.2-7.7 Keowee Hydro Intake 26.5 9.4-9.0 Keowee Hydro Discharge 25.0 9.0-9.5 Station 605 24.8 7.8-8.3

• Measurements were taken at the facility structures.

1.3.1-27 . ONS 12/77

Page 2 of 5 Table 1. 3.1- 5 (. cont. ) . Summary of weekly dissolved oxygen monitoring for May through November,1977 Date Station Temp. C DO mg/l 6/23/77 Oconee Intake 17.7 7.2-7.3 Oconee Discharge 24.5 7.4-7.5 Keowee Hydro Intake 26.9 8.1-8.2 '

Keowee Hydro Discharge 24.8 8.4-8,5 Station 605 25.0- 8.6-8.6 6/30/77 Oconee Intake 18.0 6.6-6.5 Oconee Discharge 26.1 6.6-6.8 Keowee Hydro Intake 28.5 7.9-7.9.

4 Keowee Hydro Discharge 25.5 8.1-8. 3 Station 605 25.5 8.1-8.1 7/07/77 Oconee Intake 19.1 6.1-6.2 Oconee Discharge 27.9 6.9-7.1 Keowae Hydro Intake 30.9 7.8-7.8 Keowe. Hydro Discharge 23.4 7.8-7.6 Station 605 25.1 7.8-7.9 7/12/77 Oconee Intake 20.3 6.1-6.4 Oconee Discharge 26.6 6.8-6.7 Keowee Hydro Intake 30.0 7.9-7.7 ,

Keowee Hydro Discharge 25.2 7.8-8.1 Station 605 25.7 7.8-7.8 7/21/77 Oconee Intake 20.8 6.5-6.6 Oconee Discharge 28.1 7.1-7.0

- Keowee Hydro Intake 30.5 7.7-7.8 Keowee Hydro Discharge 26.3 7.8-7.7 Station 605 26.0 7.3-7.2 7/28/77 Oconee Intake 20.0 5.4-5.3 5.6-5.5 Oconee Discharge 26.1 Keowee Hydro Intake 26.6 7.3-7.4 Keowee Hydro Discharge 24.3 7.0-7.1 Station 605. 25.7 7.6-7.4 8/04/77 Oconee Intake 20.6 4.8-4.9 Oconee Discharge 27.8 4.8-5.0 Keowee Hydro Intake 27.2 6.1-6.2 Keowee Hydro Discharge - 25.2 7.2-7.2 Station 605 25.2 7.5-7.5 1.3.1-28 ONS 12/77 1

4 i

Page 3 of 5 Table 1.3.1- 5 (Cont. ) . Summary of weekly dissolved oxygen monitoring for May through November, 1977 Date Station Temp. C DO mg/l 8/11/77 Oconee Intake 22.3 5.4-5.4 Oconee Discharge 28.0 7.1-7.2 Keowee Hydro Intake 29.3 7.7-7.9 .

Keowee Hydro Discharge 25.3 7.0-7.4 Station 605 26.1 7.5-7.4 8/18/77 Oconee Intake 21.6 5.0-4.9 Oconee Discharge 27.2 5.5-5.8 Keowee Hydro Intake 26.8 6.6-6.6 Keowee Hydro Discharge 25.7 7.2-7.5' Station 605 25.9 7.2-7.3 8/24/77 Oconee Intake 22.5 4.9-4.9 Oconee Discharge 27.2 5.7-5.8 Keowee Hydro Intake 27.0 7.5-7.6 Keowee Hydro Discharge 25.5 7.4-7.5 Station 605 26.0 7.6-7.6 9/02/77 Oconee Intake 23.2 4.3-4.4 Oconee Discharge 28.2 4.7-4.9 Keowee Hydro Intake 27.8 5.7-5.6 Keowee Hydro Discharge 26.8 6.7-6.7 Station 605 27.1 6.8-6.7 9/08/77 Oconee Intake 23.6 4.6-4.3 Oconee Discharge 28.8 4.5-4.6 Keowee Hydro Intake 27.9 5.3-5.3 Keowee Hydro Discharge 27.2 6.7-6.8 Station 605 27.5 6.8-7.0 9/15/77 Oconee Intake 23.6 5.0-4.9 Oconee Discharge 27.4 5.5-5.4 Keowee Hydro Intake 27.0 5.6-5.7 Keowee Hydro Discharge 26.0 6.9-6.9 Station 605 26.6 7.0-7.0 9/22/77 oconee Intake 24.7 5.4-5.2 Oconee Discharge 27.5 5.2-5.2 Keowee. Hydro Intake 27.0 6.1-6.2 Keowee Hydro Discharge 26.3 7.6-7.8 Station 605 26.6 7.7-7.7 1.3.1- 29 ONS 12/77

Page 4 of 5 Table 1.3.1-5 (Cont.) . Suusnary of weekly dissolved oxygen monitoring for May through November, 1977 Date Station Temp. C DO mg/l f 9/28/77 Oconee Intake 24.8 5.5-5.4 ,

Oconee Discharge 28.6 5.4-5.5 1 Keowee Hydro Intake 28.9 6.1-6.1 ,

Keowee Hydro Discharge 27.3 7.0-7.0 Station 605 27.2 7.2-7.2 10/06/77 Oconee Intake 24.6 6.4-6.2 Oconee Discharge 28.2 6.4-6.3 Keowee Hydro Intake 26.7 6.5-6.4 Keowee Hydro Discharge 26.0 7.5-7.5 i Station 605 26.1 7.2-7.2 7.2-7.2 I 10/13/77 Oconee Intake 22.9 Oconee Discharge 24.3 7.1-7.1 Keowee Hydro Intake 23.8 7.0-6.9 Keowee Hydro Discharge 23.5 8.3-8.3 ,

Station 605 23.3 8.4-8.5 10/21/77 Oconee Intake 21.1 7.6-7.5 ,

Oconee Discharge 25.7 7.7-7.8 Keowee Hydro Intake 23.3 7.9-7.8 Keowee Hydro Discharge 21.9 7.6-8.0 Station 605- 22.2 8.9-8.7-10/27/77 Oconee Intake 19.8 8.4-8.2 Oconee Discharge 21.0 8.0-8.6 Keowee Hydro Intake 21.7 7.e-8.4 Keowee Hydro Discharge 21.7 7.9-7.6 Station 605 20.9 7.5-8.0 Oconee Intake 19.7 8.7-8,5 11/03/77 Oconee Discharge _ 23.6 7.9-7.7 Keowee Hydro Intake- 22.6 8.1-8.0 Keowee Hydro Discharge 21.6 8.0-8.1 Station 605 21.5 7.9-8.3 11/10/77 Oconee Intake 18.9 7.8-7.7 Oconee Discharge 24.7 7.6-7.7 Keowee Hydro Intake 20.9 7.9- 8.2 Keowee Hydro Discharge 19.8 10.2-9.6 i

Station 605 19.2 8.9-8.9-1.3.1-30 ONS 12/77

1 Page 5 of 5 Table 1.3.1-5 (Cont. ) . Summary of weekly dissolved oxygen monitoring for May through November, 1977 Date Station Temp. C DO mg/l 11/17/77 Oconee Intake 17.9 8.6-8.8 Oconee Discharge 21.4 8.1-8.0 Keowee Hydro Intake 20.3 8.3-8.6 -

Keowee Hydro Discharge 18.8 9.3-9.3 Station 605 19.0 8.7-8.8 11/22/77 Oconee Intake 17.4 8.5-8.6

, Oconee Discharge 21.6 8.2-8.7  ;

Keowee Hydro Intake 19.3 8.8-8.6 i Keowee Hydro Discharge 18.4 9.2-9.6 l Station 605 18.2 7.9-10.0  :

l l

l 1.3.1-31 ONS 12/77

l Table 1.3.1- 6.

SUMMARY

OF KE0 WEE TAILRACE TEMPERATURE Data: Amounts (average for month and maximum within month) by which temperatures recorded during generating mode exceeded those during non-generating mode of Keowee Hydro. (See text for further explanation).

MONTH MEAN MAXIMUM (C') (C*)

January +0.8 +2.7 February +0.1 +2.1 l

March. .+1.5 +3 0 April +2.4 +5 0 May +1.8 +1 7 4

June +1 3 +3 1 July +1.7 +3 2 August + 1.1 +1 7 September +0.7 +1.8  !

October +0.4 + 1 '. 4 l l

November +0.5 +1.2 .

l i

December +0.6 +1.6 l l

1 1.3.1-32 ONS 12/77

i i i i i i i

.. . . . . . . .- . . . . . . . 7 ~,

" j W o o

~

2 7 o_ . --

)

=- -

o ~

~

. . - . . . .  %. . . . . . . S. 8

,o

~

.~

. . . . . . . . . u- $

~ _

g u

as 9

p o. T at 3

.N . . . . . .~ . . . . . . . . m. .a O.

m a

.M . . . . . . . . . . . . . . g. ,3

, 3

~

N Jll m - C 2

• c e

. . . . . . . . . . . .. g. z .

o a.

= N - g

o. he

. x M.

. . . . . . . . . . . . . . o. 2 o . - 1 6

o  :

8'*

- b .

. . . . . . . . . . . . . g. <g q o

4

.h  !

/2 c. 6 j

. . . . . . . . . . . . . ._ e. 3 g ,

a 1 g -

o.

M M 9

e% -

e.

g i 1-o I-

- -- = 4

~

a

=

s a = 2.

(satas) vicea -

_1.3.1-33 ons 12/77 3 ,

- . . o.._

. . . . . N, 8"

M o.

ame

- o ,

. . . . . . _- .a -

g o.

N o.

s

~

. . N. . . o.

= ,

• N a .

~. eG O

w t

E.

ad o e .

. g a

.3

. . . ., . . . . . . . . o.

8

\o.

O o.

W o.

e N

m N N R

~. 4 N O ee

• O m., . . . . . . . . . . g. a m O

~

o E

. . . . . . .d. ~ . . . . g. g $.

J3 s.e

- o -  ;

o O m e 49 9

j h b g

e

o. 2

. . . . . . . .s. . . . . .

1

.t.

~

. b I m

. . . . . . . . . . g, # 1 m.

m o

S 2 3

a.

C 6

. . . . . .og . . . .  %' 2 o

o o.

.. . . . . . .. . . . . g.g m

o -

t x.

e. C o ,3 m6 . . _. . . . . . e. 3.

o o h h

-ome .e o e e m

o M N N 9 1

1

.gsaatas) u dec ons 12/77 'l 1.3.1 i j

- t 1 r

e i i i i i i 2 . . . . . .

. . . . . . . . . y- 8 s..........

=. ,

h A 8 7

. . . . .~ a-

. . . . . . . . . . '. . . . g- y -

o a 4 -

/~ .

E a

.T

. \. . . . . .

o o

. . . . . . . .a . 3 5

-g . -

~ o

• 5

.n d

o -

.a . . . . . .~. . . . . . . 7 c. 4 3 4*

5e

- 3 2 s.

O c n

• < 4 u

. . . . . . .o. . . . . . . .

2 ie o 3, o -

• 3 x .

o E 1

. . . . .. . . S. -

1 g

e- .

- 5 7

/..

. . . .g. . . . .. . =, <A

o. 2 m.

o 6

. . . . . . . . . . . . e .. . -E

~

o

_ e. .

. 'i  :- f, o -

~

e e

". .' . . . . . . . -. . . . . . =<4 i i i i i I o

• 3 $ 2 N R I E

. (saatas) 4tda0 1.3.1-33 ONS 12/77 1

! 5 l l l 5

• I O u

.Z . . . . . . . . & g- .

. . . g, g O.

- to -

en O* sn Je

.......4D -e . . . . i r-

. . . W, t

- O, _

O

- N .

O.

N

- W e ee N

- - . . . . . . . . . l . . . . . O.

N

~

~

O

% i i -

\.....

Clk

...... . g< a 6.

_ 2

+ C 4 O I

~ J E

~

/ O -

e, ~.

= 3 N. . . . . . . . . . . . . O. g a*

" O N

C O. . . . . . . . . . . . . g. ,3 o, O , b e -

e ~

A (J

C *

. . Wi

. . . . 4 . .O . . . . ,3 2

~  %

- g

~

O J

- w

=

O.

2  %

. . . . . . . . . . . . . . - u.

O 4

I i

. . . . . g. . . . . . . g. g q e.

b O

W 4 .

4 *, g 6

O

. . N. .. .

- o

=N t

se

~ 4

.on . . . . . . . . . . .

r-i i i 3 i i

~5 O '" 8 f. 2 N R E I i

l (lastas)q;$ed i

'1.3.1-36 ONS 12/77-i

I 5 I l l l I I I I I I r~~~'

g , / 501.0 - - _

.Ms soso

/ soso - -

'sh 23 _

's -

'N w ' \

h N

~

Y 8 m -

/ \ ,

\

[. / 's e

IS - '\ *

/

/ 's \ ~

,/

~

\

/ /

/

~

g 10 -

/

,/ -

s.

N Nj/

I I I I I I I I I I I i s

1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct N ov Dee Month Fie==:8 3 i Surface Temperatures at Locations 5 01.0, 506.O', and 508.0 on Lake Keowee for 1977 Figure 1.3.1-5. Surface temperatures at Locations 501.0, 506.0 and 508.0 on Lake Keowee for 1977.

I I O I l 5 5 P N

• e u l

. . . . . . . . . . . . . . . . . ~. i l

l

- i se

( >

o. . . . . g no

- am. ,

w g.

--N I o .

g I

. . . .7 . . .WJ . . .  ? o.

o . l

~

- c -

me .

g

• 1 O

. . . . . . . . . . . o. ~. e ,

I.

ad

.e d

o. 3

• I a a

. . . . . . . . . . . o. <

O*

o

- no a

? S

~ * - 3 y 3 u

m. . . . . . . . . . . . . . . . ~. 3 he g 3 o* .a me

- == C n

e o* S P C w

. . . . . . . . . . .. *@. 3 o

• n j

=

.ee o.

- o a

we a

w 9 h I

o. 2

=

. . . . . . . . . . e. . . . . a 1>

\9O 3

• .ee k

a

. . . . . . . . . . . . . . ~. < j s=.0

- - S o.

ame O

s- S

. . . . . . . . . . . . . . . *- 2 E e.

m

• • *. n

. . . . . . . . . . . . . . . . ~ e w

- o, -

l M l

I C

'. . . . . . . . . . . g. 4 r

l

! I i i i t t i l

. o e o.e e

ce oN e

N o

M - #=t e .o y

(saalas)ytdeQ 1.3.1-38 ONS 12/77

3 8 6 s a i . i a

+

= -

m. u-

~

7. . . . . . . . . . . T ~ 8 o

- -g

. . .. . . . . . . . . . . e,

- ~

• /

8 o.e .

/.

- e _  ; -

• -, u

o. a 2

= . . . . .i. . . . , w, $

• o 5 J j o .=

g- -

j e

as , <

T

• o

. . . . . . . . . . . . 4 5!

e o

, a a 5* . . . . . 5 $

. . . . . . u, ,

- u

~--

= 2 E

'F

. . . . . . . , ,, ,E j

/. l. o 2

. d  ?

a w I

. . . . . . . . o.

2 as a

a b

. * . . . . . . . . . ~,

4 7'

.o --

&W A

. I a

b

• . . . . . . . .. . .. . 6" me E-o.

O _

e o

. . . .. . . . . . ,.- . . .. . , , e

u. . -

) _

9

• m s2 . . . .  :: =. 4 t t t- 't t t- 3

o. e .o ** e. - -

e o

M e

N' o

M-e

. evy ,o (5Jetas)'42da0 1.3.1 ones 12/77

4 5 I I I i 3 , 6 k u a

+ . . . . . . . . . .

,y

~-

9

~

N

• • o e . . . * . * ." 2.

o.

e d

O N *

• A o' E

~

P=

/ =

. o O

~

a. .

. ~- m .

.. . . . . . . . . . =.. . . . . - g hd

- 2 m* 3

. a e a a *

.. . . . . . . . . . . . . . m- g g

No ~

I 3 3

.. . . . . . . . . . . . g R.

+ A

- e E

e o -

F

=

e ,.

.. . . . . . . . . . . . . .< ,=

c.e O

a.

i

. . .

• X S.

E 3.

2 2>

.3 a

5 A ;...;.... -

.. ~.

g 5

E b $

7. . . 7. . . . . . . . . . . . L E t

i -

l A.

i e. e. e l o o. - m. ,4

. . . .f --

o, t

l n' i a e e i o

• a C R C R A 3Y

.(satan)y1da0 .

1.3.1-40 ons 12/77 1

1

11'j ;i

,1- i l1 ilI li a

l 8 9 h c 5

• . . . - . . '. . . o. , .

• 2-1 D

e g

5 g

.f

/

,0 .

v

• . . . * .. . . . 8 f I \ . 4- o 1 N I -

g 0 t c

0 0 O

. . . * * .. . , . + = o-t 7

0 .

i N 6 g

m 0

p

- . .

• e

.. . . . . , .

• 2-1 S

I ,5 0  ; .

5 0 4 m

g .

0 u 0 A

2

. . 8-f.**

s 1

g .

0

= . * * .. .

6 l

u m

. . . 2-1 J .

h t

g n o,

0. . o .

7 M

- . n

• .. . . . . . . 4- u .

1 J 0 .

l 8 g y .

a .

= . . * * .. M

. . . . 0 1-I .

. g 9

r p

• . .

• a .. . . . . - . . . 2-1 A

1 y0 i

- 5 0 1 ,

1 .

1 .

r ,

• .. . * * .. . . . . . .

• 4-1 k 0

1 1

4 g

' . . b

. * .. . . . . . . . 4- e 1 F i'

4 0

2 n

1 - 0 a 1

1-1 J

0 5 0 5 0 5 0 5 C .

1 3 2 2 3 3 -

4 e.

it*t 5$

. - z0 o .e~~

N

. .,'t

o 12.0-- '

11.0- -

i w

10.0- -

L. ' ,,

9.0-b g^

g ' 4 x 8.0 V '

5 7.0- -

53 oE '

j' um 6.0- -

J' +

o' ,(l 5.0-o' -

s o <

a 4.0-a $

t-s N

q 3.0--

2.0 -

1.0- -

0.0 ;;;;;;;;;;;;;;;;;;;;;;;;;;;.;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;

1971 1972 1973 1974 1975 1976 1977 YEARS Figure 1.3.1-10. Total dissolved Oxygen content for Lake Keowee from January 1971 through December 1977,

Fe 2%

Al 2t ir K 4%

Mg 4%

Ca 6%

HCO3 33%

1 Na 14%

Cl 6%

510228%

1973-1976

• l Mn 1%

Al 3%

\\f l' K 4%

M9 5%

Ca 8% HCO3 32%

N Na 13%

Cl 9%

510224%

1977-Figure 1.3.1-11. Molar percentages of mineral constituents found in Lake Keovee during operational periods 1973 through 1976 and during 1977.

I l.3.1-43 ONS 12/77

{

o o N E O S A E .

1 N 7 A 7 C 9 N 1 A

M r o

f e

7 0

e 5 w o

e 0

K e

0 k .

3 a L

n o

s n

o i

t a

0 r i t 5

2 6

0 n

n 5

e c

n o

c e

s e

n 5 a g

a 0 0 5 n a

0 m 2

d n

a n

o m r K i 4

a 0 n 5 i 0 8 r a 4 s 5 5 n 1 o 3 i a 0 t 5 a i

r a

v 2 l

- ^ a 0 a 5 i 0 t a

p 0

1 S 2

1 1

- 3

_ t

_ - a e 5

1 0 . e

_ 8 r 5 u g

i F

M = - - - - - 0 0

i 0 0 0 0 '0 0 0 5 8 6 5 4 3 2 1 0 0 0 0 0 0 0 4E w*as .

gto Ub~

1

O IRON e MANGAMSE 0.80 -

Y w

0.70 -

b 0.60 -

Y a

E 0.50 -

0.40 -

O en t- 0.30 -

)

- ~

D i

0.20 -

0.10 -

i i i i i n i a i i MC ,

JAN FES MAR APR MAY JUN JUL AUG SEP OCT MV DEC Figure 1.3.1-13. Temporal variations in iron and manganese concentrations on Lake Keowce for 1977.

1.4 .

o LITTLE RIVER O NEAR FIELD 1.2 . l A FAR FIELD 1.0 .

.80 .

D z

.60 .

t

.40 .

.20 .

1 A . I i R A

. . 1 i .

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1973-1976 l

l j l.4 e LITTLE RIVER O NEAR FIELD 1.2 .

A FAR FIELD 1.0 .

l

.80 .

.60 .

l .40 . l

^

.20 .

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1977 Figure 1.3.1-14. Monthly variations in iron concentrations during operational periods 1973 through 1976 and during 1977 on Lake Keowee.

1.3.1-46 ONS 12/77 w ___ _ _ _ _ _ _ _ . _ _ __ _ _ _ _ - _ . ___ _ e

D LITTLE RIVER a LITTLE RIVER ,

0.8 -

A NEAR FIELD 0.8 - A NEAR FIELD e FAR FIELD e FAR FIELD 0.7 -

0.7 -

0.6 -

0.6 -

/

- m I L 40.5 -

g0.5 -

hE 0.4 0.4 0 -- -

03 - -

0.3 -

0.2 -

0.2 -

0.1 -

0.1 -

A <

w

. , . . . . . - e.

1 .

- w JAN FES MAR APR M44 JWN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG 5EP GCT NOV DEC O

ai 1973-1976 1977 0

3 u

Figure 1.3.1-15. Monthly variations in manganese concentrations during operational periods 1973 through 1976 and during 1977 on Lake Keowee.

.10 .

s LITTLE RIVER

.08 . O NEAR FIELD A FAR FIELD i

a. .06 .

, h 3

x i

.04 .

l i

J

.02 .  :

y . . .. _ _- -

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC i 1973-1976 ellTTLE RIVER )

I o NEAR FIELD

! A FAR FIELD

.06 .

I g .04 .

02 .

m m -

. m a a m a m -u _ _

Y Y Y Y Y Y Y Y 7 T T 7 FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN 1977 Figure 1.3.1-16. Monthly variations in orthophosphate concentrations during operational periods 1973 through 1976 and during 1977 on Lake Keowee.

1.3.1-48 ONS 12/77 1

I

'l i

- MONTMLY MELN

-- ANNGAL MEA 4

.035 - )

f I

.090 -

H '~ .,

P .025 -

'w w . .

.020 - -

E '

.015 -

Nk

~'

.010 - ' ' - -

.005 -

11111111111 11111111111 11111111111 11111111111 11111111111 <ll111111111J 11111111111 O

[ 1971 1972 1973 1974 1975 1976 1977 e

0 Figure 1.3.1-17. Monthly and annual variations in total phosphorus concentrations on Lake Keowee

from 1971 through 1977.

I

C E

U V

n o

i O N s n

o i

t a

r T t

.Y i C n O e c

n o

c s

P u

_ .. i SE r .

o

. hp s

o h

p G

i U A

l .

a) t e og t a r

d e nv

_. 1 L

U aa J ed t e 7 at 7 hh 9 pg 1 si N

oe U

hw

. i p-J oe hm t u rl oo Y i n(v E. i A H s7 7

~

n9 o1 i

t r ao if R r s P A

ae ve w

l o ae

_f rK o

pe R mk

- i A ea H TL 8

1 B 1

" - e E F 3 1

P e H r T u R P N g O T - I A i e X J F C

. - E D

'6 l e 2 0 8 0 1 0 0 C. _

_ a E

_ FM78 oE CD~ _

lI' .l1.l1l. 1, i 11 ll jlIl h

s n

o i

t a

r t

n e

c n

7 o ai 0 c

• 5 s

0 u r

0 i

o 3 h p

s o

h p

l a

t o

t 0 d i n 5

2 6 a

= i 0 ,

5 a

i n

o n

u n

a 5

• i 0 e 0 t 5 i i

0 r 2 t i

n e

t m a K

r t

4 i .

0 n7 7

-I 5 n9 0 8 i1 i

5 I 0 1 5 sr 3 of ne

. - = i 0 i 5 t e ae i w ro ae 2 vK

- - -I 0 5 l ake 0

i a 0

i tL 1 a pn S o 9

1 E

T I

S U

R O 1 1

R H .T 0 3 0 T P 5 1 i

I S 5 N O e

- H r E A P u T I g A N L i R O A F 1 M T 1

MO N A T o e O

- - - - - - o .

0 0< 0 0 i

0 0 o -

0 5 0 5 0 5 f 2 0 -

3, 2 1 1

0 0 0 a3* 0 0 0 YF7M Om TJ3* .

a

1j. ll o sY 5 0 1 1 5 i'

, C E

_ - D

.< '/ s u

r o

1. V h

p o O N

s o'

h

/ p l

a

/ T t~

o

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O d

n J a

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t o - E r .

S t i

N n e

t N a G r o U i t

A n N ,

a i

n

% L o 0 U m J m a

% 7 , .

7 n7 9

1 e7 g9 N y1

U x J or o

df N e ve l e ow so

% Y 0  : A se M iK d

e

% nk i a L

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1.3.1-55 ONS 12/77

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1977, 1.3.1- ONS 12/77 i

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1.3.1- 62 ONS 12/77

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mensured in the Oconee discharge during the period {

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l.3.2 FISH - POPULATION DYNAMICS AND REPRODUCTION Specification: A. Comparisons shall be made of the data obtained by systematic sampling of fishes using nets, electrofishing and rotenone at suitable loca-tions both within and essentially out of the influence of the effluent.

i Significant changes in the composition, abundance,

, and growth of the major fishes in various areas of Lake Keowee shall be identified and the i factors which cause change defined especially those relating to the effluent from Oconee Nuclear Station (Duke Power Company 1973a).

I. INTRODUCTION A discussion of the effects of power plant operation on the population dynamics of fishes was presented in the Oconee Nuclear Station Semi-Annual Report for the period ending June 30,

, 1973 (Duke Power company 1973b). Those studies are being per-i formed by the Southeast Reservoir Investigations (SERI), Fish and Wildlife Service, located in Clemsc ., South Carolina.

II. METHODS AND MATERIALS Methods and materials ur *ot fisheries research in connection with the operation of s evi been summarized in the ONS Semi-Annual Report for the period ending June 30, 1974 (Duke Power Company 1974). This program has continued th.angh Decembar 31, 1 1977, except for the discontinuation of electrofishing af ter October 1975. This decision'was made because of low numbers of fish collected with this technique.

2 III. RESULTS AND DISCUSSION Data necessary to characterize the dynamics of fish populations

- of Lake Keowee have been collected using seines, gill nets, and rotenone. A discussion of these data is provided by SERI in the following two reports: (1) " Highlights of Activities" which i covers the period October 1976 - September 1977 (Appendix C) and (2) an excerpt from the proposed annual work plan for-1977-78 (Appendix D).

. Seining Preliminary analysis of data from 1977 indicates a continuous decline in shoreline species except for spotail shiners.

1;3.2-1 ONS 12/77

Gill Netting The relative abundance of most species of fish have declined since 1973. Flat bullhead and black crappie appear to be the

• only major species increasing in relative abundance.

i Except for an apparent winter concentration of fish in the area of the heated effluent, no obvious changes in the adult fish population within the discharge cove were noted.

i Rotenoning .

The standing crops of three species (flat bullhead, redbreast sunfish and green sunfish) increased during the period 19731977.

Standing crops of other species have been variable and long term trends have not been established.

IV.

SUMMARY

AND CONCLUSIONS The studies conducted by SERI have provided valuable data con-cerning species composition, abundance and growth of Lake Keowee fishes. These data show: 1) a decline in the shoreline fish population; 2) a decline in the relative abundance of most species except for flat bullhead and black crappie; and 3) an increase in the standing crops of flat bullhead, redbreast sunfish and green sunfish, while other species are too variable to predict at this time.

It is not kn]wn if the changes in the fish populations in Lake Keowee are the results of a change in habitat (riverine to reservoir) or alterations in the lake causea by *he operation of Oconee Nuclear Station. However, with the exception of a winter concentration of fish in the heated discharge Of ONS, no obvious changes in the adult fish population within the discharge cove were noted.

REFERENCES CITED

, Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR-38, DER-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Commission, Docket flos. 50-269, 50-270,' and 50-287 (re vised August 1,1975,- NRC), Washington, D. C.

1973b. Oconee Nuclear Station. Semi-Annup.1 Report, Period Ending June 30, 1973,

' . 1974. Oconee Nuclear-Station. Semi-Annual Report, Period Ending June 30, 1974.

1.3.2-2 ONS 12/77 s

1.3.2 FISH - POPULATION DYNAMICS AND REPRODUCTION Specification: B. The reproduction of four (4) indicator species (largemouth bass, black crappie, yellow perch, and bluegill) representative of the fish species in Lake Keowee shall be characterized by deter-mining the environmental requirements for re-production. Pertinent data collected from other studies shall be utilized and results and obser-vations obtained for Lake Keowee shall be compared to those previously published. ~'

Spawning data for Lake Keowee shall be collected 1 by direct observation and the use of ichthyoplankton )

trawls.

The sampling procedures, periods, and intensity related to Specifications A and B above will be based on those established by the Southeast Reservoir Investigations team of the Fish and Wildlife Service, Department of the Interior (Duke Power Company 1973a).

I. INTRODUCTION A discussion of the effects of power plaat operations on the population dynamics of fishes was presented in the Oconee Nuclear Station Semi-Annual Report for the period ending June 30, 1973 (Duke Power Company 1973b).

II. METHODS AND MATERIALS The methods and materials used in studying the reproduction of Lake Keowee fishes have been previously described (Duke Power Company 1974). This program has continue'd without change through December 31, 1977.

III. RESULTS AND DISCUSSION Life history studies have continued on four indicator species representative of the species in Lake Keowee (Appendices C and D). These are: largemouth bass, black crappie, bluegill, and yellow perch. Life history studies have been divided into three distinct parameters for each species. These are: 1) age and growth, 2) reproduction and fecundity, and 3) food habits. Four study areas on Lake Keowee have been selected as sampling loca-tions for life history data. These areas are: 1) pumpback (between Lake Jocassee and Hwy.11), 2) north (mouths of Crow-1.3.2-3 ONS 12/77

Creek and Mile Creek arms), 3) middle (from the skimmer wall to 2 km north of Keovee Dam), and 4) south (from Little River Dam to Hwy. 188). During 1977 3 major tributaries were also sampled

. (Appendicies C and D).  ;

Trawl sampling, conducted March - September 1973 thru 1977, has 1 resulted in a steadily declining catch in three of four species of fish captured consistently each year. These three species were yellow perch, black crappie and sunfish. Threadfin shad having been stocked in the reservoir during January 1974 re-mained about the same during sampling 1974-1976 (Duke Power ,

Company, 1977). If these data represent an actual drop in abundance of these three species, competition from the recently introduced species, threadfin shad, may be an influencing factor.

It is possible, however, that these data may indicate a less efficient sampling as a result of changes in larval fish dis-tribution after the operation of ONS.

Gonads have been collected a?.d preserved from specimens since

, the 1973 field ceason began. Fecundity data are still being analyzed. Comparisons will be made between pre-operational and operational periods.

IV.

SUMMARY

AND CONCLUSIONS Data on the reproduction of,largemouth bass, black crappies, yellow perch, and bluegill have been collected using trawls, seines ar.d by direct observation. These data indicate a de-

- crease in mean number of larval fish per standard frame trawl haul at all stations from 1973 through 1977. Adequate data are not yet available for an assessment of the effects of ONS on the reproduction of Lake Kcowee fishes.

REFERENCES Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, D. C.

. 1973b. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1973.

. 1974. Oconee Nuclear Station. Semi-Annual Re-port., Period Ending June 30, 1974.

. 1977. Oconee Nuclear Station. Environmental Summary Report, 1971-1976.

1.3.2-4 ONS 12/77 (bs

1.3.3 PERIPHYTON Specification: Duplicate artificial substrates (plexiglass slides) shall be held in racks and submerged at a depth of five feet at three general locations in the lake (Stations 502, 504, and a station in the discharge area) that may be influenced by the plant discharge, and at two conttol locations in the lake (Stations 501 and 506) that shall be essentially out of the influence of the plant discharge. Dry and ash-free weights of each sample shall be determined so that comparisons can be made of the relative productivity values between the different stations (Duke Power Company 1973a) .

I. INTRODUCTION A general discussion of the concepts involved in this study has been presented (Duke Power Company 1973b).

II. METHODS AND MATERIALS Previously described methods and materials (Duke Power Company 1973a, 1973b, 1975a, 1975b, 1976) were followed during this report period except for the following changes:

Duplicate diatom proportional counts were discontinued since diatom community composition has already been established.

I'i. RESULTS AND DISCUSSION Organic Accumulation Organic accumulation rates are presented in Table 1.3.3-1 and seasonal and spatial trends are diagrammed in Figures 1.3.3-1 and 1.3.3-2. Seasonal trends of organic accumulation rates generally followed patterns of temperature and solar radiation; however, peaks of organic accumulation rates during periods of warm temperatures were lower than in previous years (Duke Power Company 1977), indicating a bimodal seasonal pattern (Figure 1.3.3-1).

Spatially, organic accumulation rates tended to follow patterns of nutrient concentrations (Chapter 1.3.1, Figure 1.3.3-2), as they had in previous years (Duke Power Company 1977).

Location 506.0 usually had the highest organic accumulation rates, followed by Locations 500.0 and 504.0. Lowest rates of accumulation were usually observed at Location 502.0 (Table 1.3.3-1, Figures 1.3.3-1 and 1.3.3-2). Organic accumulation rates in the'Little River arm were progressively lower from Locations 500.0 to 502.0, while those in the Keowee River arm were higher with increased distance from the plant.

Although nutrient concentrations were low at Location 508.0, consistent 1.3.3-1 ONS 12/77

f l

current increased nutrient availability and brought about higher rates 4

of accumulation at this location than would be expected. Ruttner (1953)

, found that current Provides for constant renewal of materials in solution 1 at the surfaces of organisms.

Community Composition l A total of 296 periphyton taxa were identified from Lake Keowee locations in 1977, including 62 genera, 175 species, and 59 varieties (Tables 1.3.3-2 and 1.3.3-3). Community composition in 1977 was similar to previous years, except thsc the Chrysophyceae contributed more to the mean total density (Duke Power Company 1977). .

Total Periphyton l

Total periphyton densities are presented in Table 1.3.3-4 and seasonal trends are diagrammed in Figure 1.3.3-3. Seasonal trends of periphyton densities were similar 'to those of organic accumulation rates, and were primarily a function of solar radiation and temperature. Tempera-tures at periphyton sampling locations during July of 1977 ranged from 29.3 C (Location 508.0) to 31.6 C (Location 502.0) and were 2.4 to 5.5 C higher than those in 1976 (Chapter 1.3.1; Duke Power Company 1976).

Whitford and Schumacher (1963) found that optimum temperatures for diatom development range from 14 to 22 C. Since diatoms constituted over 75% of the mean total density (Table 1.3.3-2), periphyton densities were comparatively lower during mid-summer.

Spatial trends of total periphyton densities were similar to those of previous years (Duke Power Company 1977), and to those of organic accumu-lation rates. Nutrient concentrations generally followed this same spatial pettern (Chapter 1.3.1, Figure 1.3.3-2). Highest densities were usually observed at Location 504.0, and lowest densities generally occurred at Location 502.0. Low densities in the vicinity of ONS, especially in the Little River arm, were a function of lower nutrient con-centrations brought about by induced mixing from ONS operation. Densities at Location 508.0 were also influenced by warmer winter temperatures and increased nutrient availability brought about consistent current.

Class Variations Since diatoms constituted over 75% of the mean total density (Table 1.3.3-2),

seasonal and spatial trends of diatom densities were similar to total densities. Trends were also similar to those of previous years, except for lower densities during mid-summer (Duke Power Company 1977). Diatom densities ranged from 1.3 X 10 3 units.cm-2 at Location 500.0 on March 1 to 343.8 X 108 units ca-2 at Location 504.0 on October 21 (Appendix B, Section 1, pages 26 and 34).

Major diatom taxa observed at Lake Keowee locations in 1977 were similar to those observed in 1975 and 1976 (Duke Power Company 1977). Those which were common at all locations (Achnanthes_microcephala, Anomoeoneis.

vitrea,-Melosira distans and Synedra _spp.) are all described as ubiquitous 1.3.3-2 ONS 12/77

and cosmopolitan (Lowe 1974; Patrick and Reimer 1966). Acidophilous forms such as Eunotia app. and Tabellaria spp. (Lowe 1974; Patrick and Reimer 1966), and rheophilous forms such as Comphonema parvulum (Patrick and Reimer 1975; Wallace and Patrick 1950) were more abundant at Location 508.0 as a result of more acidic conditions during stratified periods and consistent current. The types and proportions of diatom species observed at Lake Keowee locations are those generally associated with circumneutral, oligotrophic lakes (Hutchinson 1967). .

Green algae were generally most abundant from July through October, especially at Locations 504.0 and 508.0, where this class, composed primarily cf Mougeotia spp., constituted over 40% of the total densities ,

on July 28 (Appendix B, Section 1, page 31).

Densities of green algae ranged from 34.0 X 10 3 units cm-2 at Location 501.0 on March 1 to 111.7 X 103 units cm-2 at Location 504.0 on July 28 (Appendix B Section 1, pages 2 and 31). Seasonal and spatial distri-butions of Chlorophyceae were similr.r to previous years, except that densities in 1977 were consistently lower. Since lower densities were observed at far field locations, as well as those in the vicinity of ONS, this could not be related to the operation of ONS.

Densities of chrysophytes were higher in 1977 than in previous years at all locations in Lake Keowee (Duke Power Company 1977). No chrysophytes were observed at Lake Keowee locations in January ard February. Chrysophyte densities peaked at Location 504.0 on May 31 (106.8 X 16 3 units.cm-2) when they contributed nearly 40% to the total density. Epipyris ramosa, an epiphytic, colonial chrysophyte, was the dominant species of this class (Appendix B, Section 1, pages 25, 26 and 29).

The Myxophyceae were most abundant in May, July, and October. Very low densities occurred from December through March. The dominant blue-green I alga was Oscillatoria geminata, a filamentous form which accounted for (

8.7% of the total density at Location 508.0 on May 31 (Appendix B, Section 1, page 29).

Patrick et al. (1969) found that blue-greens become dominant at tempera-tures over 35 C. Temperatures at Lake Keowee locations were never high enough to cause a shif t from diatoms and green algae to 'alue-green algae.

Low pH conditions in the discharge tended to favor green algae and acidophilous diatoms which are considered more desirable than blue-greens as they are within the food chain and do not form floating scums (Shapiro 1973).  !

l IV.

SUMMARY

AND CONCLUSIONS Seasonal trends of organic accumulation rates and densities generally. i followed patterns of solar radiation and temperature, as they have in previous years, except that a bimodal pattern was observed in 1977. Lower l

1.3.3-3 ONS 12/77 l

4 1

i ' organic accumulation rates and densities during the mid-summer of 1977 may have been due to naturally-occurring, lake-wide temperatures that were higher than those of previous years.

l Spatial trends of organic accumulation rates were similar to those of nutrient concentrations and total periphyton densities. Therefore, as l~

in previous years, lower organic accumulation rates and densities in the

' vicinity of ONS, especially in the Little River arm, were a function of reduced nutrient concentrations brought about by induced mixing from ONS operation, and not a result of thermal discharge.

j Although nutrient concentrations were low at Location 508.0, nutrient availability to attached algae was increased by current, especially during -

warm stratified periods. Increased nutrient availability and warm vinter temperatures influenced densities and organic accumulation rates at this location, as was noted in previous years. Increased nutrient availability

.and more acidic conditions brought about by the operation of ONS during stratified periods also caused a shift in diatom species toward more j acidophilous forms such as Eunctia spp. and Tabe11 aria spp., and rheophilous-

! forms such as Gomphonema parvulum.

l Community composition was similar to previous years except that chrysophytes were more abundant at all locations in 1977. Major taxa within classes were also the same as those found previously. Blue-green algae were not enhanced by the operation of ONS.

Based on periphyton species composition, densities and organic accumulation rates observed on artificial substrates, Lake Keowee can be classified as a circumneutral, oligotrophic lake. Lower organic. accumulation rates and densities during mid-summer of 1977 were probably a function of higher naturally-occurring temperatures throughout the lake, and not the operation of ONS.

f I

L l

1 f

I l

.1.3.3-4 ONS'12/77 l

l t

[.

REFERENCES CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47 and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2 and 3, Duke Power Company. U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270 and 50-287 (Revised August 1, 1975, NRC), Washington, D. C.

. 1973b. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1973.

. 1973c. Oconee Nuclear Station. Semi-Annual Report, Period Ending December 31, l'i73. .

1975a. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1975.

. 1975b. Oconee Nuclear Station. Semi-Annual Report, Period Ending December 31, 1975.

. 1976. Oconee Nuclear Station. Annual Report, Period Ending December 31, 1976.

1977. Oconee Nuclear Station. Environmental Summary Report 1971-1976.

Hutchinson, G. E. 1967. A treatise on limnology. Vol. II. Introduction to lake biology and the limnoplankton. John Wiley, NY. 1115 pp.

Lowe, R. L. 1974. Environmental requirements and pollution tolerance of freshwater diatoms. U.S.E.P.A. Cincinnati. 334 pp.

Patrick, R. and C. W. Reimer. 1966. The diatoms of the United States, Vol. 1.

Acad. Nat. Sci. Philadelphia, Monograph 13. 688 pp.

1975. The diatoms of the United States, Vol. 2, Part 1. Acad. Nat.

Sci. Philadelphia, Monograph 13. 213 pp.

, B. Crum and J. Coles. 1969. Temperature and manganese as determining factors in the presence of diatom or blue-green algal floras in streams.

Proc. Acad. Nat Sci. Philadelphia, PA. 64: 472-478.

Ruttner, F. F. 1953. Fundamentals of limnology. University of Toronto Press, Toronto. 242 pp.

Shapiro, J. 1973. Blue-green algae: Why they become dominant. Science, 179: 382-384.

Wallace, J. H. and R. Patrick. 1950. A consideration of Gomphonema parvulum Kutz. Butler Univ. Bot. Stud. 9: 227-234.

Whitford, L. A. and G. L. Schumacuer. 1963. Communities of algae in North Carolina streams and their seasonal relations. Hydrobiologia 22(2): 133-197.

1.3.3-5 ONS 12/77 .

Table 1.3.3-1 Periphyton organic accumulation rates in ag a- day- from December 30, 1976 through December 29, 1977, for locations in Lake Keowee, SC.

Values are averages of duplicate samples.

Exposure Period Locations Date (days). 500.0 501.0 502.0 508.0 504.0 506.0 Hean Feb i 1977 33 1.8 0.4 0.6 0.2 (1) 1.0 0.8 Mar 1 1977 29 1.8 3.1 2.7 2.9 3.2 2.9 2.8 Har 29 1977 28 5.8 4.7 5.0 8.2 8.1 8.0 6.6 Apr 29 1977 31 14.6 5.8 3.8 58.6 17.6 130.4 38.5 May 31'1977 32 28.6 7.6 6.2 14.2 52.8 47.8 26.2 36.1 20.0 19.9 27.6 34.9 46.6 30.8 Jun 301977 30 Jul 28 1977 28 (1) 45.0 14.2 50.0 36.2 67.1 42.5 Aug 31 1977 34 45.6 47.2 21.1 55.0 (1) (1) 42.2 r.

h' Sep 29 1977 29 95.6 32.6 23.2 (1) (1) - 103.7 63.8

'd', Oct 31 1977 32(2) 50.6 9.2 19.1 9.1 39.1 62.2 31.6 Nov 29 1977 29 11.2 4.0 4.0 8.0 8.0 45.0 13.5 Dec 29 1977 30 3.8 2.0 3.7 3.1 3.3 8.1 4.0 Mean 26.9 15.1 10.5 19.8 22.6 43.6 Sampler missing Location'508.0 this period = 31 days

+

3 us b

~

L

Table 1.3.3-2 Distribution of periphyton taxa and percent composition of algal classes in Lake Keowee, S. C., from December 30, 1976 through December 29, 1977.

Percent Taxon Genera Species Varieties Composition .

Baci11ariophyceae 26 112 50 75.6 Chlorophyceae 21 39 8 17.8 Chrysophyceae 4 6 0 4.5 Myxophyceae 4 7 0 1.3 Cryptophyceae 2 3 0 0.4 Dinophyceae 2 5 0 0.3 Euglenophyceae 2 2 1 0.1 Haptophyceae 1 1 0 <0.1 62 175 59 1.3.3-7 ONS 12/77

Table 1.3.3-3 Periphyton species list for Lake Keowce through December, 1977 Division: Chrysophyta Class: 3acillariophyceae

• Achnanthes deflexa Reim.

• A. exigua Grun.

• I. cf. hauckiana Grun.

• I. lanceolata (Breb.) Grun.

• I. lanceolata var, dubia Grun.

• • I. levanderi Hust.

• I. levisiana Patr. .

• I. linearis (W. Sm.) Grun.

• I. linearis f. curta H. L. Smith

• A. marginulata Grun.

• I. microcephala (Kutz.) Grun.

• *I. minutissima Kutz.

• I. saxonica Krasske

• • A. sp.

~

• Amphora ovalis Kutz.

• • A. ovalis var. pediculus (Kutz.) V. H.

Inomoeneis exilis (Kutz.) C1.

A. serians (Breb. ex Kutz.) C1.

• A. serians var. brachysira (Breb. ex Kutz.) Hust.

• I. vitrea (Grun.) Ross

• Asterionella formosa Hass.

Caloneis bacillum (Grun.) Meres.

• C. sp.

.Cocconeis placentula Ehr.

• C.

placentula var, lineata (Ehr.) V. H.

• Cyclotella meneghiniana Kutz.

• C. pseudostelligera Hust.

• C. stelligera C1. and Grun.

,Cymbella cf. cesatii (Rabh.) Grun. ex A. S.

• C.

gracilis (Rabh.) Cleve

• C. hybrida Grun.

• C. microcephala Grun.

• C. minuta Hilse ex Rabh.

• [.naviculiformis Auerswald

• C. tumida (Breb.) Van Heurck CI. turgida (Greg.) Cleve i

• Denticula elegans Kutz.

D. sp.

Diatoma vulgare Bory

• Diploneis ellipica (Kutz.) C1.

D. sp.

-* Observed during the sampling period of December'30, 1976 through December 29, 1977.

• • -Observed for the first time during the above sampling period.

1.3.3-8 ONS 12/77  :

i l

l 1

1

Table 1.3.3-3 (Cont) Page 2 of 7

• Epithemia zebra (Ehr.) Kutz.

Eunctia arcus var. bidens Grun.

• E_. curvata (Kutz.) Lagerst

• E. curvata var. capitata (Grun.) Patr. comb. nov.

• E. _exigua (Breb. ex Kutz.) Rabh. .

E. fallax A. C1.

• E_. flexuosa Breb. ex Kutz.

• E. flexuosa var. eur? phala Grun.

_E. incisa W. Sm. ex Greg.

E. cf. _incisa W. Sm. ex Greg.

• E. naegelii Migula

• E. pectinalis (O. F. Mull.7) Rabh.

E. pectinalis var. minor (Kutz.) Rabh.

E. pectinalis var, ventricosa Grun.

• E. perpusilla Grun.

• E. zasuminensis (Cabejszekowna) Korner

• E. sp.

• • Fragilaria capucina Desm.

• • F. construens (Ehr.) Grun.

F. construens var. venter (Ehr.) Grun.

F_ crotonensis Kitton F_. pinnata Ehr.

• F. vaucheriae (Kutz.) Peters

• F_. sp.

• Frustulia rhomboides (Ehr.) DeT.

• F. rhomboides var. amphipleuroides (Ehr.) DeT.

• F_. rhomboides var. capitata (A. Meyer) Patr.

F_. rhomboides var. crassinervia (Breb. ex W. Sm.) Ross

• F. rhomboides var. saxonica (Rabh.) DeT.

• • F. rhomboides var, virida (breb.) Cl.

Comphonema cf. abbreviatum (Ag) Kutz.

• G. acuminatum Ehr.

• G. acuminatum var. coronata W. Smith

_G. acuminatum var. turris Cleve G. angustatum (Kutz.) Rabh.

• G_. angustatum var. producta Grun.  ;

G. cf. apuncto J. Wallace  !

• • G. clevii Fricke G. constrictum Ehr. i G. constrictum var. capitata (Ehr.) Cleve

• • G. dichotomum Kutz.

• G. gracile Ehr. l

_G. intricatum Kutz.

G. lanceolatum Ehr.

• G_

parvulum- (Kutz.) Grun.

_ *G. puiggarianum Grun.

• G. sp.

_Gyrosigma spencerii (W. Smith) Grif. and Henf.

• Hantzschia amphioxys (Ehr.) Grun.

1.3.3-9 ONS 12/77 1

Table 1.3.3-3 (Cont) Page 3 of 7

• • Melosiss ambigua_ (Grun.) O. Mull.

• M. discans (Ehr.) Kutz.

• 5. distans var. alpigena_ Grun.

• 5. granulata (Ehr.) Ralfs

• M. granilata var. angustissima (Ehr.) Mull.

_M,. italica (Ehr.) Kutz.

• M. italica var, tenuissima

~

(Grun.) O. Mull.

• M. varians Ag.

~

T. sp.

• Meridion circulare (Grev.) Ag.

• Navicula _accomoda Hust. .

N. cf. accomoda Hust.

• • N, aikenensis Patr.

_N. cf. anglica Ralfs

• • N. anglica var. subsala (Gurn.) C1.

• • N. arvensis Hust.

5. capitata var hungarica_ (Grun.) Ross

5. cocconeiformis Greg, ex Grev.

• 5. cryptocephala Kutz.

N. contenta Grun.

5. decussis_ str.

• • N. elginensis (Greg.) Ralfs

• • N.

elginensis var. neglecta (Kras.) Patr.

N,. exigua var. capitata Patr.

N,. gregaria Donk.

N. halophila (Grun.) C1.

• N. hambergii Hust.

• 5. hustedtil Krasske

~

N. lanceolata (Ag.) Kutz.

N,. lateropunctata Wallace

~N.

lapidosa Krasske

• N. minima _Grun.

~

• N. mutica Kutz.

_N. mutica var. tropica Hust.

• • 5. mutica var. undulata (Hilse) Grun.

5. notha Wallace 85, paucivisitata Patr.

~

• N. pupula Kutz.

j. pupula var. capitata Sky. and Meyer N,. pupula var, elliptica Hust.

d

_N.

pupula var. mutata (Krasske) Hust.

N. radiosa var. parva Wallace

85. rhynchocephala Kutz.

N. rhynchocephala var. germainii_ (Wallace) Fatr.

• • 5. salinarum Grun.

C1.

• i. salinarum var. intermedia (Grun.)

N,. schroeteri var. escambia Patr.

N. cf. secura Petr.

• • 5. seminulum var. hustedtil Patr.

{.subtillissima. Cleve 1.3.3-10 ONS 12/77

Table 1.3.3-3 (Cont) Page 4 of 7 N,. viridula (Kutz.) Kutz.

• N. viridula var. linearis Hust.

i.viridulavar.rostellata (Kutz.) Cl.

• N. sp.

i

• • Neidium affine (Ehr.) C1.

cf. N. affine var. humerus Reim.

• N. affine var. longiceps (Greg.) Cl.

N_. iridis var. amphigomphus (Ehr.) A. Mayer N. sp.

Nitzschia acicularis W. Smith

• • N. acuta Hant.

• • j.agnita Hust. -

N. amphioxoides Hust.

N. denticula Grun.

• N. dissipata (Kutz.) Grun.

N. filiformis (W. Smith) Schutt

• N. fructulum (Kutz.) Grun.

• N. lorenziana var. subtilis Grun.

N. obtusa W. Smith

• [.palea (Kutz.) W. Smith

• N. paleacea Grun.

• • N. cf. romana Grun.

N_. sigmoidea (Nitzsch) W. Smith

• • N. sublinearis Hust.

• [.sp.

• Pinnularia biceps Greg.

P. biceps f. petersenii Ross P_. cf. borealis Ehr.

P. braunii (Grun.) Cl.

P. braunii var. amphicephala (A. Mayer) Hust.

• • P_. caudata (Boyer) Patr.

P_. cf. divergens W. Smith

• P. mesolepta (Ehr.) W. Smith P_. microstauron (Ehr.) Cl.

P. subcapitata Greg.

P_. subcapitata var. paucistriata (Grun.) Cl.

• P. sp.

Stauroneis amphioxys Greg.

• S_. anceps Ehr.

S_. ancepe f. gracilis Rabh.

S_. livingstonii- Reim.

• S_. phoenicenteron (Nitz.) Ehr.

S_. phoenicenteron f. gracilis (Ehr.) Hust.

• • S_. smithii Grun.

S_. sp.

Stephanodiscus sp.

• Surirella angustata Kutz.

S_. delicatissima Lewis S_. linearis W. Smith 1.3.3-11 ONS 12/77

Table 1.3.3-3 (Cont) Page 5 of 7 S. linearis var.-helvetica (Brun.) Meister S. ovata Kutz.

• S. sp.

Synedra acus Kutz.

'S. amphicephala Kutz.

• • 5. delicatissima W. Sm.

~

• 5. famelica Kutz.

• S. cf. miniscula Grun.

• S. parasitica (W. Sm.) Hust.

S. cf. parasitica (W. Sm.) Hust.

• S. radians Kutz.

• S. rumpens Kutz.

• 5. rumpens var. familiaris (Kutz.) Hust.

• S. rumpens var. fragilariodies Grun.

• S. rumpens var. meneghiniana Grun.

• S. rumpens, var. scotica Grun.

• ]5. socia Wallace

• S. ulna (Nitz.) Ehr.

• • [S.ulnavar.ramesii (Herib.) Hust.

• S. sp.

• Tabellaria fenestrata (Lyngb.) Kutz.

• T. flocculosa (Roth) Kutz.

Class: Chrysophyceae

• Dinobryon bavaricum Imhof

• • D. sp.

• Epipyxis ramosa (Lauterb.) Hillfard and Asmund

• • Kephyrion sp.

• • Mallomonas tonsurata Teiling

• • M. sp.

Class: Haptophyceae

• • cf. Chrysochromulina parva Lackey Unidentified chrysophyte cyst-Division: Chlorophyta Class: Chlorophyceae

• Ankistrodesmus falcatus (Corda) Ralfs

• • A. falcatus var. mirabilis (West and West) G. S. West

• • A. fusiformis Corda sensu Korsch A. sp.

• • Arthrodesmus sp.

• Characium ambiguum Hermann C. sp.

• Chlamydomonas sp.

• • Closteriopsis longissima var, tropica West and West

• Cosmarium angulosum var. concinnum (Rab.) W. and G. S. West

• C_.

asphaerosporum var. strigosum Norst.

.C. cosmetum Norst.

• • C. ornatum var. perornatum G. S. Wee

• • C. parvulum Breb.

• • C. phaseolus var. minor Boldt.

• • C, raciborskii Lag.

1.3.3-12 ONS 12/77 l

I 1

1 I

I

1 Table 1.3.3-3 (Cont)- Page 6 of 7  !

)

C. trilobatum var. depressum Printz

• C. sp. _ l

• • Crucigenia tetrapedia (Kirch) West i

• C. sp. l

• Diogenes gap.

{

• • Docidium baculum Brab. '

• • Gonatozygon monotaenium deb. l

• • Kirchneriella subsolitaria G. S. West '

• Monoraphidium contortum Thur.

• M_. setiforme (Nygaard) Komarkov-Legnerova pl. sp. .;

. *Mougeotia sp. A

• p[. s p . B Oedogonium sp.

Pediastrum duplex var, gracilimum West and West

• • Planktosphaeria gelatinosa G. M. Smith

• Pseudenoclonium bas 111ensis Vischer Scenedesmus abundans- (Kirch.) Chod.

• S. acuminatus (Lag.) Chod.

S. armatus (Chod.) G. M. Smith

• S,. (Turp.) Lag.

cf . bij uga, (Turp . ) Kutz.

• S. dimorphus

• • S. opoliensis var. contracta Pres.

• S.-quadricauda (Turp.) Breb.

• S,. sp.

• Selenastrum minutum (Naeg.) Collins Spyrogyra sp.

• • Staurastrum clevii Wittr.

S_. curvatum var, elongatum G. M. Smith S,. dejectum Breb.

• S. per.tacerum (Wolle) G. M. Smith

• S_. Meacercum Ralfs S,. sp.

• • Stigeoclonium subsecundum Kutz.

• S,. s p . , .

• Tetraedron caudatum (Lorda) Hansgirg T.-enorme (Ralfs)_ Hanagirg T. cf. list eticum ~ Borge

• T. minimum Braun l~ }.muticum'(A;Braun) Hansgirg

• • Ulothrix cf. zonata (Weber and Mohr) Kutz.

• Coccoid greens Unidentified green flagellates Division: _Cryptophyta Class: Cryptophyceae Cryptomonas ovata Ehr.

• C. phaseolus Skuja-

• C. sp.

• Rhodomonas minuta- Skuja 1

1.3.3 ONS 12/77 l

Table 1.3.3-3 (Cont) Page 7 of 7

• cf. Rhodomonas_minuta Skuja I

Unidentified flagellate Division: Cyanophyta-Class: Myxophyceae _ .

Agnenellum quadriduplicatum (Menegh.) Breb.

• • Anabaena sheremetevii Elen.

• A,. s p .

cf. A. sp. _

• Anacystis cyanea Drouet and Daily

-A.-incerta Drouet and Daily

-A.

thermale Drouet and Daily -

A. sp.

• 0scillatoria geminata Mene gh.'

l

• • 0_.

cf. tenuis _ Agardh

• 0. sp.

Phormidium angustissima West and West *

• • P._

cf. valderianum (Dep.) Gom.

• P. sp.

• Unidentified blue green filament Division: Euglenophyta -

Class: Euglenophyceae

• Euglena sp.

• • Trachelomonas volvocina var. punctata Playfair i Division: Pyrrhophyta Class: Dinophyceae

• Glenodinium sp.

' **Peridinium a.ciculiferum (Lemm.) Stein

• P. inconspicuum. Lemm.

• P_.

pusillum (Pen.) Lema.

P. wisconsinense Eddy

- *P. sp.

1

• Unidentified' Dinoflagellate il l

1 i l i.

1.3.3 OliS 12/77'- .j I

i -

l L ,

Table 1.3.3-4 Total periphyton densities in units.cm- x 103 from December 30, 1976 -

through December 29, 1977. Values are averages of duplicate samples . l Exposure

-Period Locations Date (days) 500.0 501.0 502.0 508.0 504.0 506.0 Mean Feb.1 1977 33 3.5 6.9 5.4 '17.7 (2) 25.4 11.8 Mar 1 1977 29 1.4 1.4 1.6 1.6 "4 . 8 4.2 2.5 Mar 29 1977 .28 26.3 3.7 2.6 3.1 12.7 9.4 9.6 Apr 29 1977 31- 72.9 29.7 15.1 119.8 124.2 123.9 80.9 May,31 1977 32 292.4 35.1 50.8 125.0 269.6 396.2 194.8 Jun'30.1977 30 (3) 35.1 13.1 95.4 33.8 46.6 44.8 Jul 28 1977 28 (2) 13.2 12.8 232.1 276.5 72.8 121.5 Aug 31 1977 34 131.9 77.6 31.7 228.1 (2) (2) 117.3

{

,L Sep 29 1977 29 95.7 11.1 23.0 (2) (2) 137.4 66.8 Oct 31 1977 3 (3) 19.7 59.3 29.8 405.3 254.5 153.7

'Nov 29 1977 29 54.0 12.8 12.2 (3) 47.6 78.1 40.9 Dec 29 1977 30 15.3 6.1 13.5 20.6 19.0 35.4 18.3 Mean 77.0 21.0 20.1 87.3 132.6 107.6 Bottom slides missing at Location 500.0 for Aug 31 and Location 502.0 for Sep 29.

2 Sampler missing 3

o. Top and bottom slides for densities missinf;

' E!

4 Location.508.0 this date = 31 days D"

f

.. .; M .* "'" ""

_J'&,. _ f ~- jYh }" %q~ %

~

'En A N%z:43 _

\ \),'"7^\h,,Bfhh \M7mM .,

,'r\ W s.'

P'AX\V.M\\N'V \\ \T Q N.g\ \' \N' ./ / Os.

r s._ , p " V h% \,-L e r s 1.,'X ..,

e ~

( w N.. M \' s D_,2vfA.\

-4 s ..

AN Av \ \ -

W Kw. ?y'e x,.o

\ .s

-s .'. I N \'

, , x\NO t '

3L 'N \^Y\TNi\\ ,, A ,.1' "T~\ \, b.j3o 4,o

', - . ' . . . Ty \\ i '

/

.. ., NTx sW. /h '9

,_2. \ \

FM\ s

\,

/

3'[o s,o

,, y

' ' \ '

\\\ s M\\\\\\ 1

%' l

.?c , \.. / n

.yy \ , ;

' b . . ' \ \. \ D _ .. . . . _. ._fbcT--&-- .'s o 2.0 46.,

3oo - 'N \'?

\ \ \-

h \ \ N .=r=- '

/

'5 o 1.0 It 2oo5' s Nu-__ . _ .

+ iooE N. /

o

' N--..h~Tg_.4\h'.]. -

\ ),\ '\\ \\ . .

g, tg-J.A S' O N D J FMAMJJ ASON b',J FMA MJJ A O N D E

- 1975 1976 1977 4

'd

. Figure 1.3.3-3 Periphyton densities (X103 units.cm-2) for locations in Lake Keowee, SC, from July , 1975 through December, 1977.

1.3.4 PHYTOPLANKTON-ZOOPLANKTON RECEIVING WATER STUDY Specification: Bimonthly sampling (6 times /yr.) shall be done at Stations 500, 503, 505, 506, 509.5 (intake structure), 508 (discharge cove), _ and 508.5 (approximately midway between 508 and 504) .

The latter two stations shall be geographically fixed points

, used to examine for cooling water effects.

Both whole water samples and samples concentrated using a plankton net will be collected. The sampling at stations affected by the discharge shall consist of samples taken at

, water depths, both affected and not affected by the plume.

At the control stations, samples will also be taken at these corresponding depths (Duke Power Company 1973a).

I. INTRODUCTION A discussion of the importance of temperature regimes to phytoplankton and zooplankton has been presented (Duke Power Company 1973b).

II. METHODS AND MATERIALS The methods -and materials used in 1977 were previously described (Duke Power Company 1973b,1973c,1974a,1974b,1975a,1975b,1976) except for the following changes:

Phytoplankton Sampling and Data Analyses Phytoplankton were collected monthly at nine reservoir locations in Lake Keowee during 1977. Samples were analyzed for species composition, abundance and pigment concentrations. Non-replicated data 'for three standing crop indices (density, biovolume and chlorophyll) were tested for location dif ferences using a Friedman's analysis of variance by rank (Conover 1971) .

Zooplankton Data Analyses Sampling locations were grouped into reference, intermediate and' discharge areas according to. relative distance from the Oconee Nuclear Station (ONS) discharge structure (Table 1.3.4-5). Reference (Locations 500.0, 501.0,

~

506.0),. intermediate (Locations 502.0,~503.0, 505.0) and discharge-(Locations 508.0, 508.5, 504.0) areas constituted 60,133, and 7% of the lake surface area, respectively. Estimated percentages of lake-surface ~ area for each lake area were determined by tracing the mapped shoreline with 'a planimeter and defining area boundaries to be the midpoint between locations. Previous plume studies (Duke Power Company 1975, 1976). indicate that the' majority.

of the ONS thermal plume was confined to the Keowee River. arm of the lake and

~

was only slightly detected past the Keowee River-Little River connecting canal (Location 503.0).- For that freason, Location 503.0 was included in the intermediate area group, although it is 'about'l km from the discharge structure (Table 1.3.4~5).

Data were arranged into' three lata sets _on the basis of sampling dates. The first! data set consisted of all sampling dates- (January through December,1977) .

~

' 1. 3. 4'-1 _0NS 12/77

The second and third. data sets were the " stratified" (March through Septem-ber) and "destratified" (January, February and October through December) periods. Division of months was based on the stratification of zooplankton as indicated by comparing bottom-to-surface and 10 m-to-surface den-Location 502.0 (Figure i sities lakeside _ of the skimmer wall at 1.3.4-12). Temperature isopleths at Location 502.0 (Figure 1.3.1-2) indicate a vertical thermal gradient greater than 2.5 C' existed from near surface to 20 m (approximate depth of skimmer wall opening at full pond) for the months categorized as stratified on the basis of zooplankton vertical distribution.

For most months categorized as destratified, the vertical temperature gradient was less than 2 C*. One exception was February, when a 3.5 C*

gradient existed from near surface to 20 m and the zooplankton were not 4 stratified-(Figure 1.3.4-12).

Densities of major taxonomic groups (total zooplankton, Copepoda, Cladocera, and Rotifera) estimated from 10-m-to-surface tows were analyzed statistically as follows: 1) Data for all months, stratified months, and destratified months- failed Bartlett's Test, thereby failing to meet the assumption for an analysis of of homogeniety which is required variance procedure; 2) Data were analyzed for location and month effects using Friedman's Test, a non-parametric analysis of variance procedure (Conover 1971); 3) Data groups that yielded significant results (P<0.05) were analyzed graphically since a non-parametric multiple comparison pro-cedure similar to the Student-Newman-Keul's Test was not sensitive enough to detect differences among ranked locations or months; 4) Statistical tests were performed on SAS 1976 (Barr et al.1976). Zooplankton density

- estimates derived from bottom depth-to-surface tows were not analyzed statistically since the bottom depth differed appreciably (18 to 34 m) among locations.

III. RESULTS AND DISCUSSION Light penetration was measured in conjunction with phytoplankton sampling. 1 Both euphotic depths (depth to 1% of surface light penetration) and Secchi~ l disc readings were taken in 1977. The maximum mean euphotic depth (10.2 m) occurred in May, and the shallowest mean depth of 4.9 m was observed in September and October (Table 1.3.4-1) . Secchi readings were greatest from May through July (range of 2.1 to 5.0 m), whereas readings were shallowest during April and September (range of 1.0 to 2.3 m).

Phytoplankton During 1977, 212 algal taxa were observed in Lake Keowee, including 16 new taxa (Table 1.3.4-2). Since 1973, a total. of 432 taxa' have been recorded. -

The phytoplankton community was composed primarily of diatoms (Baci11ariophyceae),

green algae (Chlorophyceae) and dinoflagellates (Dinophyceae)'. Euphotic--

zone composite (EZC) densities were dominated by green algae (Arthrodessus sp. ,

and Cosmarium asphaerosporum var. strigosum) and diatoms (Cyclotella stelligera, Melosira distans var..A, Synedra sp. A, and'Rhizosolenia eriensis) (Figure 1.3.4-1).- Total'biovolume for EZC samples was comprised mostly of. diatoms (Cyclotella stelligera and Rhizosolenia eriensis) and . dinoflagellates (Peridinium spp.), except in August and September when green algae (Arthrodesmus l sp.' and C. asphaerosporum var. strigosum) exhibited greater biovolumes than l l

diatoms (Figure 1.3.4-2).

t 1.3.4 ONS 12/77 4

-. - .r-- e. ,- ,_, e

L h

Generally, density, biovolume and chlorophyll concentrations were similar  !

in EZC and lower-depth samples (LDS) during late fall and winter months (Appendix B, Section 2). As the reservoir stratified, EZC samples had higher standing crops than LDS standing crops. Standing crops of the LDS remained relatively constant through the year. Winter EZC samples showed minor spatial l differences in phytoplankton standing crops (Figures 1.3.4-3) and 1.3.4-4). l During spring and summer, the discharge area (503.0, 508.0, 508.5) hau lower

EZC standing crops than did other locations (Figures 1.3.4-5 through 1.3.4-7).

Intake (509.5) and discharge (508.0) standing crops were similar to LDS crops 1

, at Location 502.0. In fall, EZC standing crops again exhibited minor spatial l variation (Figures 1.3.4-7 and 1.3.4-8). As was previously discussed (Duke Power Company 1977), the EZC phytoplankton concentrations in the discharge area during spring and summer seasons were lower than at other reservoir i areas. This was directly related to the deep-water source of ONS Condenser -1 Cooling Water which contained low phytoplankton standing crops compared to '

surface waters at reference areas.

' L The two arms of the reservoir exhibited slightly different standing crops l and spe'cies composition during 1977 (Figure 1.3.4-9). In August, the Little j River Arm had greater green algal densities and biovolumes than the Keowee River arm; dinoflagellates contributed more to the percent composition of ,

r densities in the Keowee River arm than in the Little River arm. In September  !

] dinoflagellates showed reduced biovolumes and greens dominated densities I t

and biovolumes for both reservoir arma (Appendix B, Section 2). Friedman's analysis of variance (Table 1.3.4-3) detected significant (P50.05) location differences for EZC biovolume as well as for EZC and LDS chlorophyll data.

Location means indicated lowest phytoplankton concentrations occurring in the ONS discharge area but concentrations gradually elevated with distance from the discharge structure. This is attributed to ONS pumping bottom water to the surface (Figure 1.3.4-10). This observation was discussed in the ONS Environmental Summary Report (Duke Power Company 1977).- The significantly higher chlorophyll concentrations in the Location 508.0 LDS (Figure 1.3.4-10)

were due to the rapid mining of discharge and lake surface water in the dis-charge cove.

i Greater EZC standing crops existed during the summer of 1977 than during i previous summers (Duke Power Company 1977). Two small desmids (green algae),

1 Arthrodesmus sp. and Cosmarium asphaerosporum var. strigosum, dominated total densities for August and September 1977 in the Little River arm (Figure 1.3.4-11).

i These taxa were observed during September 1976, but were considered rare before 1976. The greater abundance of these taxa could not be attributed 1- to changes in nutrient concentrations or temperature changes (Appendix B,  ;

Section 2, p. 377). ONS operational changes also could not' account for  !

increased desmid-standing crops, especially since the Little River arm is least affected by the ONS plume (Plume Mapping, Section 1.6). Lake Keovee water chemistry (Water Quality, Section 1.3.1)' favors desmid algae because of the slight acidity. low nitrogen and phosphorus concentrations, and-relatively low divalent to monovalent cation ratios (Kim 1967).

For comparative purposes, EZC phytoplankton data for-1977 were grouped according to lake. area as previously described (Duke Power Company 1977):

-(1) reference area group. included Locations 500.0, 502.0, 505.0, and 506.0; and (2) discharge area group consisted of Locations 503.0, 508.0,'508.5 and

-509.5. The above reservoir groupings exhibited markedly higher yearly mean

-1.3.4-3' ONS 12/77

standing crops in 1977 than during previous years (Table 1.3.4-4) . The

- 1977 ' summer pulse of desmid algae contributed greatly to this yearly increase. - However, -if the September-1977 data had been' excluded from the 1977 means, then 1977 densities and biovolumes would have been approximately 50% lower. These new means would have been similar in magnitude to previous year means for the two areas.

The previously described empirical equations (Duke Power Company 1977) which predicted standing crop reductions from Location-500.0 were used for 1977 phytoplankton data. The predicted reductions for 1977 were' typically greater than observed reductions for 1977 as was presented previously (Duke Power Company 1977). Simple linear regression detected similar spatial trends between observed and predicted percent reductions for only three months in 1977, i.e. August (r2 = 0.55, n = 7), September (r2 = 0.97, n = 7) and ~

October (r2 = 0.74, n = 7). These trends probably were due to the increased desmid biomass observed in the Little River arm.

Zooplankton Forty-seven genera of zooplankton which included sixty-six identified species (10 copepods,19 cladocerans, 37 rotifers), were collected from Lake Keovee in 1977 (Table 1.3.4-6). The copepod Cyclops vernalis, the cladocerans Alona circumfimbriata and Kurzia latissima, and the rotifer Philodina spp. ,

were identified from zooplankton samples for the first time. As in previous years, littoral organisms were occasionally found in the samples butDensities the more common organisms collected'were characteristically limnetic.

of major taxonomic groups and individual taxa are listed for each month and location sampled in Appendix B Section 3.

Numerically Dominant Organisms Although the structure of the zooplankton community varied seasonally there )

were a few taxa from each major taxonomic group that numerically dominated .'

the group. The numerically dominant zooplankton organisms in 1977 were the same as those reported in previous years (Duke Power Company 1977).

The major contributors to copepod densities were the innature naupliar cnd l

copepodid forms which averaged approximately 90% of the~ copepod population during 1977. The remaining 10% of the copepod population were adults.

~

l Tropocyclops prasinus and Diaptomus mississippiensis constituted 'approximately j 99% of the-adult copepods in 1977.

Cladocerans were numerically dominated by Bosmina coregoni and Diaphanosoma leuchtenbergianum. These two Slankters constituted-approximately.90% of the

~

cladoceran community during Si7. Holopedium gibberum and Daphnia _ambigua

. were occasionally abundant.

Rotifer species exhibited marked differences in temporal'and spatial distribution which made it difficult to: select only a few numerically dominant taxa. l Various combinations (usually.-2 or 3) of the following taxa represented major. portions of the rotifer- community-during 1977: -- Keratella spp. (including K. americana, K_. cochlearis, K_.

crassa, and K. earlinae); Polyarthra spp. '

(

(including P, dolichoptera and P_. vulgaris); Collotheca spp. (including Conochilus unicornis;

' C. balatonica, C_. discophora, C. libera, and C. mutabilis_); i l

l'. 3. 4-4 ' 'ONS 12/77

and Ptygura spp.. (including P. libera and an unidentified species) . Other rotifers that were occasionally prevalent included Ploesoma truncatum and 4 'Synchaeta pectinata.

, Seasonal Analysis The seasonal abundance of zooplankton in Lake Keowee was estimated by computing 1 a grand mean of reference, intermediate and discharge area densities. These estimates are biased towards discharge and intermediate areas since they comprised smaller surf ace areas of the lake (7 and 33%, respectively) than the reference area (60%).

The abundance of zooplankton during 1977 was generally higher during the spring and-summer (15 to 39/4) than during the fall and winter (6 to 23/4) .

as indicated in Figure 1.3.4-13. Friedman's Test results indicate there were

significant differences in the density of zooplankton among months during l 1977 (Table 1.3.4-7). Densities were similar among spring and summer (stratified) months' . Likewise, densities were similar among fall and winter months (de-stratified). Total zooplankton densities for 1977 pulsed in May (33/4) i and September (39/l). Copepods were the major contributors to zooplankton density in May (48%) while rotifers were dominant in September (50%) . In general, copepods and cladocerans were co-dominant in the lake during the first half of 1977 (56 to 80%) while rotifers were dominant the latter half of the year (50 to 60%).

The lake abundance of zooplankton in 1977 was lower than in previous years,

! particularly during the spring and summer (stratified) seasons (Figure

1. 3. 4-13) . Zooplankton density during the stratified seasons of 1974 through 1977 averaged 60, 54, 49, and 27/t, respectively._ Densities for the destratified seasons of 1974 through 1977 were 18,12,18, and 12/4, respectively. Averaged annual densities of zooplankton in the lake were.36, 30, 30, and 21/l, respectively, 'for.1974 through 1977. A gradual decrease in copepod, cladocerans,

+

and rotifer abundance was noted during stratified seasons over the years.

A number of factors which include lake _sging, predation pressure by the introduction of threadfin shad, meteorological variations, and the operation of ONS could have accounted for the trend of gradual decreasing abundance of zooplankton in the lake from 1974 to 1977.

Spatial Analysis i

The seasonal distribution patterns of zooplankton for locations in the Little i River arm of the lake differed from those'in the Keowee River arm _(Figure

!- 1.3.4-12) . A bimodal distribution curve.with density pulses ' occurring in the spring (May)-and fall (September) was noted at Locations 500.0 and 502.0 which are in the Little River arm. Copepods and cladocerans were the major contributors to the density pulse in May while rocifers were .the major -

contributors to the September density pulse. . Densities of zooplankton ranged from 10 to 59/L and 6 to 38/L at Locations 500.0 and 502.0, respectively.

A general trend of increased density from vinter to fall was noted at ~

+

Locations 506.0 and 505.0 which are in the Keovee River arm of the lake.-

L Rotifer densities-peaked in September at Location 506.0 whereas copepod and ,

cladoceran densities peaked in September at Location 505.0. - Densities of

zooplankton ranged from 9 to 89/L and 5 to 47/4, respectively,~at Locations _

506.0 and 505.0.-

1.3.4-5_ IONS 12/77' 1

,, . -, . - - . . . - - - . . . . , . - - ~ . - + . .

Zooplankton densities were generally higher in the Keowee River arm of the lake than in the Little River arm. A noticeable spring pulse in zoo-plankton density did not occur in the Keowee River arm as it did in the Little River arm. Rotifers constituted a greater portion of the zooplankton population in the Keowee River arm than in the Little River arm during the winter and early spring months of 1977.

The seasonal abundance of zooplankton at Location 508.5, which is in the Keowee River arm of the lake, was low (<23/4) throughout 1977 compared to other locations in the Keowee River arm as well as locations in the Little River arm (Figure 1.3.4-12) . Cladocerans constituted a greater percentage of the zooplankton population at Location 508.5 during the winter and early spring months compared to locations previously discussed. '

Spatial trends in zooplankton data observed for stratified and destratified periods of 1977 were similar to those previously reported for stratified and destratified periods of 1974 to 1976 (Figure 1.3.4-14) . Densities of zooplankton in the discharge area of the lake have remained about the same over the years while densities in the intermediate and reference areas have steadily decreased.

Densities of zooplankton (particularly copepods and rotifers) were lower in the discharge and intermediate areas of the lake than densities in the reference area during the stratified period of 1977 (Figure 1.3.4-15).

The density of rotifers was higher at Location 506.0 (Keowee River arm reference) than at Locations 500.0 and 501.0 (Little River arm reference).

The density of copepods was higher at Location 500.0 and 501.0 than at Location 506.0. Densities of cladocerans were lower in the discharge area than in the intermcdiate and reference areas. Intermediate and reference area densities of cladocerans were similar. Statistical analyses revealed significant differences in density among locations for each major taxonomic group of zooplankton (Total zooplankton, Copepoda, Cladocera, and Rotifera) for the stratified period of 1977 (Table 1.3.4-7) .

During the destratified period of< l977 densities of zooplankton (copepods and rotifers) were lower in the discharge and intermediate areas of the lake than in the reference area (Figure 1.3.4-15). Densities of copepods and rocifers in discharge and intermediate areas were similar during the destratified period. Statistical analyses revealed significant differences in density among locations for total zooplankton, copepods and rotifers, but not cladocerans, for the destratified period of 1977 (Table 1.3.4-7) .

The density of zooplankton in the intake canal was 28% of the density lake-side of the skimmer wall during the stratified period of 1977 (Figure 1.3.4-16).

l During the destratified period densities in the intake canal were about 80% of those lakeside of the skimmer wall. Densities of zooplankton in the intake canal and in' the discharge cove in 1977 were stallar which indicate densities in the discharge cove were governed by densities in the intake canal. Similar trends have been reported for previous- years (Duke Power Company 1977).

Effects of ONS Operation As in previous years, the major detectable effect of ONS operation on i

i 1.3.4-6 ONS 12/77 l

L

M zooplankton in the receiving water _in 1977 was lower total densities of zooplankton in the discharge (?% of lake surface area) and intermediate

(33% of lake surface area) areas of the lake. Zooplankton densities were 59 and 38% lower in the discharge and intermediate areas, respectively, 4

than densities ;in the reference area during the stratified period (Figure 1.3.4-14). During the destratified period, densities were 52 and '48% lower in the discharge and intermediate areas, respectively, than densities in the reference area. Discharge area densities remained similar from year to

, year but reference and intermediate densities have gradually decreased from

1975 through M77.

As reported previously (Duke Power Company 1977), differences in the densities of zooplankton among reference, intermediate, and discharge areas was the

, result of a combination of intake skimmer wall effects and condenser cooling .

water (CCW) flow, particularly during the stratified period. During the

stratified period, substantial numbers of zooplankton were prevented from i

entering the intake canal due to bottom water withdrawal for cooling by

+

ONS. Intake water with a low density of zooplankton was passed through the CCW System and discharged into the receiving water. Oconee Nuclear Station CCW flow during the stratified period of 1977 (monthly averages of 4,385 to 6.964 m3 / min) were sufficient to substantially dilute zooplankton populations in the discharge and intermediate areas. The CCW flow for the stratified 1977 period was comparable to CCW flow for 1975 and 1976 stratified periods.

The dilution effect diminished with distance from the discharge structure (Figure 1.3.4-14).

During the destratified period of 1977 CCW flow (monthly averages of 4,698

to 6,755 m3 / min) was sufficiently high to dilute populations in the discharge area had there been appreciable intake skimer wall exclusion of zooplankton.

However, little skimmer wall exclusion was indicated during the destratified

! period (Figure 1.3.4-16) . Densities of zooplankton in the reference area l were higher than densities in the rest of the lake. Densities were similar for discharge and intermediate areas. Nutrient concentrations (nitrate-4 nitrite, ammonia) were higher at reference Locations 500.0 and 501.0 than i

at other. locations (Water Quality 1.3.1), which could have created a greater i availability of food (phytoplankton blooms) for zooplankton, and thus could have resulted in higher densities of zooplankton in the Keowee River ' ara reference area during the destratified period. However, phytoplankton data indicate similar densities throughout the lake during the destratified period l of 1977. Zooplankton densities at reference Location 506.0 could have been high because of influence from the operation of the Jocassee Pumped Storage facility. - Zooplankton densities in Lake Jocassee have been reported to be appreciably higher than those in Lake Keowee (Duke Power Company 1977, SERI Addendum A-6). Also, Location 506.0_ is more protected from weather dis-turbances. ' Another explanation 'of higher densities of zooplankton in the reference areas than in the remainder of the lake could be that of predation

{ pressure by fish (particularly.threadfin shad) since they tend to overwinter 4

in heated waters (U.S. Atomic Energy Commission 1972, Industrial Bio-test 1974).

3 Due to rapid mixing of the heated affluent in the discharge cove, the water temperature (mean from bottom depth to surface) measured in the discharge '

cove ~(Location 508.0) did not exceed the thermal tolerance level of -30 C

described in ~ the literature for'a viable zooplankton population (Bunting 1974,

}f Goss and Bunting 1976). The =awi== discharge cove temperature occurred in E

e 1.3.4-7 ONS 12/77.

~ - - . - _ _.~m.

in July at 27.9 C (Water Quality 1.3.1). Surface water temperatures recorded in the reference area were similar or slightly higher (0.5 te 1.5 C') than discharge cove temperatures during the summer and early fall months when discharge cove remperatures were highest. The minimum dissolved oxygen

[. concentration (mean of bottom depth to surface recorded at Location 508.0) occurred in September at 4.3 mg/4. This concentration was not surficiently low to be lethal to the zooplankton (Bogatova 1973, Kring et al.1976, Mangum et al. 1973, Sprague 1963).

IV

SUMMARY

AND CONCLUSIONS Phytoplankton (1) The phytoplankton of Lake Keowee were sampled monthly during 1977_

to assess the impact of cooling water use by ONS on their distribution

' and abundance. Phytoplankton conar.inities were dominated by diatoms, green algae and dinoflagellates, as in previous years. Green algae j were more abundant in the Little River arm-during summer 1977 than l

1976. This was reflected in the overall higher standing crops during summer 1977 than previous years.

(2) Euph' tic-zone phytoplankton were more abundant during months of thermal stratification than under isothermal conditions, with greatest concentrations occurring in August and September. The greater the vertical differences in phytoplankton concentrations lakeside of the skimmer wall, the greater the differences between standing crops in the euphotic-zone of discharge and reference areas. The lower standing crops in the discharge area occurred primarily in spring and summer months. Thus, the exclusion of upper strata phytoplankton from the ONS intake via a skhr wall affected the phytoplankton abundance and distribution more than did ONS heat inputs to the reservoir.

Zooplankton Data collected in 1977 revealed the same general trends in the zooplankton I

as those reported previously (Duke Power Company 1977).

(1) The zooplankton community was numerically dominated by immature copepods and rotifers. Cladocerans and adult copepods were relatively scarce.

The same taxa as previously reported were numerically dominant in 1977.

Copepods were generally more abundant in the Little River arm of the

! lake while rotifers were more abundant in the Keowee River arm.

i (2)- The density of zooplankton in the lake in 1977 was. lower than densities reported in previous years. Lake aging, predation pressure by the iatroduction of threadfin shad, meteorological variations, and/or -

the operation of 'ONS could have contributed to this trend. -

i (3) The density of zooplankton was lower in the discharge and intermediate j areas (40% of. lake surface area) than in the reference area during l

1977. Densities in the intake and discharge area were similar to those reported in previous years while densities in the intermediate and reference area were lower:than those previously reported.-

1.3.4-8 -ONS 12/77-I- , . _ _. .

I l

l l

l (4) The low densities of zooplankton in the discharge and intermediate areas during the stratified period of 1977 was the result of dilution due to ONS's . intake of bottom water for cooling. Oconee CCW flow and skimmer wall exclusion of zooplankton contributed to the diluting affect. Similar spatial trends were noted for stratified periods of 3975 and 1976 under similar plant operating conditions.

1 (5) Densities of zooplankton were lower in discharge and intermediate areas I than in the reference area during the destratified period of 1977. I Densities in the discharge and intermediate areas were similar. This trend could not be completely explained by dilution or predation by fish in the discharge and intermediate areas nor by greater availability of food in the reference areas.

(6) Discharge cove temperatures and dissolved oxygen concentrations in the discharge cove were not responsible for the low densities of zooplankton in the discharge and intermediate areas during 1977.

I 1.3.4-9 ONS 12/77-

REFERENCES CITED 1976. A users guide Barr, A. J., J. H. Goodnight, J. P. Sall, J. T. Helwig.

Sparks Press, Raleigh, NC. 329 pp.

to SAS 76.

Bogatova, I. B. 1973. Lethal ranges of 02 content, temperatures, and pH

.for some representatives of the family Chydoridae. (In Russian). Zool.

Zh. 41:58-62.

Bunting, D. L. 1974. Zooplankton: thermal regulation and stress. Proc.

Limnetics, Milwaukee, WI.

Symp. Energy Production and Thermal Effects.

Sep. 1973. pp. 50-55.

Conover, W. J. 1971. Practical nonparametric statistics. John Wiley and Sons, .

Inc., NY. 462 pp.

Duke Power Company. 1973a. Appendix B to facility operating license nos.

DPR-38, DPR-47, and DPR-55, technical specifications for the Oconee Nuclear Station units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Commission, docket nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, DC. 18 pp.

1973b. Oconee Nuclear Station. Semi-Annual Report. Period ending June 30, 1973. Charlotte, NC.

1973c. Oconee Nuclear Station. Semi-Annual Report. Period ending December 31, 1973. Charlotte, NC.

1974a. Oconee Nuclear Station. Semi-Annual Report. Period ending June 30, 1974. Charlotte, NC.

1974b. Oconee Nuclear Station. Semi-Annual Report. Period ending December 31, 1974. Charlotte, NC.

1975a. Oconee Nuclear Station. Semi-Annual Report. Period ending June 30, 1975. Charlotte, NC.

1975b. Oconee Nuclear Station. Semi-Annual Report. Period ending December 31, 1975. Charlotte, NC.

1976. Oconee Nuclear Station. Annual Report. Period ending December 31,-1976. Charlotte, NC.

1977. Oconee Nuclear Station. Environmental summary report, 1971-1976. Volume 1. Charlotte, NC.

Goss, L. B. and D. L. Bunting. 1976. Thermal tolerance of zooplankton. Water Res. 10:387-398.

Industrial Bio-Test Laboratories, Inc. 1974. A baseline / predictive environmental investigation of Lake Wylie.- Catawba Nuclear Station and Plant Allen.

356 pp.

Report to Duke Power Company.

PhD.

Kim, Y . C . 1967. The Desmidiaceae and Mesotaeniaceae in North Carolina.

Thesis. N. C. State University, Raleigh. 126 pp.

1.3.4-10 ONS'12/77

Kring, R. L. and W. J. O'Brien. 1976. Effect of varying oxfgen concentrations .

on the filtering rate of Daphnia pulex. Ecology. 37(4):808-814.

Mangum, C. and W. V. Winkle. 1973. Responses of aquatic invertebratce ca declining oxygen coniitions.- Am. Zool. 13:529-541.

Sprague, J. B. 1962. Resistance of four freshwater crustaceans to lethal high temperature and low oxygen. J. Fish. Res. Board Can. 20(2):387-415.

U. S. Atomic Energy Commission, Division of Radiological and Environmental Protection. 1972. Final environmental statement related to operation of Oconee. Nuclear Station Units 1, 2 and 3. Duke Power Company. Docket Nos. 50-269, 50-270, 50-287. 170 pp.

1 l

i l

l

1.3.4-11_ ONS 12/77

Table 1.3.4-1 Page 1 of 2 Summary of cuphotic (EZ), lower sample (LS) and Secchi disc (SD) depths (m) for Lake Keowee phytoplankton collections, 1977.

2 Feb 15 Mar 15 Apr 13 May 10 Jun 15 Location Jan 11 EZ LS SD EZ LS SD EZ LS SD EZ LS SD EZ LS SD EZ LS SD 6.0 23 1.9 8.0 20 2.0 5.0 25 1.6 10 25 3.1 6.5 25 2.9 500.0 7.0 20 2.3 7.0 30 2.0 7.5 30 2.2 6.0 30 2.3 12 30 3.8 9.5 30 5.0 501.0 6.5 30 2.2 7.0 25 2.2 7.0 25 1.9 4.0 25 1.3 9.0 25 3.1 8.0 25 3.7 502.0- 7.5 25 2.4 7.0 25 2.2 8.0 25 2.0 4.5 25 1.5 9.5 15 2.8 7.0 25 3.0 503.0 6.5 20 2.1 7.0 30 2.2 7.5 30 2.0 6.0 30 1.5 10.5 30 2.9 8.0 30 4.0 505.0 6.0 30 2.0 7.0 '30 2.2 7.0 30 1.6 6.0 30 1.6 12 30 3.2 9.0 30 3.7 b 506.0 6.5 30 2.2 b 2.1 7.5 8 2.0 5.0 10 1.3 9.0 11 2.4 6.0 11 3.0 508.0 6.0 10 2.0 7.0 9 7.0 22 2.2 7.5 25 2.1 5.5 20 1.5 10 25 2.8 7.0 25 3.4 508.5 6.0 20 2.0 1

1.0 10 2: .2 1.0 10 2.4 1.0 10 1.4 1.0 10 2.9 1.0 10 2.5 509.5 1.0 10 2.3 2.2 6.9 2.1 7.5 2.0 5.2 1.6 10.2 3.0 7.6 3.5 Month Mean 6.5 1 A 1-m sample was collected instead of measuring the euphotic zone and creating a composite.

c) 2 A Montedoro-Whitney Solar Illuminance Meter Model LMD-8A was used to measure the euphotic zone;

$ a Kahlsico Model 268WA310 Submarine Photometer was used on all other dates.

3 The Submarine Photometer developed a malfenction on this date; thus, an average cuphotic zone was used based on k;

23 Section 1.3.1 data.

u a

Table 1.3.4-1 (Cont) Page 2 of 2 3

Location Jul 12 Aug 9 Sep 12 Oct 13 _ Nov 17 Dec 14 Year Mean E ME E M S.D E Mg E MM E MM E MM E E 500.0 6.0 22 2.1 6.5 22 1.5 5.5 25 1.4 5.0 25 2.4 5.0 25 2.1 5.0 25 2.0 501.0 7.5 30 3.2 8.5 30 1.4 8.0 30 2.0 5.0 30 2.5 5.0 30 2.3 5.0 30 2.1 502.0 6.0 25 2.7 7.0 25 2.1 7.0 25 2.2 5.0 25 2.3 5.0 25 2.1 5.0 25 1.8 503.0 6.0 25 2.7 7.0 25 1.2 3.0 25 1.1 4.5 25 1.9 5.0 25 1.8 5.0 25 1.8 505.0 7.0 30 2.3 7.0 30 2.3 4.0 30 2.2 5.0 30 2.1 5.0 30 1.8 5.0 30 1.7 506.0 6.0 30 2.4 8.0 30 2.5 6.0 30 2.3 5.0 30 2.6 5.0 30 2.3 5.0 30 1.9 P' 508.0 8.0 10 2.7 7.5 10 2.6 3.0 10 1.2 4.5 10 2.0 5.0 10 1.9 5.0 9.0 2.2 T

C 508.5 6.5 20 2.3 7.5 20 1.8 2.5 25 1.0 5.0 25 2.1 5.0 25 1.9 5.0 23 1.8 1 1.0 10 2.2 1.0 10 2.4 509.5 1.0 10 3.4 1.0 10 3.1 1.0 10 1.0 1.0 10 2.1 Month Mean 6.6 2.6 7.4 2.1 4.9 1.6 4.9 2.2 5.0 2.0 5.0 2.0 6.5 2.2 O

m

~

i :3,

~ ,

e

Table 1.3.4-2 Page 1 of 9 Phytoplankton Species Checklist for Lake Keowee through December, 1977 Division: Chlorophyta Class: Chlorophyceae

• Ankistrodesmus falcatus (Corda) Ralfs

• A. falcatus var. acicularis (Braun) G. W. West

• E lalcatus var. mirabilis (West & West) G. W. West jj[Ifusiformis Corda sensu Korsch 2d.spp.

• Arthrodesmus incus (Breb.) Hass. ,

• A. incus var. extensus Anderson

• E subulatus Kutz.

• L spp. ,

• Asterococcus limneticus G. M. Smitn

!b.spp.

Bambusina brebissonii var. gracilescens Wolle.

Binuclearia eriensis Wittrock

• • Botryococcus braunii Kutz.

• B. sudeticus Lemm.

Carteria klebsii (Dang.) Dill Sh,spp.

Cerasterias staurastroides West & West Chlamydomonas mucicola Schmidle

• C n spp.

Chlorella ellipsoidea Gerneck.

C. homosphaera Skuja

_C. vulgaris Beyer.

• C.t spp.

Closteriopsis longissima Lemm.

C. longissima var. tropica West & West

• Closterium ceratium Perty Cb, gracile Breb.

• C incurvum Breb.

Cb,pusillum Hantz.

C. venus var, incurvum (Breb.) Krieg.

• C. spp.

• Coccomonas spp.

• Coelastrum cambricum Archer

• C. microporum Naeg.

_IEIreticulatum (Dang.) Senn.

Cb,sphaericum Naeg.

Sh_spp.

Cosmarium abbreviatum Raciborski C. abbreviatum var. minor West & West C. asphaerosporum Nordst.

• C7 asphaerosporum var. strigosum Nordst.

f i

-Cb,botrytis Meneg.

C. cosmetum West & West I

• Observed during 1977

• • Observed for the first time during 1977

~

l -

1.3.4-14 ONS 12/77

1. 8* '

Table 1.3.4-2" (Cont)

• • E ornatum. var. perornatum Croasdale

• C. phaseolus var. minor Boldt.

E portianum Archer E suberenatum Hantz.

• C. tenue Archer

• E tinctum Ralfs

• C. spp.

Cosmocladium saxonicum DeBary E spp.

• Crucigenia apiculata (Lema.) Schmidle

• C_., fenestrata Schmidle

,C. irregularis Wille

• E quadrate Morren -

• C. tetrapedia (Kirch.) West & West C:,spp.

• • Dactylococcus infusionum Naeg.

Desmatractum indutum (Geitler) Pascher

• Dictyosphaerium ehrenbergianum Naeg.

• D. pulchellum Wood D_:, s p p .

Dysmorphococcus variabilis Takeda D_:,spp.

• Elakatothrix gelatinosa Wille E,:, s p p .

Euastrum spp.

Eudorina spp.

• Franceia droescheri (Lema.) G. M. Smith

• Gloeocystis gigas (Kutz.) Lag.

• G. planctonica (West & West) Lema.

• G. vesiculosa Naeg.

G_:. spp.

Golenkinia paucispina West & West

• G. radiata Chod.

Gonatozygon aculcatum Hast.

G. monotaenium DeBary

• Gyromitus cordiformis Skuja Haematococcus lacustris (Girod.) Rostaf.

Kirchneriella contorta (Schmidle) Bohlin E elongata G. M. Smith

• h lunaris (Kirch.) Moebius K. lunaris var. dianae Bohlin

• • {-obesa (W. West) Schmidle

• K:.spp.

• Lagerheimia_ spp.

Micractinium pusillum Free.

M_.spp.

. *Monoraphidium braunii Naeg.

• Mg contortum Thur.

E irregulare, G. M. Smith

• M. pusillum Printz

• M. saxatile : Kom.-Legn.

• E-setiforme (Nyg.). Kom-Legn.

M.,:, spp .

1.3.4-15 ONS 12/77:

i E'

Table 1.3.4-2 (Cont)

Mougeotia elegantula Wittrock

• Ib.spp.

Nannochloris spp.

• Nephrocytium agardhianum Naeg.

"N. limneticum (G. M. Smith) G. M. Smith

• 0ccystis borgei Snow

0. elliptica W. West

• (([lacustris Chod.

• 0. parva- West & West

• 0_. pusilla Hansgirg

• jD . submarina Lag.

• 0. spp.

• Pediastrum duplex Meyen .

P. duplex var. gracilimum West & West

• { tetras (Ehr.)

tetras var, Ralfs(Corda) Rabenhorst tetraodon

• P__.

_Penium spp.

Planktpnema lauterbornii Schmidle

• Planktosphaeria gelatinosa G. M. Smith

• Quadrigula closterioides (Bohlin) Printz

• g. lacustris _(Chod.) G. M. Smith ,

9e.spp.

Rhizoclonium spp.

• Scenedesmus abundans (Kirch.) Chod.

S. abundans var. brevicauda. G. M. Smith 5((abundansvar.longicauda G. M. Smith

• S. acuminatus (Lag.) Chod.

i((armatus (Chod.) G. M. Smith S. armatus var. bicaudatus (Gug.-Printz) Chod.

55'bernardii G. M. Smith

• 55'bijuga (Turp.) Lag.

• 5I' Eras 111ensis Bohlin

• • 55'carinatus (Lemm.) Chod.

• 5~ denticulatus Lag.

iiT'denticulatus var. linearis Hanagirg

• S~ dimorphus (Turp.) Kutz.

5~ ecornis (Ralfs.) Chod.

t S. granulatus West & West S. opoliensis var. contracta Prescott

• 5[quadricauda (Turp.) Breb.

• • S. quadricauda var. alternans G. M. Smith

• S. quadricauda var. longispina (Chod.) G. M. Smith

! *S. spp.

! Schizochlamys spp.

t

• Schroederia setigera (Schroeder) Lemm.

j

• Selenastrum gracile. Reinsch

• S. minutum - (Naeg.) Collins

• 57 westii G. M. Smith

• 5phaerocystis schroeteri Chod.

• Sphaerozosma granulatum Roy & Biss.

Staurastrum arctiscon (Ehr.) Lundell i *S. curvatum W. West

• 5~ curvatum var. elongatum G. M. Smith '

1.3.4-16 ONS 12/77

1 Pags 4 of g Table 1.3.4-2 (Cont)

• S 2 cuspidatum Breb.

E ct spidatum var. divergens Nordst.

E dejectum Breb.

E limneticum var. cornutum G. M. Smith

_S2 megacanthum Lundell S. ophiura var. cambricum (Lund.) West & West

• S. paradoxum var. parvum W. West

• • E paradoxum var. A

• [ pentacerum (Wolle) G. M. Smith S. quadricuspidatum Turner

• • E suberuciatum Cooke & Wille

• E tetracerum Ralfs.

S. spp. -

• • Itigeoclonium spp.

• Tetraedron caudatum (Corda) Hansgirg.

• T. minimum Braun '

l

• 2~T muticum (Braun) Hansgirg

• T. regulare var. incus Telling _ {

• [ spp. '

l Tetraspora lamellosa Prescott l Tetrastrum glabrum (Roll) Ahlstrom & Tiffany I

• T. heteracanthum (Nordst.) Chod.

Treubaria setigerum (Archer) G. M. Smith l Xanthidium cristatum var. uncinatum f. mucronata W. West Division: Chrysophyta Class: Bacillariophyceae Achnanthes inflata (Kutz.) Grun.

• h microcephala (Kutz.) Cleve j

• A. minutissima Kutz.

• [ spp. -

• Asterionella formosa Hass. *

• Attheya zachariasi Brun.

Cocconeis spp.

Cyclotella kutzingiana Thwaites

& meneghiniana Kutz.

C. michiganiana Skvortzow

• [ stelligera (Cleve) Van Heurck

• C2 spp.

• Cymbella affinis Kutz.

E naviculiformis Auerswald

• E turgida Greg.

C,:, app .

Denticula thermalis Kutz.

Diploneis spp.

• Eunctia flexuosa (Breb.) Kutz.

E. naegelii Migula

• E. zasuminensis (Cab.) Koerner

• E. sp. &

• E2 spp.

i Fragilaria crotonensis Kitt.

• F_:, a pp .

l Frustulia spp.

Gomphonema constrictum Ehr.

1.3.4-17 ONS 12/77.

Pagn 5 of 9 l Tablo 1.3.4-2 (Cont)

_C. parvulum (Kutz.) Kutz, h spp.

Gyrosigma spp.

Hannaea arcus (Ehr.) Patr.

• Melosira distans var. alpigena Grun.

• M. distans var. A.

M granulata (Ehr.) Ralfs

• M2 italica (Ehr.) Kutz.

• M. italica var. tenuissima (Grun.) Mull.

• Iiavicula cryptocephala Kutz.

• N. exigua Greg. Ex Grun.

E gysingensis Foged.

W. notha Wallace IN. pupula Kutz N. pupula var. elliptica Hust.

N. pupula var. mutata (Krasske) Hust.

• N. subtilissima Cleve N. viridula var. linearis Hust.

. *N2 spp.

Neidium spp.

• Nitzschia acicularis_ (Kutz.) W. Smith

• N. angustata (W. Smith) Grun.

E dissipata (Kutz.) Grun.

E filiformis (W. Smith) Schutt

• E gracilis Hantzsch N. kutzingiana Hilse E linearis (Agardh) W. Smith

• E lorenziana var. subtilis Grun.

• N2 palea (Kutz.) W. Smith

• N sublinearis Hust.

• N,:, s p p .

Pinnularia braunii var. amphicephala (A. Mayer) Hust.

P. biceps Greg.

E_ crucifera Cleve-Euler P. gibba Ehr.

E mesolepta (Ehr.) W. Smith E

_ mesolepta var. angusta Cleve

• P2 spp. '

• Rhizosolenia eriensis H. L. Smith R. longiseta -Zach.

Rhoicosphenia curvata (Kutz.) Grun.

Stauroneis phoenicentaron (Nitz.) Ehr.

.S.2 spp.

Stenopterobia intermedia (Lewis) Breb.

Surirella linearis W. Smith S.2 spp.

'Synedra a_cus, c Kutz.

• S . nana Meister.

• E radians Kutz.

• E rumpens- Kutz.

1.3.4-18 ONS 12/77

Page 6 of 9 Table 1.3.4-2 (Cont)

S. rumpens var. scotica Grun.

• • ~S. tenera W. Smith

• S. ulna (Nitz.) Ehr.

• jS_ sp. fu,

• S. L spp.

• Tabel? aria fenestrata (Lyngb.) Kucz.

• T. flocculosa (Roth) Kutz.

Tj,spp.

Terpsinoe americana (Bail.) Ralfs Class: Chrysophyceae Chromulina stellata Pascher

• C t spp. '

• Chrysococcus spp.

• Chrysosphaerella longispina Laut.

,* Dinobryon bavaricum Imhof J D;. campanulostipitatum Ahlstrom 1

• D. cylindricum Imhof

• D. divergens Imhof D. pediforme (Lemm.) Stein.

• D.,sertularia Ehr.

• D spp.

Epipyxis spp.

Erkenia subaequiciliata Skuja

• Kephyrion spp.

Lagynion spp.

• Mallomonas acaroides Perty l

• M. allantoides Harris )

j((alpina Pascher and Ruttner 1

• M. caudata Conrad

• (([elongatavar. americana Bourrelly

• • M. globosa Schill.

• M. majorensis Skuja 16,producta Iwanoff

• p6,pseudocoronata Prescott

• M. tonsurata Te111ng

• Ib.spp.

Ochromonas chromata H. Meyer 0., variabilis H. Meyer

• 0; spp.

Pheaster spp.

Pseudokephyrion latum (Schill.) Schmidle P. schilleri Conrad

• !5.spp.

Pteridomonas pulex Penard Synura adamati G. M. Smith

• jb, spinosa Korsch.

Sj,uvella Ehr.

• S2 . spp.

Class: Haptophyceae

• Chrysochromulina parva Lackey Class: Xanthophyceae Ophiocytium capitatum var. longispinum (Moebius) Lemm.

1.3.4-19 ONS 12/77

Pigs 7 of 9 Table 1.3.4-2 (Cont)

Division: Cryptophyta Class: Cryptophyceae

- *Chroomonas acuta Utermohl C. caudata Geit.

MEI coerula_ (Celt.) Skuja

• C7norstedtii Hansgirg

[_C7 reflexa Kiss.

Sb.spp.

• Cryptomonas erosa_ Ehr.

• • C. erosa var. reflexa Hursson C. marsonii Skuja

• C7.obovata Skuja i

• C. ovata Ehr.

• C. phaseolus Skuja

• C_.

reflexa Skuja -

fh.spp.

• Cyanomonas spp.

Division: Cyanophyta Class: Myxophyceae

• Agmenellum quadriduplicatum (Menegh.) Breb.

Ag ,thermale (Kutz.) Drouet and Daily Anabaena catenula (Kutz.) Bornet and Flahault A. gvlindrica Lemm.

7. levanderi Lemm.

• [ scheremetievi Elenkin

• A n spp.

• Anacystis cyanea Drouet and Daily -

A. firma (Kutz.) Drouet and Daily

• A7 incerta Drouet & Daily

• II montana Drouet & Daily

• A_ n spp.

Coccochloris stagnina (Sprengel)

Sb.spp.

Coelosphaerium kutzingianum Naeg.

C_. naegelianum Unger Cylindrospermum spp.

Dactylococcopsis acicularis Lemm.

D. rhaphidioides Hansgirg j((smithii Chod. & Chod.

Ib,spp.

Comphosphaeria lacustris Chod.

i G. spp.

Lyngbya contorta Lemm.

l l 0. acuminata Gomont I 'Oscillatoria acutissima Kuff

0. agardhii Gomont O. amphibia Agardh l

! 0. angusta Koppe 02 angustissima West & West

• 0. geminata Menegh.

Ob, limn-:tica Lema.

O. tenu's Agardh Sb. spp..

1.3.4-20 ONS 12/77

Pagn 8 of 9 Table 1.3.4-2 (Cont)

• Phormidium angustissimum West & West Ih.8PP.

Radiocystis geminata Skuja Division: Euglenophyta Class: Euglenophyceae Euglena gracilis Klebs Eb, proxima Dang. I

• E.,spp.

Lepocinclis spp.

Trachelomonas abrupta (Swir.) Defl.

)),acanthostoma (Stokes) Defl.

E dubia (Swir.) Defl. -

]b, intermedia Usng.

L mammillosa Prescott

)), eulchella Drez.

Ji pulcherrima Playfair l

)),superba (Swir.) Defl.  ;

ji volvocina Ehr.

)),volvocina var. punctata Playfair

• 3h.8PP.

Division: Pyrrhophyta Class: Dinophyceae .

Ceratium hirundinella (Mull.) Duj.

• Glenodinium armatum Levander

$b, gymnodinium Penard j gb,palustre,(Lemm.) Schiller  ;

fy,pulvisculus (Ehr.) Stein 06,quadridens (Stein) Schiller ,

• $b.spp. I Gymnodinium spp. l Hemidinium nasutum Stein lb.spp.

• Peridinium aciculiferum (Lema.) Stein l Pj, africanum Lemm.

• Pj,cinctum Ehr.

• P;._ deflandrei Lefevre Fj,gatunense Nygaard

• P. inconspicuum Lemm.

• • ))[keyense Nygaard -

'

• P. pusillum (Pen.) Lemm.

• P. wisconsinense Eddy-

• lh.spp.

Division: Chloromonadophyta Class: .Chloromonadophyceae Gonyostomum depressum (Laut.) Lems.

• Gi latum Iwanoff Unknown Species

• 0374-2

• 0574-2-02

= 0574-2-03 '

• 0574-2-04 0774-2-07 1.3.4-21 ONS-12/77' Lu

8' '

Table 1.3.4-2 (Cont)

• 0774-2-15 0774-2-16 0774-2-17

• 0774-2-22

• 0774-2-24

• 0774-2-28.

• 0774-2-32

• 0774-2-34

• 0974-2-07

• 0974-2-24

• 1074-2-02

• 1074-2-04 -

1174-2-01 0175-2-01 0275-2-03 0675-2-01 0675-2-02 0675-2-05 .

0775-2-02 0775-2-03 0875-2-03 0975-2-01

• 1175-2-04 0176-2-01 0176-2-02 0776-2-02 0776-2-03 0776-2-04

• 0976-2-01

• 0976-2-02

• 0976-2-03 0976-2-04

• • 0477-2-01

• • 1277-2-01

• Observed during 1977

• • Observed for the first' time during.1977

1. 3.'4 ONS 12/77

Table 1.3.4-3 Results of Friedman's analysis of variance for phytoplankton indices,

Lake Keowee, 1977.

Data Type Treatment Friadman's Statistic by Index Source Density Biovolume Chlorophyll Euphotic Zone Location 13.7 18.9* 35.3*

Composite (df = 8) (df = 8) (df = 8)

Euphotic Zone Time 75.8* 60.9* 42.1*

Composite (Months) (df = 11) (df = 11) (df = 11) l l

1 Lower Depth Location 13.4 12.8 32.0*

Sample (df = 7) (df = 7) (df = 7)

Lower Depth Time 67.6* 70.3* 48.0*

Sample (Months) (df = 11) I (df = 11) (df = 11) 1 Compare with Chi-square distribution table using designated degrees of freedom.

• significant at the p<0.05 level.

1 f

1 i 1.3.4-23 -ONS 12/77-

Table 1.3.4-4 Summary of phytoplankton standing crop indices for Lake Keovee, SC, .

1974-1977.  ;

Meanl 95% Confidence Interval by Index Sampling Lake Density, x Biovglume, Chloropgyll, Area 106 units /m3 mm /m3 mg/m Year _yi 1974 reference (2) 23 537 156 242 116 2.42 0.51 discharge (3) 23 315 i 82 119 29 1.07 1 0.35 1975 - reference 24 597 144 546 t 152 2.37 0.54 discharge 24 290 65 190 1 49 0.96 0.14 1976 reference 24 708 322 420 154 2.07 0.50 discharge 24 361 66 212 72

• 1.08 0.15 1977 reference 24 1125 641 887 566 2.55 0.66 discharge 24 464 120 308 f 119 1.22 0.19 1 The months January, March, May, July, September, and November were used to-analyze data for each year because of the availability of data in each study year.

2 Data averaged for Locatiots 500.0, 502.0, 505.0, and 506.0.

3 Data averaged for Locations 503.0, 508.0, 508.5, and 509.5.

. -1 l \

l i

I ,,

1.3.4-24 ONS 12/77

Table 1.3.4-5. Description of sampling locations and lake areas of Lake Keowee used in data analyses. 1977.

b TO DESCRIPTION CLASSIFICATION 500.0 approximately 14 km up Little River arm from discharge structure 501.0 approximately 10 km up Little River arm from discharge structure * ***"

506.0 approximately 9 km up Keowee River arm from discharge structure 0%

505.0 approximately 5 km up Keowee River arm from discharge structure p 503.0 Keowee River - Little River connecting canal, 1 km from discharge u2 structure Intermediate area

't- 502.0

• Lake-side of the skimmer wall, approximately 3 km up Little River da arm from discharge structure w

504.0 <1 km up Keowee River arm from discharge structure 508.5 <1 km up Keowee River arm from discharge structure Disdiarge area 508.0 discharge cove 77 509.5 intake canal

• estimated percent of total lake surface area O

m

3

~

a

Table 1.3.4-6 Zooplankton Taxa of Lake Keowee Collected through December 1977 Arthropoda Crustacea Copepoda Calanoida

• Diaptomus mississippiensis Marsh Cyclopoida

• Cyclops thomasi (Forbes) ~

• • Cyclops vernalis Fischer

• Eucyclops agilis (Koch)

Eucyclops prionophorus (Kiefer)

• Mesocyclops edax Forbes

• 0rthocyclops modestus (Herrick)

• Paracyclops fimbriatus (Fischer)

• Tropocyclops prasinus Fischer Harpacticoida

• Canthocamptus cf. assimilis Kiefer

• Canthocamptus ef. sinuus Coker

• Harpacticoid spp.

Cladocera Alona_affinis (Leydig)

• • Alona circumfimbriata (Megard)

• Alona gutatta Sars

• Alona quadrangularis (Muller)

Alona setulosa (Megard)

• Alona spp.

• Bosmina coregoni Baird Camptocercus spp.

• Ceriodaphnia lacustris (Birge)

• Ceriodaphnia reticulata (Jurine)

Chydorus piger Sars

• Chydorus sphaericus (Muller)

• Chydorus spp.

• Daphnia ambigua Scourfield

• Daphnia laevis Birge

• Daphnia parvula Fordyce Diaphanosoma brachyurum (Lidven)

• Diaphanosoma leuchtenbergianum Fischer

• Disparalona acutirostris (Frey)

• Disparalona spp.

• Holopedium gibberum Zaddach

• Ilyocryptus spinifer Herrick

• • Kurzia latissima Kurz

• Leptodora kindtii (Focke)

• Leydigia leydigi (Leydig)

• Sida crystallina Huller

• Simocephalus expinosus Birge

• Observed during this reporting period

• • Observed for the first time during this reporting period 1.3.4-26 ONS 12/77

Table 1.3.4-6 (cont.)

Zooplankton Taxa of Lake Keowee Collected through December 1977 Rotifera Asplanchna amphora West rn

• Asplanchna priodonta Ehrenberg Brachionus angularis Gosse

• Brachionus patulus (Muller)

• Brachionus spp.

• Chromogaster ovalis (Bergendel)

• Collotheca balatonica Varga

• Collotheca discophora (Skorikov)

• Collotheca libera (Zachairas)

• Collotheca mutabilis Hudson *

• Conochiloides coenobasis (Skorikov)

• Conochiloides natans (Seligo)

• Conochilus unicornis Rousselet

• Dipleuchlanis spp.

• Euchlanis spp.

• Filinia spp.

• Gastropus stylifer Imhof

• Hexarthrs mira (Hudson)

• Kellicottia bostoniensis (Rousselet)

• Keratella americana Carlin

• Keratella cochlearis (Gosse)

• Keratella crassa Ahlstrom

• Keratella earlinae Ahlstrom Lecane acronycha Harring and Myers j Lecane crepida Harring and Myers l Lecane depressa Harring Lecane flexilis (Gosse)

Lecane haliclysta Harring and Myers  !

• Lecane hornemani (Ehrenberg) l Lecane leontina (Turner)

Lecane luna (Muller)

Lecane mira (Murray)

• Lecane ploenensis (Harring)

• Lecane spp.

• Lepadella spp.

• Macrochaetus subquadratus Perty

• Macrochaetus spp.

• Monostyla crenata Harring and Myers

• Monostyla lunaris (Ehrenberg)

Monostyla quadridentata Ehrenberg Monostyla stenroosi Meissener

• Monostyla spp.

Noltholca spp.

• • Philodina spp.

• Platyias quadricornis (Ehrenberg)

• Ploesoma hudsoni (Imhof)

• Ploesoma truncatum (Levander)

• Polyarthra euryptera Wierzejski-

• Observed during this reporting period

• • 0bserved for the first time during this reporting period 1.3.4-27 ONS 12/77

Tcbio 1.3.4-6 (cant.) Pega 3 of 3 Zooplankton Taxa of Lake Keowee Collected through December 1977

• Polyarthra dolichoptera (Idelson)

• Polyarthra major Burckhardt

• Polyarthra vulgaris Carlin

• Ptygura libera Myers

• Ptygura spp.

' *Synchaeta pectinata (Ehrenberg)

• Trichocerca capucina Wierz Trichocerca chattoni (de Beauchamp)

• Trichocerca cylindrica (Imhof)

Trichocerca longiseta (Schrank) -

Trichocerca multicrinis (Kellicott)

• Trichocerca platessa (Meyers)

• Trichocerca porcellus (Gosse)

Trichocerca pusilla (Jennings)

• Trichocerca similis (Wierzejski)

• Trichocerca stylata Gosse

• Trichocerca spp.

• Trichotria spp.

Unidentified Bde11oidea Unidentified Rotifer

• Observed during this reporting period

• • Observed for the first time during this reporting period 1.3.4-28 ONS 12/77 l

~-

t e ,

Table l.3.4.-7. Summary of Friedman Two-way Analysis of Variance by Ranks for major taxonomic categories of zooplankton. Lake Keowee, 1977.

DATA CROUPS TREATMENT / BLOCK COPEPODA CLADOCERA ROTIFERA TOTAL ZOOPLANk"r0N Jan-Dec 1977 1 57.23* 11.91 52.78* $9.59*

2 75.35* 33.34* 79.08* 73.49*

Stratified 1977 1 44.14* 26.97* 30.05* 45.79*

(Mar-Sep) 2 1.71 0.69 0.18 0.58 F Destratified 1977 'l 21.00* 12.32 33.87* 23.80*

j[ (Jan, Feb, Oct-Dec) 2 1.30 0.56 0.22 1.10 1 location / month 4

2 month / location

• p50.05

. Ow 4%J .

• w e

100 -

16---M Chlorophyceae

, O Bacillariophyceae M Dinophyceae _

80 -

8 t

y 60 -

O e

w 0

Y $

! 'T U '"

8 g 40 20 .

0 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr

" 1977 e Mean percent composition of total density for major algal classes occurring at w Figure 1.3.4-1.

nine locations in Lake Keowee, SC.

d

100 -

__qg Chlorophyceae 0 0 Bacillariophyceae S ll Dinophyceae 80 -

8 0

8.

g 60 -

o U

- 8 L 8 1 **

b 40 -

1 20 -

4

^ ^ ^

4 O -

^ ^

c) Jan Feb Mar Apr May Jun Jul Aug 'Sep Oct Nov Dec

$ 1977 kl Figure 1.3.4-2. Mean percent composition of total biovolume for major algal classes at nine 23

~4 locations in Lake Keowee, SC.

i 4

11.0 1.0 10 35 January a s 10.0 =q , 4.0 8 - 28 El

,t .,,

,, 4 e' J j

ea .I 3 .0 6 *' 21 .*

g 8

- r 3

.I  :. - *

=

i 1 -

e y

• g ~ .e. .

e0 .

=

2,0 -2 4 .3 -

's : .

2 2 6 3 I . .

E

= -

7.0 -

1.0 E ' 1 6.0 0 0 0 5

i: 9 4: 4 e e:

9 e

R e

• * * * *9 * *

- ~ ~ o e e e E 3 $ R R S 3 location (distance from discharge structure, km) 11.0 5.0 10

• II b

i

't

28 . g 10.0 .il 4.0 -

8 ,,

JL

• ti

• al IB r m* u 9.0 -

6 m,' 21 ,*

, 3.G

=

/- = ,

E s-f -l' i

7=  :-

e -

I

, 8.4 e

, 2.0 -

4 e g

14 l

o 1

3 3 2 - 7 7.0 1.0 -

6.0

• 4

? $ Q E E A $

0 5

3 o

d 5Nd

• • 1 b

D*

~ e e + e

} R R R R S 3 location (distance from discharge structure, km)

Figure 1.3.4-3. Euphetic some phytoplanktoo standing crepe and surface temperatures measured at selected locations, Lake Keowee, SC Le January and February,1977.

1.3.4-32 ONS 12/77

11.0 e 3.0 10 IS Ma r th 3

11 10.0 <> 4.3 -

8 :S Il 'I Ja <>

g

• al

-:1 9.0 a

? 3.9 =

• 11 g 6 *e. e a .( ^

e. i 7 -

e

~ t s.O .

2.0

• l' 3 3 -

e 7.0

• 1.0 3 I 6.0 0 ' ' ' '

- n a0 0

• - ?

m o A. e. O. 8 C. 8 O O O O

• O 9 9 * *. .*

• O C

$ 5 E. $3! $ $

location (distance f ree discharge structure, km) 11.0 3.0 10

• 3S April ig 10.0 " q ) 4.0 S .

28 , g II 1 , il

.l 11 m," m,* - -

u

}

9.0 a # 3.0 I 6*a -

21 e' b

• r a 4 I . 2 5

i m

O i

o a 8.0 - o 2.0 14 .g E E 4} a 3 3

• 7.0 1.0 Z 3 "'I 6.0 = 0 '

0 0

)O o' 9 9 9

• 9 9 O O O

• O O S d

• m 9

a e

e 9

e 9

2 R R R R R g R e location (distance from discharge structure, km)

Figure 1.3.4-4. Ewphetic sone phytoplankton standing crops and surface temperatures measured at selected locations. Lake Keovee.

SC. la March and April 1977.

1.3.4-33 ons 12/77

10 33 11.0 3.0 g May J

4

' a.0 '

20,l it 10.0 11 3E

<l u"

2 i

• • e 21 ,-

% 9.0 l 3.0 "

1 8 . } 4

~

. g "o 0 A

"g 7 _ #_  % i

-- i a f 2 3 I =3 g 2 .

2

• J43 14 4 3

g- e.0 3

. 2.0 J

lo "

-] ,

L L I

3 I 7.0 h 1.0 i

i ,

e

> a

• 0 0 6.0 = 0 k k O $ 0 o O o

• A a i a A i E E I o 6 X e 5 a

A 4 i A g k 2 3 2 3 3 3 a location (diatance from discharge structore, km)

- - + - 10 e 33 11.0 - 3. 0 ,

8 June i J 1

1 ---e 8 28 it 10.0 b i ' 6. 0

• i i i

an <i n ,it i ** al

• ll f

4 .,

j

? f? 5 I

e J 6e*e 21 3

.0 I N e.

~0 9.0 F"S a - /  ! y

.: ,1 J, }i i .

a 5

b ki3 a

[.

i f  :  :

ia w

i s'!

e 38.0 - 32.0 43o - 14 4 e is

• 4 3 3 m Z

2 7 7.0 - 1.0

' ' ' ' 0 0 6.0 0 '

o k k 3k k k e  : = se e e R * *. *

• g g e. a A

g ,M e S +

A S S +

locaties (distance free diacharge structure, km)

Figure 1.3.4-3. Euphotic some phytoplanktoe standtas crops and surface temperatures measured at selectes' tecettees. Lake Keowee.

sc to May and June.1977.

1.3.4- 34 033 13/77

10 35 11.0 1,0 Jsty

^

- .e _

s . 2:

' 10.0 -o ..t El 'l JE

"# ll 41

. u e a 6aa 21 7

9.0 'Dg 3.0 g

f -

.i A

p

' I e 1 2 *

• 3 t A -

• l' 3 8.0

• 2.c d

= = y m

3 3

= -

2 7 7.0

• 1.0 .

q -

' ' . e 0 . 0 6.0 = 0 5 h 9 s94

s

9 c*

e

=

• 9 8 8 3 ;3 8 8

+

8

+

+ + + + e e location (distance f rom discharge structure, km) 11.0 5.0 10 3 35 August

,8 28 ii 10.0 < > 6.0 _

iB II 3t i>

- <l r

e a 6 *8. 21 g*

9.0 " l 3.0

=

• 8 t g  :

I

e i 2

• j 3 e e s 8.0 - e32.0 - 42u 14 3 r .3 a

~ s I

l i

2- 7 -

7.0 1.0 -

= 0 0 0' .j

. 6.0

)  :.

k k e :

k k e

k e: -

o - m a e e e e.

3- .R 2 3 3 3 3 3 location (distance from discharge structure, km)

Figure 1.3.6-4. Euphotte some phytoplanktoa standias crope and surface '

temperatures measured at selected locatione. Lake geouse.

$C. La July and August,1977.

I 1.3.4-35 ' ONS 12/77 j f

I i

n

1 1

l l

\

l 10 35 11.0 5.0 september qi 8 28 , l ji 10.0 4.0 > en -

El Ii , <[

II Il u

e e 6,* 21

~

9.0 *

• ~ 3.0 . * *.

}

• 1

• m* .-

! =. .

n e

W e i i 4 j 3 2 e g 43, 14 .g s.O . 3 2.0 -

W 3 .s

.1 3

2 .e 7 7.0 . 1.0 .

a = 0 ,0 0.0

• 0 k kk k= k k e a

= = =e c., e

=

a a a a a + r a A

5 2 5e N

R $d $,

e R R #

b location (distance free discharge structure, km)

. .-- * -- ., 10 = 35 11.0 p 5.0 - - - - -

Oc tober J J p .

a 8 - 28 ,g li 10.0 b ' ' 4.0 b ,

is

'b l <i ni

[

- ** M .l. tl I

• .  ! _.- I -

e 4 21 ,*

p"l,.3.0 6",

d 9.0 1

}

3 m

.~

2 3

. =

.' I

=

e.

a  :

N -

4 .*. 14 -4 3 8.0 22.0

• g 1

3 3 is 2 7 7.0 1.0

. 5 o o 4.0 . 0 e ~

k kkk k k

= c*  : ese e c

• 9 * * *

- ~ a = g e g 3

a R R R R , R ,

location (distance from discharge structure hm)

Figure 1.3.4 7. Euphette some phytoplanktoa standing crope n W surf ace temperatures usaeured at selected locations. Lake Keowee.

SC. in September and October.1977.

1.3.4-36 otts 12/77

r___ _ . -._.

11.0 1.0 10 35 Neventee 11 10.0 il 4.0 8 28.l El Il

,li al

,. ,. 11 a e e 9.0 J 3.0 . J 3 l 6aw

. 21 e

d ,. .+ -

i !e 7_

E 1 -

a. 6 j

~

m

.I. i e -

I 8.0

• 2.0 e o 6o. . 16

• Z ." G 2 3

3 3 a 7.0 1.0 2 7 m

w _ _

6.0 0 0 0

?  ? A E C 8 A R

a. 2 A a 4 a  ; i E o K o 6 % o 3 6 4 .;  : 4 4 A 3 2 i 3 S S S 2 X loca!!as (distance f rom dischange strweture, km) 11.0 .  %.0 10 -

31 D=ces ser .

10.0 6.0 8 -

28 ,,

11 ii 1, . *I n u

<> is 9.0 *

• lU -

e. <

.g ea'- y 21 l

y I

7 -

y  :

5

" J

.f.

~

l

_/

I -

i e 1 g a.u ;g.:.o  ;

14 X l 6 .:

3  ; 6 a e

3 2 e .

3 3 7.o i .o 2 . 7 1

l l

1 6.o . o O 0 l R 8 A E E 5 o l

, 3 $ d 55 5 0 C 3 4 * **

• 9 *

~ m e o e k 8 3 3 3 3 E l

1eestien 1 distance f rom discharge structure. km)

Figure 1.3.64. Sophetic sone phytoplanatos standtes crepe sad surface temperatures esseured at selected locattens. Lake Keowee.

SC. Se November and December.1977.

1.3.4 17 CNS 12/77 l

4

A x x 1000 - (1135)(9145)(5191)

' A m

A (4688) d* 800 -

~

Y 600 -

Ta ~

G "

. 400 -

w x

0m -

o 8 200 - .

o N ' ' ' 's t ' ' s a e i "3

• 0 X X (1407)(6345) 1000 - A &

(1048)(2613) e m

d 800 -

0 e 600 -

1

@ 400 -

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U 200 -

' ' ' ' 8 ' ' ' ' 8_

0 10 -

~

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wa -

t 6 -

C ' i .

P

? 4 -

l j

i a

u d

2

[f_

2 -

0 0 N D J F M A M J J A S Month Figure 1.3.4-9. Phytoplankton standing crops for the two arms of Lake Keowee, f

1977. Location 500.0 (W-M) represents the Little River arm and Location 506.0 (4 - 4) represents the Keowee River arm.

l 1.3.4-38 ONS 12/77

l' !i' Ill l\

Po .

8 nsn ret's

".o .

7m .

3 m

/ .

g '

o

, 7u .

l l

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0 <

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=

w$o .

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/

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. " 2oEn*. Fv m$c a s- ,d . . EE r$4f.

c i*

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$ D 3000 -

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Y e t I I I o o *. * *

• d d 4 8 SE R S o 8 m c c Location O Figure 1.3.4-11. The amount which two desmid taxa densities (Arthrodesmus sp. and Cosmarium

" asphaerosporum var. strigosum) observed in 1977 exceeded densities of U previous years in Lake Keowee, SC. Densities for August 1977 minus August 1974 (M--M) and September 1977 minus September 1976 (H) are presented.

}

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.. , u.  : "": 1

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Igj29I.

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s.... .

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1.3.4*41 ONS 11/77

DOS TOTAL 200 PLANKTON t o-60-40-2&

01 e0-TOT AL COPEP00 A 50-a w

• 40-

.a a 30-w t o-a w

an so-3 3

s C TOT AL CLAD 0CERA 10-g TOTAL ROTIFERA 30-20-i 10-I

'O'N'J Sdkb J FNhMJ J hSUN bJ FU NJ J h'S bb b3 kW5UU 3 ES bb b ISTS OU 1974 1975 Figure 1.3.4-13. Seasonal distribution (10 m-to-surface) of major taxonomic groups of socplankton in 1.ake Keowee for 1974 through 1977.

Abundance of tooplankton in the lake was estimatedintermediate by computing a grand mean of reference (500.0, 501.0, 506.0).and discharge (508.0, 508.5, 50 (502.0, 503.0, 505.0),

area densities.

ONS 12/77 1.3.4-42

s' 8 - -o 90s q o sos

\ s e t 8' 'g o i g- '. -osos M ) -

ows a .a a 5 8 e

et , &*

e*

i

• g4 a I 8 g

) wo3 o os

{ ea .I W e,

-o vos

.s' sos

.o gos -

s9os o'1Cs g,

l. e'

• f, -

otosf

-o'tos I - , -

3 l"' h

. -o*20s s g-o Zos g f

• 8 3 a l I I

i2 l (. e$ ,! I

'

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j* r e g;8 l o 0 I r , wa #

$ o I >@

-

• e 2 ,I

' E8 ja- 2_ , i

!- !g ,4 -onos "t / ou t- ,' s I

o

/ l I

n, r

., e o& i s ,' s E .' -roos 4 -

ows 2 2 3 3 8 2 9 3 3 3 8 2 vain um isot=vwz wtot a' ,. -o pos ., -roos

's N

', 's i N

.- ', g ',.

' e -rsos

,3 . -o sos 'y j

e

' l e

- 5 ,,

T '

5 \ r l

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s G' g n a- #

w %g ,'.

.sos,os os W 1' - os -

2 o,os 3 -

e 1,- -roos psos f-; gg 9. ~,e

/ -otos , ,.

g .,".. ,b rsos g s -

8

- ,' 6 *IJ

~, *

" - N' lu -

14 '

v' -o ros $' ;I t -rzos ! -

g-l 3 0

~

I l Eg l

$e

• g / Y

.hagg

-t g8 s

)

8

[ { Ir /

a rg 1  :

g. .

yw '

a ro /

iy C5 - si 33 o

,I-

.t2 l EE- /

P, :a 3* l. -

i .l . . . .o ..

• . ,,./ - -oios W

! . ,.. --*. -rios  ;

gu.i i

, . i l

, , 9

,k4i

/;

3o.! ,

t g .#

c, ,

o*oos '

-.,,*' -o*oos af ap e i e a , f f f f f a f f me t t t i e i e t 3 e , a

'R 3 2 2 e o 3 3 E 3 3 .4 .2 2 2 - #

.usal W3d NODeeV1dOOZ 7V101 Figure 1.3.4-14. spatist distrt'>uties (lo e-to surface) of scoplankten in take Keowse for stratified and destratified periods of 1974 through 1977, Denstates were calestated as a aman of usethly denstates categorised as stratified and as a mean of moethly densities categottaed as -

- destratif ted.

3

'I

. 1. 3.4-43 _ oits 12/77,. '!

L d'- ., >

l

TOTAL ZOOPLANKTON '

c - 3 CCPEPODA l

, ..._.4 etantvwqa

- --- ,e m RA KLOhETERS FPOW 045 06 CHARGE STRJCTl#IE BY WATER .

9 6 3 0 3 s 9 6 Q 45 .  ;

40 .

STRATF1ED PUttC S77 35 . (WWI TWIOUOM SEP) 30 .

25 .

p 20 .

N /

IS .

\ ,

--- N

- - .,. s . 5 /

Ny/:

---

.__ ^------..

S .

0 '

i a i; iill i i KLohETERS FROM ONS Ol8CHWt0E STRJCTLPE BY WATER iS i2 s s 3 0 3 s 9 2S DESTRATFIED PEROD 077 20 . (.lAN. FE8. APO OCT TH40UIE4 DEC)

IS .

10

-% ;T= -

p l  % -~~s , /

- r__--.w-S_g_ s/ ,,,,. _e_ .

S .

i H i ilii i i SAnati LOCATIONS Figure 1.3.4-15. Spatial distribution (10 m-to-surface) of major, taxonomic

- groups of zooplankton in Lake Keowee for stratified and destratified periods of 1977. Densities were calculated as

, a mean of monthly densities categorized as stratified and as a mean of monthly densities catenorized as destratified.

l-1,3,4 44 ONS 12/77

l IMMATURE COPEPOOS 25 _

ADULT COPEPODS

(

CLADOCERANS 20 .

• l**: ROTIFERS I

a:

w l 3 2 k

o l5 .

1 g 10 y .

5 - ........ .

0 ........ .....- -

502.0 509.5 508.0 502.0 509.5 508.0 l STRATIFIED 197/ DESTRA'ilFIED 1977 Figure 1.3.4-16. Densities of zooplankton (10 m-to-surface) lakeside of the skimmer wall (Location 502.0), in the intake canal (Location 509.5) and in the discharge cove (Location 508.0) of Lake Keowee for stratified and destratified periods of 1977.

l Densities were calculated as a mean of the monthly dansities categorized as stratified and as a mean of the monthl, densities categorized as destratified.

1.3.4-45 ONS 12/77 i

1.3.5 BENTH0S Specification: The benthic macroinvertebrate populations of Lakes Keovee and Hartwell shall be sampled four (4) times per year. Sampling stations shall be located on the lake side of the skimmer wall (502), in the vicinity of the discharge, (Discharge canal and 504), at control stations on Lake Keowee (501 and 506), and in Lake Hartwell below Keowee Dam (604 and 606). Quantitative samples shall be taken with a modified Petersen grab. Qualitative samples (e.g., sweep-netting shall be taken along the shore nearest eacn of the stations listed above.

Benthic organisms collected shall be identified to the genus level where practicable. Diversity indices shall be calculated, .

as well as data on standing crop of benthic organisms, such as number per square meter and/or grams per square meter (Duke Power Company 1973a).

I. INTRODUCTION A discussion 'of the value of benthic macroinvertebrates as environmental monitors has been presented previously (Duke Power Company 1973b).

II. METHODS AND MATERIALS The methods and materials were the same as described in the ONS Environmental Summary Report (Duke Power Company 1977), except as indicated herein.

Quantitative estimates of 011gochaeta were presented at the Class level; in addition, a qualitative checklist was compiled to record taxonomic composition.

III. RESULTS AND DISCUSSION Lake Keowee: Littoral Zone A total of 60 taxa was collected in Lake Keowee core and sweep net samples, of which chironomids (31 taxa) and oligochaetes (8 taxa) were the most diverse groups. The greatest number of chrionomid taxa (20) occurred in the subfamily Chironominae (Table 1.3.5-1) . Six genera of Orthocladiinae and five' genera of Tanypodinae were also collected. Dominant chironomids in core samples were Cryptochironomus sp., Pseudochironomus sp., and Stictochironomus sp.

The Naididae (3 taxa) and Tubificidae (4 taxa) were the most diverse 011gochaeta families (Table 1.3.5-1). Other frequently occurring organisms included chironomid pupae and ceratopogonid larvae.

Chironomids and oligochaetes, as in previous years (Duke Power Company 1977),

continued to be the dominant benthic organismo in the littoral zone of Lake Keowee in both density and standing crop. Chironomids represented 85% of

~

the total density and 77% of the total standing crop in 1977, while 011gochaeta comprised 6 and 16% of the density and standing crop, respectively.

The highest mean annual density (2,505/m2 ) and standing crop (1,573 mg/m2) of macroinvertebrates occurred at Location 505.0 (Fig.1.3.5-1). High densities of macroinvertebrates at Location 505.0 have been previously reported (Duke Power Company 1977), and were attributed to the excellent habitat provided

.ONS 12/77 1.3.5-1

k I

2 l by the aquatic vegetation. The lowest mean annual 2 density (551/m ) and the lowest mean annual standing crop (225 mg/m ) were recorded at Location l

. 508.0 (Fig. 1.3.5-1) and were attributed to unsuitable substrate and wave i action in the discharge area. Low densities and standing crops of macro-invertebrates have commonly occurred at Location 508.0 (Duke Power Company

' 1977). The highest monthly mean density and standing crop of macrainvertebrates in the littoral zone occurred in August. The lowest mean monthly density occurred in February while the lowest standing crop occurred in May (Fig.

1.3.5-1).

. , The highest number of taxa (34) was identified from Location 504.0, and the lowest (21) was identified from Location 502.0. Similar findings were noted in the Oconee Summary Report. The low numbers of taxa at 502.0 were attributed to the poor substrate of hard packed clay. .

Lake Keowee: Sublittoral and Profundal Zone i

l It appears that only slight changes in taxonomic composition have occurred since sampling commenced in 1973 (Duke Power Company 1977). With the exception of Corbicula, which was collected for the first time in August, no new taxa were found in 1977. Taxonomically, the groups that were the most diverse in the littoral zone of Lake Keowee were also the most diverse i

in the sublittoral and profundal zones, and have remained so throughout the study. Chironomids and oligochaetes were the most diverse groups, with 29 l

and 6 taxa, respectively. Chironominae was the dominant subfamily with 17 4

taxa, while Tanypodinae and Orthocladiinae were represented by 10 and 2 taxa,

! respectively.

j Chironomids, oligochaetes, and chaoborids were the dominant macroinvertebrates in density (95%) and standing crop (70%). Chironomidae was the dominant benthic group by density (52%), while Oligochaeta was the dominant group by standing crop (46%). -

Macroinvertebrates were most abundant at Locations 501.0 and 506.0 (Fis.

1.3.5-2). lh2 previous years, there were high densities at these locacions (Fig. 1.3.5-3); the high densities were attributed to organically er.riched substrates. The discharge (Location 508.0) had a characteristica13y low density (221/m 2 ) in 1977 (Fig.1.3.5-2). Low densities have repeatedly occurred at the discharge (Fig. -l.3.5-3), due to the unsuitable substrate and low organic carbon (Duke Power Company 1977). The maximcm mean monthly density (1,348/m 2 ) of macroinvertebrates at all locations occurred in winter and the minimum (399/m 2 ) occurred in. summer . (Fig.1.3.5-2) .

Fluctuations in total density were related to changes in the density of chironomid populations. Densities of Chaoborus punctipennis, which had pre-

[ viously been low (Duke Power Company 1977), remained low throughout 1977,-

with' seasonal peaks occirring in February and November (Table._.3.5-2).-

'Although densities of _C_. punctipennis have not been exttemely Ligh in Lake Keowee, (Duke Power Company 1973b), the decrease since 1973 catuot-be fully explained. Some possible causes for the. decrease were mentioned in the Oconee-Susanry Report (Duke Power Company 1977).

The annual mean standing crop was high at Locations 506.0 and 508.0 (Fig.

~

1.3.5-2) in 1977. Location 506.0 has consistently had a high st anding crop (Fig. 1.3.5-4),'which has been associated with the high' organic carbon content j

i of the sedimects,Jand also with the' larger. size of profundal macroinvertebrates.

1 01S 12/77.

1.3.5-2 q

In past years, however, the standing crop at Location 508.0 has been lower than at other locations (Fig.1.3.5-4); it was higher in 1977 due to the collection of the wingle large Corbicula in August, which accounted for 90%

of the annual star sing crop. Seasonally, the maximum mean standing crop 2

(1,434 mg/m ) occurred in August, coincident with the time of minimum density (Fig. 1.3.5-2). However, the high standing crop in August was due to the collection of the single large Corbicula at Location 508.0. Excluding this specimen August mean standing crop would have been reduced to 578 mg/m2 ,

In the laat three decades, Corbicula has become widely dispersed in freshwater habitats in North America. Once Corbicula enters a river basin, it rapidly exploits the new habitat with an explosive population build-up (Sinclair 1971).

It is believed that Corbicula will proliferate in Lake Keowee in the future and will contribute significantly to the standing crop.

Although diversity generally decreased as depth increased, the differences between the number of taxa in the littoral zone (60) and in the sublittoral and profundal zones (51) were slight. The highest number of taxa was identified from Locations 501.0 and 505.0 with 34 and 27 taxa, respectively.

The icwest number of taxa (14) occurred at Locations 506.0 and 508.0. In past years, similar_ trends in the number of taxa have been noted (Fig. 1.3.5-5).

Diversity indices (H) are listed in Ta' ale 1.3.5-2 and revealed highs and lows at the same locations as mentioned above.

Lake Hartwell: Littoral Zone The taxonomic composition of Lake Hartwell has remained similar to that of previous years (Duke Power Company 1977). A total of 68 taxa was collected in core and sweep net samples from Lake Hartwell, with Chironomidae (29 taxa) being the ominant group. The subfamily Chironominae was represented by 15 taxa, with Tanypodinae and Orthocladiinae represented by 8 and 6 taxa, respectively. 011gochaetes were represented with 4 taxa in Tubificidae and 4 taxa in Naididae (Table 1.3.5-3). The lictoral zone in Lake Hartwell was more diverse tFan the littoral zone in Lake Keowee. The Tanypodinae and Orthocladiinae were also more abundant and diverse in Lake Hartwell than in Lake Keowee.

011gochaetes and chironomids remained the dominant macroinvertebrates and accounted for 70% of the total number of organisms collected. 011gochaetes represented a much higher percentage of the total density in Lake Hartwell (56%) than in Lake Keowee (6%). Location 604.0 had a higher mean annual density (3,893/m2 ) than did Location 606.0 (2,910/m 2 ) (Fig. 1.3.5-6).

However, Location 606.0 had a slightly higher standing crop (1,113 mg/m2 ) than did Location 604.0 (1,085 mg/m 2 ) (Fig. 1.3.5-6).

The maximum r.ean monthly density I and standing crop occurred in February, while the minimum mean monthly density '

and standing crop occurred in November (Fig.1.3.5-6) . Diversity was higher at Location 606.0 (57 taxa), than at Location 604.0 (47 taxa), and was attributed mainly to a more diverse oligochaete population.

Lake Hartwell: Sublittoral Zone The sublittoral zone of Lake Hartwell had a less diverse benthic community  !

(48 taxa) than the littoral zone. Chironomids.(22 taxa) and oligochaetes I (11 taxa) were the most diverse groups (Table 1.3.5-4). The subfamilies '

1 1.3.5-3 ONS 12/77

Chironominae and Tanypodinae were represented by 10 and 9 taxa, respectively.

Tubificidae was the most diverse oligochaete family, with 7 taxa.

Chironomids and oligochaetes represented 61% of the total density, with the respective groups accounting for 25 and 36%. Chaoborus punctipennis larvae comprised only a small percentage (6%) of the total density. Locntion 606.0 2

had a higher mean annual density (1,491/m ) than did Location 604.0. Also, 2

Location 606.0 had a much higher mean annual standing crop (27,081 mg/m )

than did Location 604.0 (1,372 mg/m2 ). The high standing crop at 606.0 was due to the presence of large Corbicula in February samples (Fig.1.3.5-7). 2 The highest monthly mean density (3,270/m2 ) and standing crop (44,756 mg/m )

occurred in February (Fig. 1.3.5-4).

Location 606.0 had a more diverse benthic fauna (33 taxa) than did Location .

604.0 (27 taxa). Diversity indices (ii) for Lake Hartwell grab samples are listed in Table 1.3.5-4.

IV.

SUMMARY

AND CONCLUSIONS The benthic communities of Lakes Keowee and Hartwell were sampled quarterly in 1977, in accordance with the Technical Specifications for ONS. No major changes in taxonomic composition, density, standing crop, or diversity were noted from past years, with the exception of the first collection of Corbicula.

The density of Chaoborus punctipenais in Lake Keowee, which had dropped

' between 1973 and 1976, remained low in 1977. The discharge, Location 508.0, had the lowest density in 1977, but did not have the lowest standing crop or diversity. Low densities have consistearly been reported at the discharge and are suspected to result from unsuitable substrate rather than temperature and/or water quality, which were within acceptable limits for most aquatic insects. Also, the Asiatic clam, Corbicula, was collected at the discharge in August for the first time, and was largely responsible for the high standing crop at the discharge. Corbicula are expected to increase in Lake Keowee.

No detrimental effects from ONS were observed on Lakes Keowee or Hartwell during the 1977 sampling period.

l l

l ONS 12/77 1.3.5-4

REFERENCES CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47, and DPR-55, Technical Specificatians for the Oconee Nuclear Stations Units 1, 2, and 3, Duke Power Company, U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised April 9,1976, NRC), Washit gton, D. C.

1973b. Oconee Nuclear Station. Semi-Annual Report.

Period Ending June 30, 1973. Charlotte, N. C.

1977. Oconee Nuclear Station. Environmental Summary Report. 1971-1976. Charlotte,'N. C. .

Sinclair, Ralph M. 1971. Corbicula Variation and Dreissena Parallels.

The Biologists. 53(3) 153-159.

1 l

i i

i l

A

/ ^

l 1.3.5-5 ONS 12/77

Table le3e5-1 Density (mean no./m2 ) of benthic macroinvertebrates collected in a core sampler and presence (S) of macroinvertebrates collected by sweep net in the littoral zone of Lake Keoween 1977.

502.0 504.0 Recettame 501.0 A M F M A E F M y N A N Tams S.131 S.249 Chirescaldae (p) 8 S.26 53 26 24 Chironomidae S.105 3 8 Abtabessyta segere S Ablabesmyta malloch1 Coetotanypus scapularte $ S.184 p g ed6ue opp. S.220 316 53 210 procladium belli.e 26 S.552 8

Oethociaditnae U.S. 8 Critotopus op.

Microcracetopus sp. S.316 S.920 parakteffertella op. 26 ISS 3.421 S.158 S S poectrocladius op. S Setttia opp. 3 Chiremonital U.I. 53 8 8 S.158 8.526 S.79 Cryptochtronomus op. 26 24 33 105 S Cladopelma sp. S 3.552 S

Cr2S_t*t'ad_t

- ~ t 'l *p.

F.* $lerotenJipes sp. S.158

• Chironoeuw sp.

y Siiothou-a e,. 8 158 53 u pa Laetteita op. S 3

fotyneiT E app. 5.26 79 5.158 S,26 S S S m folypedi_g (Tripodura) Srp.

gotyped t.,sen (Nubeculeeg grp. 5 to}ygedij g (fallas) gry. 8 S S.105 26 pseudochtrinemus op. S

$tenochtr e ous op. S.1499 8 3 S.920 S.1183 33 S.421 S.6154 158 105 M M tuchtri,nomes op.

Tanytarstal U.I. 1026 Cladotanytarsus sp.

8 8 S.26 S.53 S.79 S 368 nacropsectra sp.

237 S.447 stempellana sp. 8.316 S 26 S S.26 S.710 Tanytarsue ap.

Ceratoponomidae '(p) 26 S.53 S S,33 S.53 8 S.552 palpomyte comples (paleomyte sp., Sessie 8.26 S 131 S.421 sp., probesa ta sp., 'a == = = ===qrta sp.)

(lesvae) 26 AlluaudosM a opp. S 8.79 26 Dasyhelea opp. S 8 26 Chaoborus punettaenste 26 Decette opp.

S S S 8.26

{olycentropus opp.

Cent roptilwa app. 8 ucptagentidae Neuantenta opp.

o Con +hwe opp.

/. S f./1 Coenast1onidae 26 53 26 uydrachaellae 8 S.26 158 26 8,79 79 oligochaeta Neldidae t y +

pJ Asphachaeta emericans N pale vertabitte f Lesubriculus verseastue

Table 1.3.5-1 (Cont)

Locattens 501.0 502.0 504.0 s fame F M A W F M A N F M A X, Tubtfacid.no l'.I. 8 Aetodritue linnobius +

[limodritus spp. 5 Lien Mailes hoffecteteri S tienateda S S S,26 79 53 26 53 131 semeertimea . S S 26 Prestoma spp. S S S S Corbicula opp.

Pectiestetta meanifice +

' Total Littore! Tema 2 4 15 25 13 4 11 10 7 to 17 21 8 Mesa Number of saate=3/m 78 185 1M5 7628 79 973 1841 157 79 3158 53tN 1811 Wet Weight (as/ ) 21 . 92 MS 1874 26 113 1107 45 34 318 423 131 fel - p.eee g' . + = orgentese present in core samples Y

e

.W I

N 6 9 G 9 E?e)

E D EEPJ

& e)

W

$ D b

DJ N

M

. M e

Paga 3 of 4 Table 1,3:5-1 (Cont) 506.o 508.0 sos.o y g g _ y n a y locations y y a y a Tasa 8 S.53 8 S.26 3.79 8.131 8.26 131 Chironomidae (p)

Chireeceidae g 3 26 Ablabesmyta gap g Abtabeserta mallocht g Coetetanypus seasularte 8 26 3 26 a procladius opp.

procladius bell a 8

. Otthoclad!!ame U.1. -

8 Cricotorve op. 5 158 s.105 nicrocricetopus op. s.105 S.158 8 m kteffersella op. 33 26 poectroc.ladtwo op.

Setttia app.

8.53 8 5.79 26 S.79 8.26 5.26 Charonenting U.1. 3.237 s.53 s.789 8.289 S.26 ggstechtronoems op. 3,237 8 Cladopelas op. g 3.79 3 Cryptotendipes op. S 5.79 Dieroteadtpos op. 3 8 8.79 ghtroeceue op. 3 26 53 3 H pt!=thauma op. 26

• panastielle op. 26 79 s.158 s.26 s s.53 79 F . yo reedttua spp. s.158 s.26 79 s.131 79 Ut po JP*flyan (TrJ2*c.l*J.a) grp.

F.a. s I ivredt um (hub utoeve) gry.

00 Pol y ped t we Qatten) grp. 3.131 368 S 605 8.1673 8 8 C_)3 m

pseudoch renoeue op.

stenochtronomus op. 8.162o 158 8.364 S.2525 8.736 8.158 8.166 5 S.158 5.526_

(

)

itietoch!renomus sp. '---

Ianytaretat U.t. 53 79 8.421 8.79 5.53 S Cladotanytareas op. 26 8.79 131 C 237 S.26 Microssectra sp. 368 8.316 5 8 53 8.53 s

. h opetiima sp. 53 53 26 Tanytarsus op.

s s 26 S.53 5.158 25 8 3.26 8.53 Ceratopogoaldae (p) 3 Palpemyta comptes (palpomyte op., Bessia c' ,

op., Frobetsia sp., '= h =""=""T te op.) [A __3 (larvae) S 3i. 26 c A11usudomyIa app.

3 53 -

gaevheleg spp. -

gps.,heru_s puncttPeemio 5 '--

Decetts spp.

3 8 8 26 G) goJycentropus opp. ,

d Centroptitus opp. 26

• s o

g Comphet opp. y C/3 Coenagstonidae 26 sydrachaellae 53 S.621 S.263 S.26 5.26 8 8.53 3,1131 3.131 O!!gochaeta 8 g Baldadae y g htchaeta americans

% g vertablite

= w ru.iu. rte.at

Page 4 of 4 Table 1.3.5-1 (Cont) t=s t s-a m .8 m .8 Tome F 38 & S F M & S F [* 1 8 Tobificideo tr.1. + 3 Auledritus itseiebius +

h edratus opp. S 8.+ 5 +

Lt-e drites hoffesteter! Se+ 8 Eematode 8.79 26 S.26 S.26 26 26 g heaertimos praetone opp. S S 8.26 Corttevia app.

Pectteste!!e Me 3.

Total Littoral Tese , 13 16 18 18 17 19 16 6 8 16 16 6 sneen pueber of Ostentems/m 3156 1298 3841 2734 2928 1428 1051 447 341 498 526 841 v g u,g ght (,gfe s) 2880 171 2183 1131 781 363 781 221 34 7 179 313 181 (p)

• papee

+ = Orgestone presamt is core esoples.

E @D L GEED a Si@

cc q

Ld--

w w

P O

2:

rn H

P4 4 N N

il 8

Table 1.3.5.2 Density'(mean no./m 2 ) of benthic macroinvertebrates collected with a modified Petersen grab in the sublittoral and profundal zones of Lake Keowee, 1977.

505.0 506.0 508.0 502.0 50410 5 F M & M F M & N Iscatione 501.0 E F M A 5 F M A M & 5_ F M &

F Tua 13 29 26 Ostronomidae 26 chtremontese (papee) 13 26 13 13 26 13 ablabeoerta espere 26 26 Annabeseyte janta 39 39 sblat,esaria maltocht 24 cao totanygue opp. 13 coelotanypus ocaeularis 52 65 65 26 13 13 26 Proc'edius spp. 13 26 13 39 26 65 65 91 Proc .adius (Pettetsavoue3 M 11ee 65 13 Proc indtus (h o yclg app.

Poectrotamipus dgari 26 13 13 Clinotanepus opp. 13 13 26 79 Perakter: este11e op. 117 26 13 13 Poectroc ,edies op. 26 13 39 26 39 13 39 13 32 Shtronoeue op. 13 cryptochtromouve_ ep. 39 .

fyryptoLendi2 ** . ap. 39 Dicrotendtoes op. 26 Endochtronoeue op. 13 24 Baratshtta op._ 26 13 13 26 26 143 39 H utloghauma op. 13 156 13 130 403 52

• gegam e h ep.

91 13 13 g 78 39 13 13 13 Etedopetes sp. 52 13 26 vi heu+,c hireno . op. 1300 299 .286 13 962 286 39 39 299 78 65 39 13 .13 I stictochtronceue 65 143 39 52 78 91 13 26 286 260 H retypedstum GrIpodera) $rp. 13 13 13 78 O Tanytaratet U.1. 26 39 26

$1 dotanytarena sp. 78 104 13 Micropeectra op. 65 Stoneettina sp.

78 39 13 52 65 26 546 39 117 195 13 Taartarous.sp.

65 39 26 '65 52 39 13 78 13 39 13 26 taipuerte comptes (Palpoorta ep.. Bessie op.. Probensta sp., 117 182 26 2M Johanneenomyta sp.)

52 52 39 104 78 13 104 26 26 13 52 182 13 chaoborus punctisenate 13

' 13 26 s t A Chachorus pusetteennie (pupae) 26 13 13 \_J oecette opp. 13 26 tc A 32 39 k~/

Polycentropus sp. ~

Gomphoe op. C 13 13 13

$1a14e op.

Mydrachnettaa 26 13 104 2418 1235 845 1404 26 39 351 39 01:sochaeta + +

Nate avaalle + + + + +

IIain variablite '

+ +

T tficadae 7 ~

Ailodrito_e tienobtus

+

+

+

+

+

+

+ W]

b 0 Llanodratue app. +

Z llenodetius hoffaelstert 13 M Tubtfes tubtfes_ ' '

hematoda 26 13 Prootoma app. 13 13 p _

N corbicuta sp. +

Pectinatetta magnifica +

C:-

Mesa number ersantems/m 2 2236 1066 458 221 403 234 104 156 1339 1001 117 299 1040 1092 312 442 2743 1313 897 1547 32 5 156 1 Wet wetsht (as)/m 2 368 795 4567 9872562 119 5 454 165 to 14 332 439 7 81314191 14 235 9 320 4 20256 2449 6 2344 4 2136 9 2 2687 5

1893 5

h273 46 5:49 217 Total number of tems 13 15 17 - 27.0 - 10.0 - 25.0 20.0 6.0 - 13.0 19.0 9.0 18.5 22.0 22.0

. 8etten temperature (*C) 7.012.030.020.0 7.0 17.0 15.0 18.5 10.0 66 0.12 0.65 0.35 a = (Diveretty)

R = (8adadancy) .0.581.031.020.760.250.230.500.430.510.960.800.760.890.850.890.460.220.1

Table 1.3.5-3 Density (mean no./m 2 ) of benthic macroinvertebrates collected in a core sampler and presence (S) of macroinvertebrates collected by sweep net in the littoral zone of Lake Hartwello 1977.

Taas Locatismo 606.0 606.0 F 18 & II F M A N Chironomidae S. (26) 26 26 Chironcaldae (p) 8.(105) (53) S 5 Ablabesmyta aspera (105) 5 S (26) S Coelote.Igus scapularis (26) 5 (26) (26) S.

Coelotanypus concinnus G.

Coetocanypus tricolor (26) (26) 26 Coelotanypus spp. (26) 26 Procladius spp. 8.(131) S.(26)

Procladius (PsitotecI2us) bellus (26) 8.(186) (26) 8.(158)

Procladius (Procladius) spp. S. S. S.

Crtcotopus spp. S. S.(186) (53) (53)

Paraktef feriella spp. (ISS) 5 S. (26) S.(105)

Pee:t rocladius spp. S.(131) S. S.(26) 8.(105) S.

iticrocricotopus spp. S. 26 Nenocladius incomptus (79)

Smittia spp. 26 Cntronomus spp. S.(263) 3 S.

g Cryptochtsonomus opp. (79) (79) (26) S (26) S.(26)

. Dicretend h app. S.(26) 5 S.(53)

La Patasese11a sp. S.(316) S.

g Cl4daselma sp. (26) 8 (316) 8.(26) g Pseudochironomus sp. S.

H St ctochironomus so. S.(79) (26)

H Po ypedilum (Tripodura) Srp. (26) S. S.(53)

Pc reedilum (Polysedilum)Srp.

Cryptorendipes op. (26) 8.(210) 3*

h- )

Nilorhauma sp.

Cladotanytarsus sp. S.

5

( )

Tanytarsus sp. S.(131) 8 S. S.8 Micropsectra sp. S.(53) (ISS) 5 (26) S.(131)

Sterpellina sp. (26)

CeratopoSonidae (p).

Palpomyia compisa (Palpouria sp., Sessis sp., 5,(131)

8. ,

5 8.(815) 5 S.(667) S S.(1262) .S.(53) { }

Probeasts sp., Johoamaeasuria sp.) D Dasyhe h spp. (210) 5.(53) S. (237) (26) 8 (26) 8.(26) f Alluaudemyta spp. (I9) -

Chaoborus gunctlpenals S.

Decetta spp. S.

Polycentropus opp. S (26) S,(26) 5 j O oxvechira spp. S. A

.h Baetidae Caents spp. S.

S.

Henamenta app. S.(158) 8 g, Comphus opp.

[

g, Argia spp. S.

S. U N Statis spp. S. S.(26)

N Nydrophorus opp. S.

age f2 Table 1.3.5-3 (Cont) 606.0 i ,c.tte.e 604.0 F M A N Ta,a M & N F

53 26

- Tipultdae 26 geuscidae (1)

Coleoptera (p) S,(105)

Ilydrachnellae (26) 8.(5102) S,(473) 8.(2209) 8,(4865) 8 8,(4050) S.(105)

+

oliSochaeta 8, +

Ealdidae +

M spp. S.

+

3Arcteenais variabille lomondi S. S+

Lurbriculus wartenstus S+ S.+ S.+

+

Tuttitcadae +-

tir.nodriiue_ spp. +

S,+

+ S.+ +

[tenodrttue hoffmeister1 + S.

+ +

Sothrtoneurum voldovskream Autodritue linnobius S,(26) (26) (26) 8, (79) (26)

"Eeeatoda S. S.

+ S, Eenertina S,(53) 8 S.

3,(79) (26)

H Frostoma app. 8 (I'44)

, 3 (79) S. S.

'g relecypoda (53)

Corbicula app. S. 26 Castrepoda + +

.En +

rectinatetta meanifica 42}6 420

$ 7262 1235 6839 235 84 WS 2264 918 216 1670 M2 Haan number orSe tems/n 2538 234 1133 34 14 IS 24 20 uet yess ht (eS/e ) 19 22 28 Total Number of Tasa (1) = 1arvae (p) " pupee

+ = Indicates presence la Srab eemples.

(w)

PP9)

O 2:

(co) w

~

c-C -&

C' m

\f

Table 1.3.5-4 .

Density (inean no./2.4 of benthic macroinvertebrates collected with a modified Petersen grab in the sublittoral zone of Lake Hartwell, 1977.

! Tama locatione 604.0 606.0 F M A N F M A N Chironoeidae 13 39 Chironomidae (P) 39

-Ablabessvla aspera 13 39 13 Ablabesuvia e111ochi 26 Ablabess:sta annulata 13

.Cceletanvpus concinaus 13

' Cceloranypus tricolor 65 52 13 CoelotanYous scapularis 65 169 52 65 130 65 26 ProclaJius spp. 13 13 Procladius (Psilotanypus) bellus 78 13 52 13 13 Procladius (Procladium) spp. 26 13 Cricotopus sp. 26 Parakiefferiella spp. 52 heetrocladius sp. 13 273 156 13 Chironomus sp. 13 13 Jr: rtochirocomus sp. 39 Dierotend g sp. 26

,H ' h asttella sp. 143 39 39 y Cladopelma sp. ,

65 13

. Pseudochironomus sp. 13

) U 5tictochiremus sp. 13

.h w

Polypedilum (Tripodura) grp.

Tan > tarsus sp.

26 13 13 Mitrossectra sp. 26 Palponyta complex (Palpoeyla sp., 52 13 26 390 364 13 169 Besa t a sp., Probera ta sp., Johammessomsta sp.) ( .h Chaoborus punctipennis 26 416 91 13 26 3/

Decette opp. 26 26 Hemeaenia spp. 39 26 39 E' 2hus sp. 13 Hydrachnellae 13 Oligcchaeta 91 208 13 1.1 858 949 845 117 Naididae +

! Cats pseudobtusa +

Q corcaunis stylaria lacustris + + + + =

lubtficidae + + + + -

Autodritus piquett +

Aglodritus linnobius +

+ "

L!rnodritus spp.

Lienodritus hoffmeistert +

g L i r.:1odr h udekemismus + + >

g

~g 5.snrioneirum vejdovskyanus C/3 bematoda 26 39 13 13

+ h Neuereina p Prostoma opp. 39 13 13 39 91 PJ Pelecypoda 169 403 325 13

]

4 Corbicula spp. 39 65 221 39 13

-l 6

6 ___________ _ _ _ _ _ _ _ _ _ . _ _ _._ _ _ ___ ___ _ __ _ ______ _ __ _ _ _ _ _ . _ _ _ _ _ .

Page 2 of 2 Table 1.3.5-4 (Cont) .

lac gg ,

Tasa y M A N

1. A N

+ +

Pectinstella saamifice 260 2353 2093 1040 494 1 819 M2 598 1173 88,697 15.858 674 3096 temas number Wet i.eight orga9)ese/n (as/s 813 1953 349 10 21 18 13 11 18 13 9 Total Number of Tasa 29 20 8 19.5 28.5 21 Botton Temperature (*C) 7 -

0.73 0.54 0.85 0.87 0.80 0.39 0.84 i= (Diversity) 1.94 0.11 0.43 0.70 0.52 0.34 0.42 0.87 0.17 a = (amaandansy)

(p) = papes

+

• 1adicates pra==="" la greb esmples, f

'N

~

(ca) 0 a) h?-SI GE@

W .

Lora).

em

'JEE3

" W e

t ___-. . _ _ >

l i

soooo E o ar teet 's

• C3 stemmas cree (more's sooo -

. M m ,< w .*,

) -

C J .. . c,.,i ,.r.

sooo sooo .

j  :

~

~

l -

i 100 loo -

i t

sol see so, ses soo see no nur i Aue nov Figure 1.3.5-1. Mean density (no./m2 ).and standing crop (mg/m2 ) of benthic macroinvertebrates in Late Keowee littoral zones in 1977, by location and sampling period.

)

l

) l - \

, i t, ,

c .

f.

g

~.

=

i gi  :

. . m, _

. e s,

=

- 0 .

- 0 0

3 , -

_ s m

I

)

'm M

1. . e

(

/

e e

s y

C' s, a. o m .t p

e n

e W

r

e p

. g E n 1

. 1

. zp

. o,

.: g

'  ; l ) ,: '

3500 Sol.o

.. SO2.0

. . . . 504 o 3000 .

esoo ,

2000 -

i800 .

e .

1000 , *

• soo l

• n'. .. .

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1.3.5-17 ONS 12/77

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1.3.5-19 ONS 12/77

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a

l 1.4- FISH IMPINGEMENT 03 INTAKE SCREENS AND ENTRAINMENT OF FISH EGGS AND LARVAE' Specification: A. A detailed analysis of fish impinged _upon the intake screens of the Oconee Nuclear Station shall be conducted by species,-

size and number and weight each time one or more intake screens are pulled due to reduced pumping efficiency of the associated condenser cooling water pumps. Quarterly, an inspection.of six intake screens (two from each unit) will be performed. The screens to be inspected will be cleaned one week prior to inspection so that the rate of fish im- ,

pingement during the week can be determined. A detailed l analysis of the fish impinged shall be conducted by species,

' size and number and weight. The data collected from these inspections will be recorded in tabular form (Duke Power ,

Company, 1973a).

I. INTRODUCTION Fish fmpingement at Oconee Nuclear Station has been discussed previously in the Oconee Nuclear Station Reports (Duke Power Company,1973b,1977).

II. METHODS AND MATERIALS l Unscheduled Screen Inspections Methods and materials for inspection of screens pulled because of reduced pumping efficiency due to build up of trash have been discucsed previously 3 (Duke Power Company, 1973b, 1974). Data collected included: species, i numbers, estimated lengths, and weights.

Quarterly Screen Inspections

~

Methods and materials for quarterly screen inspections have been discussed previously (Duke Power Company, 1975a, 1976). Data collected included:

species, numbers, estimated lengths, weights, water temperatures (surface and bottom), auul dissolved oxygen concentrations at the intake structure.

III. RESULTS AND DISCUSSION Unscheduled Screen Inspections A total.of fifty-three screens were pulled in 1977 due to a build up of trash on the screen surface. A total'of 10,106 fish were impinged on these screens. _ Species, numbers and percent abundance of identifiable fish were: threadfin' shad (Dorosoma petenense), 4920 (97.3%); yellow

-perch (Perca flavescens), 131 (2.6%); and bluegill (Lepomis macrochirus),

3 (0.1%), respectively. _A total-of 5052 fish were unidentifiable due to extreme decomposition. A summary _of data for the above screen inspections is presented in Table 1.4-1.

Quarterly Screen Inspections During the first quarterly. screen inspection of'1977,. conducted on February

'0NS'12/77 1.4-1:

18, a total of 7081 fish were impinged on the six screens inspected (Table 1.4-1). All but one, a bl,ack crappie (Pomoxis nigromaculatus),

were threadfin shad. The impinged fish weighed 28.07 kg for an average of 4.0 g per fish. Size distribution of impinged fish were: 2-4 cm (57.2%); 4-6 cm (38.1%); 6-8 cm (4.7%); and 3,10 cm (< 0.1%).

On May 24, the second inspection, a total of 136 fish were impinged (Table 1.4-1). Species, numbers and percent abundance of identifiable impinged fish were: yellow perch, 68 (58.1%); bluegill, 48 (41.0%); and thread-fin shad, 1 (0.9%), respectively. A total of 19 fish (14% ofThe total fish impinged impinged) were unidentifiable due to extreme deccmposition.

fish weighed 1.16 kg for an average of 8.5 g per fish. Size distribution of impinged' fish were: 4-6 cm (30.9%); 6-8 cm (58.8%); 8-10 cm (8.8%);

j '

and 3,10 cm (1.5%). ,

On September 16, the third inspection, a total of 72 fish were impinged

(Table 1.4-1). All fish observed impinged were unidentifiable due to extreme decomposition. The impinged fish weighed 0.29 kg for an average of 4.1 g per fish.' Tha two size groups of impinged fish were 6-8 cm (98.6%) and 3,10 cm (1.4%).

On December 19, the fourth inspection, a total of 2549 fish were im-pinged (Table 1.4-1) . Species, num'bers, and percent abundance were:

i threadfin shad, 2537 (99.6%); and miscellaneous identifiable fish, 12 (0.4%), respectively. The impinged fish weighed 7.07 kg for an2-4 average cm of 2.8 g per fish. Size distribution of impinged fish were:

I

' (21.2%); 4-6 cm (68.9%); 6-8 cm (8.0%); 8-10 cm (1.8%); and 3,10 cm (0.1%).

Figure 1.4-1 illustrates the average numbers of. fish impinged per day pro-jected for the station and the associated water temperatures in the intake canal. The numbers of fish impinged per day were determined by multiplying the totals for the six screens' inspected by four to represent a station total and then dividing by seven, the number of days in the inspection period. The numbers of threadfin shad impinged were highest in February l (4045 fish per day) when water temperatures were lowest while the numbers of threadfin shad impinged were lowest in September (0 fish per day) when l

water temperatures were highest. The susceptibility of threadfin shad to low water temperatures has been well documented (Parsons and Kimsey,1954; Strawn, 1965). Other identifiable fish, primarily small numbers of yellow perch and bluegill, were most commonly impinged in the spring.

l l IV.

SUMMARY

AND CONCLUSIONS The number of fish impinged in 1977 follow the seasonal trends exhibited in 1975 and 1976 (Duke Power Company,1975a,1975b,1976). During the-winter . months, aus intake water temperature decreases, the numbers- of thread-During fin shad (2-6 cm in length) impinged on the intake screens increase.

the remainder of the year, when intake temperatures .were warmer few thread-fin shad were impinged, however, small numbers of yellow perch and bluegill (4-8 cm in length) were impinged.

The numbers, kinds, and sizes of fish impinged.on the intake screens at Oconee Nuclear Station should not be detrimental to the fishery; resource

! 'S 12/77-1.4-2 1

I l

of Lake Keowee.

REFERENCES Duke Power Company. 1973a. Appendix B to Facility Operating License Nos.

DPR-38, DPR-47, and DPR-55, Technical Specifications fcr the Oconee Nuclear Station Units 1, 2, and.3, Duke Power Company, U. S. Atomic Energy Com-mission, Docket Nos. 50-269, 50-270, and 50-287 (revised April 9, 1976.

NRC), Washington, D. C.

Duke Power Company. 1973b. Oconee Nuclear Station. Semi-Annual Report.

Period Ending June 30, 1973.

. 1974. Oconee Nuclear Station. Semi-Annual Report.

Period Ending June 30, 1974. -

. 1975a. Oconee Nuclear Station. Semi-Annual Report.

Period Ending June 30, 1975.

. 1975b. Oconee Nuclear Station. Semi-Annual Report.

Period Ending December 31, 1975.

. 1976. Oconee Nuclear Station. Annual Report. Period Ending December 31, 1976.

. 1977. Oconee Nuclear Station. Environmental Summary Report.

1971-1976.

Parsons, J. W. and J. B. Kimsey. 1954. A report on the Mississippi threadfin shad. Prog. Fish Culturist. 14 (4): 179-181.

Strawn, K. R. 1965. Resistance of threadfin shad to low temperatures. Proc. 19th Ann. Conf. S. E. Assoc. Game and Fish Comm. pp. 290-293.

l l

j 1.4-3 ONS 12/77

l.4 FISH IMPINGEMENT ON INTAKE SCREENS AND ENTRAINMENT OF FISH EGGS ANl LARVAE Specification: B. The entrainment of fish eggs and larvae in the cooling water system shall be monitored biweekly (every other week) during the major spawning period of April through July and an estimate made of the total number of fish eggs and larvae

)

entrained and their survival.

C. If the quantity or type of fish, or their eggs or larvae,  ;

is determined to be of significance or to have a significant detrimental impact on the propagation of fish of recreational importance, then plans for corrective action will be developed (Duke Power Company,1973a) . .

I. INTRODUCTION The effects of entrainment of fish eggs and larvae have been discussed pre-viously (Duke Power Company,1973b and 1977).

II. METHODS AND MATERIALS The Condensar Cooling Water (CCW) system at ONS was sampled at least bi-weekly (once every two weeks) for entrainment of fish eggs and larvae during the months of April through July. The sample procedure remained the same as discussed previously (Duke Power Company, 1973b, 1975a, and 1977).

Supplemental sampling was carried out in the ONS intake canal weekly during the same period. This sampling consisted of two samples, one collected A 500 from the surface and one collected at a depth of five (5) meters.

micron nylon mesh net was towed behind the boat for two 15 minute periods at each depth.- Simultaneously, a second net was suspended in the opening of the skimmer wall at a depth of 23 meters for a period of .approximately one hour. A flow meter, attached to each net, was used to calculate volmses of water sampled. In addition, temperature and dissolved oxygen profiles were determined weekly at the shimmer wall.

III. RESULTS AND DISCUSSION The results of the fish eggs and larvae entrainment sampling in the CCW Samples ranging in volume from system3 are summarizgd in Table 1.4-2.were collected from the Unit 1 pre-condenser out 6.82 m to 216.58 m No fish eggs or larvae were collected du*ing any of the thirteen sample periods.

Table 1.4-3 summarizes the supplemental sampling conducted in the DNS in-take canal. A total gf 50 larval 5 vs were e nducted with sample volumes ra ;.og from 273.84 m to 659.76 m . Sixteen (16) samples were collected fromtheopeginginthesgimmerwallwithvolumesofwatersampledranging from 79.84 m to 219.10 m . No fish eggs or larvae were collected from the sampling in the intake canal.

-IV.

SUMMARY

AND CONCLUSIONS The collection of one fish larvae and no fish eggs in the CCW system from 1.4-4 ONS 12/77

1973 through 1976 and the absence of any fish eggs and larvae collected in 1977 clearly shows entrainment at ONS to be minimal. Based upon the supplemental sampling of water flowing into the intake canal, it is ap-parent that the skimmer wall acts as a barrier to entrainment of fish eggs and larvae and limits passage to those fish eggs and larvae found at the depth of the skimmer wall opening. It is also apparent that based on the low numbers cf fish eggs and larvae collected, (two fish larvae in the past five years), in the intake canal that reproduction of fish in-habiting the intake canal is minimal. Therefore, the entrainment of fish eggs and larvae caused by the operation of ONS has not had a measurable impact upon the fishery resource of Lake Keowee.

REFERENCES Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR- -

38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Com-mission, Docket Nos. 50-269, 50-270, and 50-287 (revised April 9, 1976, NRC), Washington, D. C.

Duke Power Company. 1973b. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1973.

. 1975. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30, 1975.

. 1977. Oconee Nuclear Station. Environmental Summary Re-port. 1971-1976.

l l

1 l

1.4 ONS 12/77

l Table 1.4-1. Summary of fish impingement data by screen inspection date, 1977.

L Page 1 of 6 l

DO TEMP SCREEN WFI NFI SPECIES COMPOSITION SIZE GROUPS (cm)

DATE (kg) # BG YP TS U M 2-4 4-6 6-8 8-10 10 + mg/l (*C) 0 0 1610 0 0 0 910 700 0 0 01/31/77 2A1 6.40 1610 500 75 0 2A2 3.90 950 0, 0 950 0 0 0 375

~~

0 0 2560 0 0 0 1285 1200 75 0

/rAL 10.30 2560 3100 0 1000 3100 0 0 0 s-6.5 02/11/77 ' 1A1 16.00 4100 0 0 1000 0 5 1420 2800 0 1300 2800 5 120 0 11.2 b-6.4 1A2 16.50 4225 1080 0 0 525 360 195 0 0 2A1 4.25 108C 0 0 1260 0 0 625 550 87 0 0 2A2 5.15 1262 0 2 99 0 0 0 99 3 0 0 3Al .0.51 102 0 3 0 0 0 0 101 3 0 20 84 0 F 3A2 0.50 104 0

10873 0 10 4960 5903 0 3470 6993 290 120 7 TOTAL 42.91

'* 0 0 980 0 0 425 400 155 0 0 02/18/77 1A1 3.90 980 s-6.8 0 0 1375 0 0 900 475 0 0 0 11.5 b-6.6 1A2 5.50 1375 0

0 0 1475 0 0 875 550 50 0 2A1 5.75 1475 0

1000 0 0 450 450 100 0 2A2 4.00 1000 0 0 0 0 1150 0 1 825 325 0 1 0 3Al 4.72 1151 0

0 0 1100 0 0 575 500 25 0 3A2 4.20 1100 0 0 7080 0 1 4050 2700 330 1 0 TOTAL 28.07 7081

• Quarterly Inspection- Screens pulled 7 days prior, cleaned, returned and fish and debris allowed to accumulate for a seven-day period.

Screen # - Represents Condenser Cooling Water (CCW) intake screen; two sets of screens for each CCW pump.

gj WFI - Represents the weight of fish impinged (kgs).

u2 NFI - Represents the number of fish impinged.

[- Species Composition - BG = Bluegill; YP = Yellow perch; TS = Threadfin shad; U = Unidentifiab)::

M = Miscellaneous.

U Temp. - Represents the lake temperature in the intake canal: a = surface, b = bottom.

Table 1.4-1 (Cont.). Summary of fish impingement data by screen inspection date, 1977.

Page 2 of 6 DATE SCREEN WFI NFI SPECIES COMPOSITION SIZE CROUPS (cm) DO TEMP

1. (kgs) # BG YP TS U M 2-4 4-6 6-8 8-10 10 + (mg/1) (*C) 03/03/77 2C1 1.12 490 0 10 5 475 0 0 455 35 0 0 2C2 4.80 850 0 0 0 850 0 0 275 375 200 0 TOTAL 5.92 1340 0 10 5 1325 0 0 730 410 200 0 _

03/16/77 3B1 3.80 1075 0 25 0 1050 0 0 1050 25 0 0 3B2 4.70 1133 0 0 0 1133 0 0 1125 0 0 8 TOTAL 8.50 2208 0 25 0 2183 0 0 2175 25 0 8

• 04/04/77 3B1 0.02 6 0 0 0 6 0 0 6 0 0 0 f 05/03/77- ID1 1.50 375 0 0 0 375 0 0 375 0 0 0

-J 1D2 0.41 100 0 0 0 100 0 0 100 0 0 0 TOTAL 1.91 475 0 0 0 475 0 0 475 0 0 0 05/06/77 1A1 2.20 205 0 75 0 130 0 0 125 75 0 5 1A2 4.20 781 0 0 0 781 0 0 550 225 0 6 TOTAL 6.40 986 0 75 0 911 0 0 675 300 0 11 05/17/77 1A1 0.20 21 0 0 0 21 0 0 5 15 0 1 1A2 0.29 45 45 0 0 0 0 0 8 33 4 0 8.6 s-14.0 o 2A1 2.50 490 0 0 0 490 0 0 50 400 0 40 b-13.6

$ _2A2 2.80 420 0 0 0 420 0 0 75 325 0 20 g 3Al 2.10 465 0 0 0 465 0 0 380 85 0 0 Q 3A2 0.63 210 0 0 0 210 0 0 210 0 0 0 0 TOTAL 8.52 1651 45 0 0 1606 0 0 728 858 4 61 Y

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Table 1.4-1 (Cont.). Summary of fish impingement data by screen inspection date, 1977.

Page 6 of 6 DATE SCREEN WFI NFI SPECIES COMPOSITION SIZE GROUPS (cm) DO TDIP

1. (kgs) # BG YP TS U M 2-4 4-6 6-8 8-10 10 + (mg/1) (*C) 12/06/77 2C2 0 0 0 0 0 0 'O O O O O O 12/12/77 1A1 0 0 0 0 0 0 0 0 0 0 0 0 1A2 0 0 0 0 0 0 0 0 0 0 0 0 9.4 s - 13.5 2A1 2.60 1031 0 0 0 1051 0 800 200 50 0 1 b - 13.5 2A2 1.50 760 0 0 0 760 0 600 150 10 0 0 3Al 1.50 770 0 0 70 700 0 420 350 0 0 0 H 3A2 1.10 551 1 0 0 550 0 350 200 1 0 0 p TOTAL 6.70 3132 1 0 70 3061 0 2170 900 61 0 1 H

• 12/19/77 1A1 0.15 108 1 0 105 0 2 12 86 10 0 0 1A2 0.07 47 0 1 45 0 1 10 36 1 0 0 9.4 s - 12.7 2A1 3.30 815 0 0 815 0 0 200 500 100 15 0 b - 12.8 2A2 1.14 517 0 0 517 0 0 50 430 27 10 0 3Al 1.20 531 0 1 530 0 0 120 350 50 10 1 3A2 1.21 531 0 6 525 0 0 150 355 16 10 0 TOTAL 7.07 2549 1 8 2537 0 3 542 1757 204 45 1

-O m

H 0

Table 1.4-2. Susunary of entrainment of fish eggs and larva [within the ONS Condenser Cooling Water System for April through July,1977.

[

SAMPLE SAMPLE # FISH ENTRAINED INTAKE DISCHAR'GE CCW PUMPS DATE' TIME DURATION VOLUME (m )

3 ytog (,3/ min) EGCS LARVAP.

HOURS TEMP (*C) TEMP (*C) OPERATING (f) 0.08 0 0 24.0 10.5 21.4 2 190.05 4/06/77 0905 0.12 0 0 24.0 10.6 21.8 3. 179.93 4/13/77 0900 0.13 0 0 24.5 11.4 22.4 3 194.81 4/20/77 0900 0.13 0 0 24.5 11.8 21.4 3 194.80 4/27/77. 0845 183.68 0.12 0 0 5/04/77 0845 24.5' 12.5 24.1 3 '

g 0 0 1 174.50 0'.12 5/11/77 0830 24.0 ~ 12.6 12.8 7 1 6.82 0.11 0 0 5/17/77 0930 1.0 13.0 1 '4. 0 M 8.50 0.14 0 0 14.4 3 6/01/N 0920 1.0 'd.4 0.15 0 0 1.0 15.3 26.3 3 9.09 6/15/77 0945 0 0 16.6 27.5 3 168.68 0.13 6/29/77 0830 22.5 185.35 0.13 0 0 7/07/77 0845 24.5 17.4 24.0 3 0.15 0 0 23.8 18.9 28.8 3 216.58 7/20/77 0845 204.46 0.14 0 0 7/28/77 0840 24.0 19.2 29.6 3 a

m N

b~

{

Table 1.4-3. Summary of sampling for fish eggs and larvae in the ONS intaka canal from April through July, 1977.

DATE SURFACE TOWS 5 METER TOWS SKDOER WALL _

AVC. VOL. # FISH AVG. VOL. # FISH * .VOL. # FISH 3 3 3

• - (m ) -

EGGS LARVAE (m ) EGGS ' LARVAE (m ) EGGS LARVAE 4/06/77 546.24 0 0 563.93 0 0 192.63 0 0 4/12/77 531.77 0 0 545.49 0 0 1,40.37 0 0 4/19/77 567.07 0 0 502.78 0 0 139.62 0 0 4/26/77 567.64 0 0 395.23 0 0 138.81 0 0 5/05/77 51P.74 0 0 588.54 0 0 219.10 0 0 F 5/12/77 529.56 0 0 502.02 0 0 131.41 0 0 y 5/18/77, 480.11 0' O 487.02 0 0 132.47 0 0 Fe

" 5/24/77 545.89 0 0 534.06 0 0 203.54 0 0 6/01/77 563.66 0 0 423.68 0 0 145.85 0 0 6/07/77 536.07 0 0 * - - -

94.25 0 0 6/16/77 611.10 0 0 - - -

86.09 0 0 6/21/77 563.76 0 0 - - -

85.02 0 a 6/28/77 538.82 0 0 - - -

83.07 0 0 7/05/77 567.04 0 0 - - -

84.17 0 0 7/19/77 562.32 0 0 - - -

84.25 0 0 7/26/77 557.90 0 0 - - -

79.94 0 0 8

[.

q

• Volumes measured for the skimmer wall are approximations-flow meter inaccurate at low velocities.

U

• Sampling deleted.

1 i

s TOTAL FISH THREADFIN SHAD OTHER 10ENflFIA8LE FISH TEMPERATURE

--24 4000 - .

\

O

• 4 cc E \ -

-18 .G 3000- - g ~

O W e \ -

o e N 3 \ e a

a \ a m 1 - -12 0 2000- - \-

. a \

i \

! --6 5MO- -

/

\ 1

\ /

l /

\

\

/

\

o ._ ....= u::: A:um:h /

_ t__ __ _. _ o i

5/24 9 /16 12/19 2/18 C'JARTERLY SCREEN IN3PECTION DATE Pigure 1.4-1. . Seasonal fish 1:npingement rates as determined by

' the quarterly screen inspections.- Values were computed by multiplying the totals of the screen inspections by four for a station total and then dividing by seven, the number of days in the in-spection period of 1977.

1,4- 14 ONS 12/77-

i 1.5 PHYTOPLANKTON-ZOOPLANKTON ENTRAINMENT MORTALITY STUDY I Specification: At least 6 times per year water samples will be collected by either plankton nets or pumps at the condenser cooling water systems intake and at the heated water discharge before it enters the receiving water. Samples will be analyzed for types, quantities and survival of the various planktonic groups. Sampling will be such to encompass the range of temperature rises across the condenser (e.g., 16*-28'F)

(Duke Power Company 1973a). l I. INTRODUCTION

~

The effects of entrainment in condenser cooling water on planktonic organisms have been discussed previously (Duke Power Company 1973b, 1977).

l II. METHODS AND MATERIALS '

l Previously described methods and materials were used in 1977 (Duke Power l Company 1977) except for the following amendments: l l

Phytoplankton Entrainment Phytoplankton samples were collected on six occasions during 1977 from  !

two locations at ONS, the intake (530.0) and the postcondenser (530.6).

In this report, as in the ONS Environmental Summary Report (Duke Power Company 1977), assimilation ratios (the rate of production per unit of chlorophyll) were used to estimate algal metabolism. Thermal effects were tested by comparing the heated intake ratios to the ambient intake l ratios. Mechanical effects were tested by comparing the heated post- '

condenser ratios to the heated intake ratios. Total plant effects were l analyzed by a comparison of the heated postcondenser metabolism to the I ambient intake ratios.

Phytoplankton density, biovolume, chlorophyll concentrations, and assimilation ratios were all analyzed by a two-factor analysis of variance (ANOVA) to determine significant differences (pf0.05) between locations and dates (Keppel 1973). When interactions occurred in an ANOVA, a simple main effects test was applied to separate differences between samples (Keppel 1973). All statistical testing was performed by means of the Statistical Analysis System computer programs of Barr et al.

(1976).

Zooplankton Entrainment I Regular entrainment studies were conducted in January, March, May, July, October, and November of 1977. In conjunction with the March 16, 1977 '

regular entrainment study, zooplankton immotility and damage were assessed at an open lake location (502.0).. Duplicate samples were collected with a 0.5 m net towed from ten meters to surface (10-s) and bottom to' surface (b-s). Immotility and' damage analyses were performed 1.5-1 ONS 12/77

utilizing the same methods as for the intake (509.5) collections. The purpose of this study was to compare immotility and damage in the lake with those values found in the intake canal.

Data Analyses Spearman's rank correlation coefficient, a non-parametric measure of '

association, was calculated to determine which variables could be possible effectors of zooplankton immotility and damage. Friedman's test, a non-parametric analysis of variance, was used to test percent immotility and damage data for differences among sample periods and between locations (pf0.05). Friedman's test and Spearman's coefficient were calculated -

using procedures in SAS 76 (Barr et al. 1976).

III. RESULTS AND DISCUSSION j

Phytoplankton Standing Crops 3

Mean density estimates were the highest in July (438 X 106 units /m ) with similar values during March and November (Table 1.5-1). The lowest mean density occurred in May (141 X 10 6 units /m3 ). Baci11ariophyceae was the dominant class in 67% of the samples, Chlorophyceae in 17%, and an i

unidentified taxon in 17% (Figures 1.5-1 and 1.5-2). Typical dominant green algae were Monoraphidium setiforme and coccoid greens. Dominant diatoms were Melosira distans var. A, Synedra sp. A, and Melosira italica var. tenuissima (Appendix B, Section 4).

3 3 4

The highest mean biovolumes were found in November (430 mm /m ), although, like the densities, relatively high biovolumes were also observed during March and July (Table 1.5-1). The lowest mean biovolume was in January 3 ). Algal biovolumes were dominated by Bacillariophyceae (110 mm3 /m (primarily Rhizosolenia eriensis, Synedra sp. A, Melosira italica var.

tenuissima, and Tabellaria fenestrata) in 58% of the samples and by Dinophyceae (primarily Peridinium deflandrei, P. wisconsinense, and P. inconspicuum) in the remaining 42% (Figures 1.5-1 and 1.5-2; Appendix B, 3ection 4).

The dominant classes were the same as was reported in the ONS Environmental Summary Report-(Duke Power Company 1977). The presence of Myxophyceae j continued to be of minor importance since blue-greens were never observed

(

l to comprise over 4% of the density or 1% of the biovolume.

The results of the two-factor ANOVA's on density and biovolume (Table 1.5-2) showed no significant differences between the intake and the.

postcondenser locations. This indicated that ONS operation had no effect on phytoplankton densities and biovolumes as was previously reported in the ONS Environmental Summary Report (Duke Power Company 1977). There were significant differences between sampling dates due to seasonal periodicity of the phytoplankton. .This was also consistent with the trend observed in the ONS Environmental Summary Report (Duke Power Company 1977).

1.5-2 ONS 12/77

, - , - _ . - ir

The mean chlorophyll concentrations ranged from a high of 1.36 mg/m3 in January to a low of 0.7 mg/m3 in July (Table 1.5-1). Trends in chlorophyll concentrations appeared to differ from those of biovolume and density; however, the magnitude of the differences in chlorophyll concentration was so small that it was difficult to recognize a definite seasonal trend in the data.

An ANOVA of the chlorophyll data showed significant differences between the intake and the postcondenser on all of the dates sampled (Table 1.5-2).

The postcondenser had higher chlorophyll concentrations on five of the dates and lower concentrations in January (Table 1.5-1). Chlorophyll data showed no consistent pattern with respect to temperature increases in the Condenser Cooling Water (CCW) System, nor with the ambient intake .

temperature. Since biovolume and density did not show similar trends, the chlorophyll concentration differences were probably due to natural variation (patchiness) in the intake water. Also, the low chlorophyll concentrations were subject to higher analytical error.

Phytoplankton Metabolism Mean assimilation ratios of the two locations were highest in November (0.65 mgC/mg chlorophyll /hr) and lowest in July (0.17 mgC/mg chlorophyll /hr)

(Table 1.5-3). The variability was due to seasonal periodicity of the phytoplankton. The same seasonal pattern occurred in 1976 (Duke Power Company 1976).

Thermal, mechanical and total plant effects were analyzed by a two-factor ANOVA (Table 1.5-4). Results indicated there were no significant mechanical effects evident in 1977. Location-date interactions occurred in the thermal and total effect analyses. A simple main effects test isolated the dates on which there were significant thermal and total effects. In January, the thermal elevation caused a 470% stimulatory effect and a total stimulatory effect of 760%. These effects appeared to be large because the control intake assimilation ratio was relatively low (0.10 mgC/mg chlorophyll /hr) as compared to previous years (Figure 1.5-3), and even -

a small metabolic increase in the heated intake or heated postcondenser sample would result in a large percentage increase. The intake tempera-tures, AT's, and flow rates at ONS were very similar during January and March 1977 (Figure 1.5-4); however, phytoplankton metabolism was signifi-cantly stimulated during January but not during March. The phytoplankton entering the CCW System in January might have been in better physiological condition than in March, which would result in a greater response to thermal elevations. In November, although there were no significant thermal or mechanical effects, the total passage effect caused a 45%

inhibition of phytoplankton metabolism. Again, due to lake mixing, the physiological state of the algae drawn into the intake from bottom waters was probably better than during months _of stratification, so the phyto-plankton responded to CCW System passage. During thermally stratified periods of the year, the phytoplankton were in the aphotic zone of Lake Keowee for a longer period of time and were probably in very poor con-dition, as indicated by lower photosynthetic efficiencies.

1.5-3 ONS 12/77

The previous three years showed no significant thermal, mechanical, or total station effects on entrained phytoplankton when all the data were analyzed together (Duke Power Company 1977). Ingl977, tota" station effects caused an increase in assimilation ratios (fr'om 0.10 mgC/mg chlorophyll /hr to 0.86 mgC/mg chlorophyll /hr) and a decrease in November (from 0.87 mgC/mg chlorophyll /hr to 0.48 mgC/mg chlorophyll /hr) (Table 1.5-3).

Zooplankton Entrainment: Assessment of Immotility Data for each study date including taxa observed, time of sampling, number of organisms observed, volume filtered, percent immotile, and -

corrected percent immotile (CPI) are presented in Appendix B, Seccian 5, pp. 173-201. Negative CPI values resulted when the percent of immoaile organisms at the postcondenser or discharge was lower than the percent of immotile organisms at the precondenser or intake, respectively.

Immotility should not decrease as a result of passage of organisms through the condenser system. Negative CPI's were, therefore, probabl;'

a result of sampling error and/or variations in subsampling and were assumed to be zero.

Eight major taxa or life stages comprised 95% to 99% of the total Crustacea entrained on all sample dates (based on standing crop values at Location 509.5 taken one day prior to or one day after entrainment sampling, Appendix B, Section 3, pp. 37-61). Three of the taxa were Cladocera and five were Copepoda.

The three major Cladocera taxa (Bosmina coregoni, Diaphanosoma leuchten-bergianum, and Daphnia ambigua) comprised the majority of total Crustaces entrained during January, March, and May sample dates, representing 63.7%, 52.5%, and 62.4%, respectively, of the total Crustacea. Bosmina coregoni was the dominant cladoceran on all sample dates with Diaphanosoma leuchtenbergianum and Daphnia ambigua being second and third in abundance.

The five major Copepoda taxa or life stages (nauplii,.cyclopoid copepodid, calanoid copepodid, Diaptomus mississippiensis, and Tropocyclops prasinus) comprised the majority of total Crustacea entrained on July, October, and November sample dates, representing 73.7%, 77.9%, and 52.4%, respective 1';,

of the total Crustacea. Nauplii were the most abundant with cyclopcid copepodid, calanoid copepodid, Diaptomus mississippiensis, and Tropocyclops prasinus following from high to low in order of numerical abundance

' Appendix B, Section 3, pp. 37-61).

J The condenser CPI values (Figure 1.5-5) were greatest for Cladocera in March (ECPI = 27.2) and for Copepoda and total Crustacea in May Intake-discharge CPI values )

i (ECPI's = 4.6 and 6.5, respectively). l were greatest for Cladocera in October (XCPI = 7.9) and for CopepodaThe and l total Crustacea in November (XCPI's.= 7.9 and 6.5, respectively).

data appeared to exhibit a seasonal trend, i.e., greater CPI values occurring primarily during the stratified months of the year.

ONS 12/77 1.5-4 t

l

! l

1 l

) Major percent immotility peaks (Fr.gures 1.5-6 and 1.5-7) occurred ducing i

stratified months (March, May, and July). The results of Friedman's test revealed no significant differences (p50.05) in percent immotility among

, sample dates or between sample locations for Cladocera, Copepoda, and

. total Crustacea.

~

l Data indicating percent immotility of total number of organisms observed in 1977 are presented in Table 1.5-6. These data were variable between locations, but indicated that passage through the ONS Condenser Cooling c~.:ce lad a minimal effect on the crustacean zooplankton 1

Spearman's rank correlation coefficients were significant (p50.05)

between precondenser total Crustacea immotility and both intake and pre- ~

l condenser temperatures. Cladocera immotility was not significantly correlated with any of the physical-chemical variables (Table 1.5-7).

Discharge Copepoda and total Crustacea immotility correlated (p50.05) l with intake and discharge temperatures. These data suggest that at higher acclimation temperatures the Crustacea were more susceptible to the stresses which render them immotile. This supports conclusions I

stated previously (Duke Power Company 1977). Intake percent' immotility j

for Cladocera, Copepoda, and total Crustacea did not correlate with factors tested that might affect it (Table 1.5-7).

j

. The final temperatures to which the zooplankton were exposed during this study (Figure 1.5-8) are not lethal to most microcrustaceans (Goss and i Bunting 1976, Bunting 1974, and Brown 1929). These results were >

the same as those reported previously (Duke Power Company 1977).

The open lake.(Location 502.0) study of March 1977 was conducted to further investigate the hypothesis that organisms in the deeper strata

.of the lake may exist there as a result of their inability to maintain vertical position due to injury, age, and/or other stresses. Those j animals in the deeper water (>20 m) at Location 502.0 vere more likely to 4

be entrained through ONS cooling system. Data from the open lake j analyses (Figure 1.5-9) indicated that total Crustacea immotility at

] Location 502.0 was greater.in the bottom-to-surface samples than in the j ten-meter-to-surface samples (X % immotile = 2.8.and 1.8, respectively).

Immotility in the lower depths was probably greater than 2.8% but was

. biased by the inclusion ~of organisms in the upper 10.m of the water '

column. This hypothesis was supported by the comparatively high immotility for. total. Crustacea in the' intake canal'(ll.6%~1mmotile) on the same date. ~ The data indicated _that a; greater percentage'of the organ-isms are immotile in- the lower. depths of the ' lake -than in the upper strata.

Results of this' study were basically.the same as those' reported previously.

(Duke Power-Company 1977).-

Zooplankton Entrainment: -Damage Analyses-1

Percent damaga at precondenser and postcondenser was lowL(<5% in most 1 cases) and:quite variable (Figure 1.5-10). ~ Percent damage for the

~

I i

liS-51 ONS'12/77 Y

a_ -

major taxa was generally higher at the discharge than the intake (Figure 1.5-11). Highest percent damage was found during stratified months.

Friedman's ANOVA results indicated no significant differences (pf0.05) for percent damage (Cladocera, Copepoda, and total Crustacea) between  ;

intake and discharge, precondenser and postcondenser, or among collection dates. Spearman's correlati:n results for the major taxonomic categories indicated no significant correlations between percent damage and the l physical-chemical variables.

Table 1.5-8 presents the percent damage values for total organisms studied over the reporting period. These data indicate that damage .

encountered between locations was low, with the net damage for total Crustacea between intake and discharge being 1.4 percent. The net effect for this study period was neither statistically nor ecologically significant.

SUMMARY

AND C]NCLUSIONS Phytoplankton Entrainment

1. Phytoplankton entrainment studies were conducted on six dates in 1977. The studies involved measurements of density, biovolume, chlorophyll and assimilation ratios.

2. Algal densities were dominated by Bacillariophyceae, Chlorophyceae, and an unidentified taxon. Baci11ariophyceae and Dinophyceae dominated the algal biovolumes. Both observations were consistent with previous years.

3. Statistical analyses of biovolume and density data revealed the same results as reported previously. Neither biovolume nor density showed significant differences between the intake and the postcon-denser locations. Chlorophyll concentrations showed significant differences between the two locations, differing from prior data; however, since density and biovolume data were not consistent with chlorophyll, these differences were attributed to sampling and/or natural variability.

4. Assimilation ratios of entrained phytoplankton were not significantly In inhibited or stimulated by mechanical factors in 1977.

January, there were stimulatory thermal and total effects on phyto-plankton metabolism. In November, On the CCW passage had a total effect other four sampling dates, of inhibiting metabolism.

ONS.did_not have any significant effects on the metabolism of entrained phytoplankton.

Zooplankton Entrainment_

1. Copepoda _and total Crustacea percent immotile at the discharge The results correlated with discharge as well as intake temperatures.

indicated that immotility was associated with ambient temperature and the final teuperature to which the organisms were exposed.

'1.5-6 ONS 12/77

2. The AT's had little or no apparent relationship to immotility. The maximum temperatures to which the zooplankton were exposed during passage through ONS Condenser Cooling Water System were generally below thermal tolerance levels found in other studies.

3. Friedman's test results indicated that there was no significant difference between precondenser and postcondenser or intake and dis-charge locations for percent immotility and percent damage.

4. Although seasonal trends appeared to be present for percent immotility and percent damage, Friedman's test indicated no statistically signifi-cant differences among the collection dates.

5. A study of open lake (502.0) immotility and damage showed that immotility and damage was greater in the intake canal than at either 502.0 (b-s) or 502.0 (10-s), indicating that zooplankton in i the lower portion of the water column are immotile prior to induction into ONS.

6. Net immotility and damage percentages indicate that the entrainment '

effects on the zooplankton were small if not negligible.

7. Analysis of data collected during this reporting period yielded the same basic conclusions as those reported in previous years, l

l l

l 1.5-7 ONS 12/77

REFERENCES CITED .

Barr, A. J., J. H. Goodnight, J. P. Sall, J. T. Helwig. 1976. A user's guide to SAS 76. Sparks Press, Raleigh, N.C. 329 pp.

Brown, L. A. 1929. The natural history of cladocerans in relation to temperature. I. Distribution and temperature limits for vital activities.

Am. Nat. 63: 248-264.

Bunting, D. L. 1974. Zooplankton: Thermal regulation and stress. Proc.

Symp. Energy Production and Thermal Effects. Limnetics, Milwaukee, Sep. 1973. pp. 50-55. .

Duke Power company. 1973a. Appendix B to facility operating license Nos.

DPR-38, DPR-47, and DPR-55, Technical specifications for the Ocesee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 1,1975, NRC), Washington, D. C.

1973b. Oconee Nuclear Station. Semi-Annual Raport, Period Ending June 30, 1973.

1976. Oconee Nuclear Fration. Annual Report, Period Ending December 31, 1976.

1977. Oconee Nuclear Station. Environmental Summary Report, 1971-1976.

Goss, L. B. and D. L. Bunting. 1976. Thermal tolerance of zooplankton.

Wat. Research. 10: 387-398.

Keppel, G. 1973. Design and analysis: a researcher's handbook. Prentice-Hall, Inc., Englewood Cliffs, NJ. 658 pp.

1.5-8 ONS _ '7

}g{) -

Table 1.5-1 Phytoplankton density (X 10 6 units /m3 ), biovolume (mm 3 7,3), and total chlot:optyll (ag/m3) for DNS entrainment studies,1977.

DENSITY Location Replicate Jan 12 Mar 16 May 11 Jul 13 Oct 12 Nov 16 Mean 530.0 A 161 468 122 539 217 339 B 177 577 164 493 178 773 Mean* 168 520 142 514 195 556 349 530.6 A 168 493 157 477 179 368 B 125 380 126 433 174 291 Mean* 145 434 140 '352 173 330 279 Date Mean 156 477 141 .,4 i 184 443 BIOVOLUME T 530.0 A 115 265 136 145 220 362

• B 112 425 157 143 137 637 Mean* 114 345 146 144 179 500 238

'530.6 A 117 257 183 260 93 332 B 94 232 131 148 108 388 Mean* 105 245- 157 204 100 360 .95 Date Mean 110 295 151 174 140 430 CHLOROPHYLL .

530.0 A 1.32 0.75 1.04 0.49 1.07 1.15 B 1.61 0.91 1.03 0.74 0.68 1.03 Mean* 1.46 0.83 1.04 0.60 0.88 1.09 0.98 E

530.6 A 1.38 1.08 1.48 0.81 1.30 1.00

[l B 1.15 0.80 1.26 0.80 1.44 1.20 Mean* 1.26 0.94 1.37 0.80 1.37 1.10 1.14 Date Mean 1.36 0.88 1.20 0.70 1.12 1.10 530.0 - intake location 530.6 - postcondenser location

• Replicate means may appear to be a few digits off the last significant digit. This is due to truncation of numbers by the computer in calculating summary table totals (Appendix B, Section 4).

                                                                                       -- -   ---_s_ _ - - - - - - - -          _ _ _ -

Table 1.5-2 Analysis of variance (ANOVA) of phytoplankton density, biovolume, and chlorophyll measurements of ONS entrainment locations, 1977. SS MS F Source d_f 29190.4 29190.4 3.05 Density between locations 1 114720.7 12.00* Density among dates 5 573603.7 5 34178.4 6835.7 0.72 Location X date 9556.8 Error 12 114681.5

 .w                                                                                                2.03 1         10880.0            10880.0 y        Biovolume between locations                                           59980.3        11.22*

Biovolume among dates 5 299901.7 g 5 28538.7 5707.7 1.07 Location X date 5347.1 Error 12 64165.5 e Chlorophyll between locations 1 0.1473 0.1473 6.11* 5 1.0861 0.2172 9.02* Chlorophyll among dates 0.0597 2.48 Location X date 5 0.2983 12 0.2891 0.0241 Error

• Sigr.ificant at the a50.05 level.

O m

    ~

O

Table 1.5-3 Carbon assimilation ratios (mg carbon /mg chlorophyll /hr) and mean incubation temperatures (MIT) for assessment of phytoplankton entrainment effects at ONS, 1977. Entrainment Location 530.0 530.0 530.6 Sampling Assimilation Assimilation Assimilation Date Ratio MIT, C Ratio MIT, C Ratio MIT, C 01/12/77 0.06 10.2 0.60 19.8 0.55 19.8 0.15 0.54 1.18 Mean 0.10 0.57 0.86 - 03/16/77 0.58 10.7 0.52 20.9 0.43 20,9 0.47 0.54 0.18 Mean 0.52 0.53 0.30 05/11/77 0.36 14.4 0.35 22.3 0.25 22.3 0.31 0.28 0.38 Mean 0.34 0.32 0.32 07/13/77 0.18 21.1 0.18 28.9 0.26 28.9 0.11 0.07 0.23 Mean 0.14 0.12 0.24 10/12/77 0.39 20.2 0.44 26.0 0.39 26.0 0.86 0.80 0.29 Mean 0.62 0.62 0.34 11/16/77 0.90 17.8 0.61 25.1 0.37 25.1 0.84 0.60 0.58 Mean 0.87 0.60 0.48 1977 Mean 0.43 15.7 0.46 23.8 0.42 23.8 530.0 - intake location 530.6 - postcondenser location 1.5-11 ONS 12/77

Table 1.5-4 Analysis of variance (ANOVA) of assimilation ratios for thermal, mechanical, and total ONS effects, 1977. SS MS F Source df Thermal Effect 0.0043 0.25 Between locations 1 0.0043 5 0.9836 0.1967 11.72* Among dates 3.37* 5 0.2830 0.0566 Date X location 0.0168 E.ror 12 0.2014 Mechanical Effect 0.0081 0.28 Between locations 1 0.0081 5 0.6789 0.1358 4.78* Among dates 1.68 5 0.2393 0.0479 Date X location 0.0284 Error 12 0.3410 Total Effect 0.0006 0.02 Between locations 1 0.0006 5 0.5242 0.1048 3.21* Among dates 5.35* 5 0.8730 0.1746 Date X location 0.0326 Error 12 0.3917 l

• Significant at the af0.'0 5 level.

l f 1.5-12 ONS 12/77

Table 1.5-5

                                                                   ~

Analysis of simple main effects of thermal and total ONS effects, 1977. Source MS* F Thermal Effect January 0.21622 12.886** March 0.00002 0.001 May 0.00040 0.024 July 0.00040 0.024 October 0.00002 0.001 November 0.07022 4.185 Error 0.01678 Total Effect January 0.57760 17.696** March 0.04840 1.483 May 0.00040 0.012 July 0.01000 0.306 October 0.08122 2.488 November 0.15602 4.780** Error 0.03264 F.05(1,12) "

• Each month MS=SS/1 df.
  • Significant at the a10.05 level.

1 1.5-13 ONS 12/77

e tl

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Table 1.5-8

                           . Percent damage at the locations sampled based on total number of organisms observed in 1977.

intake Discharge

              -Site    Precondenser           Postcondenser Number        Percent   Number      Percent Number       Percent   Number        Percent Damage    Observed    Damage Observed     Damage    Observed      Damage    Observed Taxa 1612          0.9      1527          2.2 Cladocera  1401          3.0       1292          2.3 2124          2.4       2071          4.6      2389          5.7 Copepoda-  1622          2.3 2.4       3683          3.0      3916          4.4 Crustacea  3023          2.6       3416 F

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1.5-27 ONS 12/77

1.6 PLUME MAPPING FOR TEMPERATURE AND DISSOLVED OXYGEN Specification: At least four times per year, special sampling studies shall be made to identify and characterize the cooling water discharge plume with respect to dissolved oxygen and temperature. Data shall be collected from a minimum of 30 sampling points, following a sampling pattern designed to achieve coverage of the plume. Three of the surveys shall be conducted during periods when the following conditions are exp ected: i

1) Maximum condenser cooling water discharge temperature

2) Maximum acreage of discharge plume

3) Minimum condenser cooling water dissolved oxygen .

concentration (Duke Power Company 1973a). I. INTRODUCTION l During 1977 six plume surveys were conducted to characterize the thermal discharge from Oconee Nucleat Station (ONS). These plume surveys were conducted on February 24, August 30, September 21, October 12, November 22, , and December 14, 1977. The surveys in a'agust, September, and October were l conducted to satisfy conditions 1 and 3 of the specification. Condition 2 of the specification was satisfied by surveys in February, November, and j December. l II. METHODS AND MATERIALS I Temperature and dissolved oxygen (DO) measurements were obtained by an in-situ sonde; a description of this method was contained in the Water Quality , Section of a previous ONS Semi-Annual Report (Duke Power Company 1973b). i Temperatures and DG concentrations were recorded to the nearest 0.1 C l and 0.1 mg/1, respectively. ) l Sample locations for the plume surveys conducted on February 24, August 30, and September 21 are indicated in Figure 1.6-1. Each location was sampled j in a vertical profile which began one meter above the bottom and continued i to the surface (0.3 m), at intervals designed to characterize the plume. ' Vertical profiles for the plume surveys of October 12, November 22, and December 14 consisted of mid-channel profiles as in previous surveys. Other locations within a transect (Fig. 1.6-2) were sampled from a depth of 16 m to 0.3 m, where possible. During the December lA plume survey, a malfunction of the D0 subsystem on one of the instruments resulted in DO concentrations being recorded only in the discharge area (App. E, Table E-6). Sample locations (Fig. 1.6-1 and 1.6-2) for sli surveys were located by visual alignment between established reference points. The majority of the reference points were located by survey crews by triangulation for place-ment on a map (Duke Power Company 1973b). Other locations were visually placed on a map. Interpretation of Data Data for each transect in the Keowee River arm were averaged for each depth. 1.6-1 ONS 12/77

The data were then plotted with respect to depth and distance from the dis-charge and isolines were drawn (Fig. 1.6-3 through 1.6-13). Since the effects of the thermal plume were minimal in the Little River arm, data for that area were not plotted. Figures 1.6-14 through 1.6-19 were drawn by placing surface temperatures on a map. The average surface temperature for transect 30, 31, 32 (Location 506.0) served as a reference temperature; so that comparisons could be made with surveys previously reported. Using the surface temperatures for each location and.the reference temperature, isopleths depicting surface areas affected by the thermal plume were drawn for each survey. The resulting areas were measured with a planimeter and tabulated in Figures 1.6-14 through 1.6-19. Daily heat rejection rates by ONS are plotted in Figure 1.6-20. III. BESULTS AND DISCUSSION During the surveys conducted in August and September 1977 the thermal plume was almost non-existent. This situation was attributed to the hypolimnetic l withdrawal of the intake, low operating capacity, and high CCW flow. During February, November, and December larger plumes were recorded. Discharge temperatures recorded by the CCW temperature monitoring program (Table 1.1-1) ranged from 15.4 C in February to 30.7 C in September. The highest discharge temperature recorded during a plume survey (29.9 C) occurred on August 30. Dissolved oxygen concentrations at the discharge as recorded by the weekly DO monitoring program ranged from a low of 4.6 mg/l in September to a high of 8.7 mg/l in May (Table 1.3.1-3). During the August 30 plume survey the lowest discharge DO concentration (4.4 mg/1) was recorded. February 24 On this date the average rate of heat rejection for DNS was 6.2 X 10 7 kcal/ min (Fig.1.6-20). This was the highest heat rejection rate that occurred during the plume surveys of 1977. Condenser cooling water flow was 68% of the maximum. The highest discharge temperature recorded during this survey was 20.0 C (9 C* above reference) and the lowest discharge 2 dissolved oxygen concentration was 10.8 mg/1. Approximately 16.2 km (21.8%) of the lake surface was heated more than 0.5 C* above the reference temperature (Fig. l 1.6-14). These temperatures were noted as far as 7 km from the discharge. Data for depths below 10 m were not obtained due to high winds and rough 'sur-face conditions. August 30 ! The rate of ~ heat rejected by ONS averaged 3.6 X 10 7 kcal/ min with a CCW flow of 82% of the maximum on August 30. The highest discharge temperature recorded The 0.5 C* (29.9 C) was 2.3 C higher than the reference temperature. Surface isotherms in isotherm bounded an area of 0.1 km2 (Fig. 1.6-15). the Little River arm depict an inverted thermal plume which was the result of cooler water from the Keowee River arm being drawn through the connecting canal (Fig. 1.6-15). Low operating capacity, high CCW flow, and utilization of a hypolimnetic intake resulted in the discharge of waters approximately the same temperature.as the receiving waters. , 1 1.6-2 ONS 12/77

I During the plume survey on August 30, the intake surface DO concentration ) was 4.3 mg/1, while the lowest discharge DO concentration was 4.4 mg/l (App. E, Table E-2). Surface DO concentrations of 6.0 mg/l were record 2d within 0.8 km of the discharge (Fig ~ 1.6-10) . Surface DO concentrations in the inverted thermal plume of'the Little River arm were in excess of 7.0 mg/l (App. E, Table E-2). l-1 I September 21 Heat was rejected by ONS at an average rate of 2.6 X 107 kcal/ min on September 21 (Fig. 1.6-20). The CCW flow averaged 96% of the maximum. The highest ' discharge temperature recorded during the plume survey was 27.5 C. The i temperature difference between the discharge and the reference was 0.5 C*. ., Again, as in August, the thermal plume was discernible only in the discharge cove of ONS. Surface isotherms (Fig. 1.6-16) depict an inverted thermal plume in the Little River arm, which was the result of the same factors affecting the August pluma. The minimum discharge Do concentration recorded for the survey was 5.0 mg/1. The CCW mixed rapidly with the receiving waters and a surface DO concentration of 6.0 mg/l was recorded at the discharge. DO concentrations in the Little

River arm inverted thermal plume averaged 7.0 mg/l (App. E, Table E-3).

4 October 12 On October 12, the heat rejection rate was 2.3 X 107 kcal/ min (Fig. 1.6-20). The CCW flow averaged 93% of the maximum. The maximum discharge temperature recorded was 29.0 C and the minimum discharge DO concentration was 6.3 mg/l (App. E, Table E-4). The temperature difference.between the maximum discharge temperature and the - , reference temperature was 5.2 C*. Characterized by the 0.5 C' isotherm, the CCW plume was detected 4.5 km from the discharge and covered 10.0 km2 ) (13.4%)-of the total laks surface area (Fig. 1.6-17). The plume.affected

lake waters to a depth of 6 m (Fig.1.6-6). .The intrusion of the thermal i plume into the Little River arm was small..

In the discharge area (i.e. within about.5 km) the plume seems to have inhibited i DO replenishment to waters below 12 m (Fig. 1.6-12). In the Little River arm-areas not affected by the plume had nearly the same DO concentration top ; to bottom. This condition has been. observed in previous' years (Duke Power j Company 1977). 4 November ~22' 4 The' heat rejection rate for ONS on November 22 was 3.2 X 107 kcal/ min (Fig. 1.6-20)...The CCW flow-averagedL78% of the maximum. The highest recorded discharge temperature was 23.8 C which was 6.1 C' higher than the reference temperature (Fig. 1.6-18). The plume was detected at 6.5~km.from the discharge-(Fig. l.6-18)'and to'a. , maximum depth of 11 m (Fig. 1.6-7).- The 0.5 C* isotherm bounded an' area-

                                                ,1.6-3                       .ONS 12/77'

l of 17.6 km2 (23.7%) of the total lake surface and was observed in the Little River arm (Fig.1.6-18) . This plume was the largest observed during 1977. Predictions of monthly average plumes were made by Duke Power Company prior The to the operation of ONS (United States Atomic Energy Commission 1972). I plumes with the largest area coverage were predicted to occur from November to March. The area affected by temperatures 1.7 C* above the reference was , to be 22.4 km2 (30.3%) of the total lake surface. The 1.5 C' isotherm of the i plume on November 22 encompassed an area of 8.2 km2 (11.1%) of the lake surface area (Fig.1.6-18) and was considerably smaller than predicted. This plume affected less area than the largest plume recorded (November 19, 1975) during ONS operations (Duke Power Company 1977). The lowest D0 concentration recorded at the discharge was 7.8 mg/1. The DO concentration of the discharged CCW had little effect on the receiving waters since DO concentrations of both were nearly the same (Fig. 1.6-13). December 14 The heat rejection rate for ONS averaged 5.3 X 107 kcal/ The min on this date highest discharge (Fig. 1.6-20) and the CCW flow was 78% of the maximum. temperature was 22.9 C (App. E, Table E-6). A difference of The 8.2 C' was area bounded observed between the discharge and' reference 2 temperatures. by isotherms 0.5 C' and greater was 16.4 km (22%) of the total surface area of Lake Keowee (Fig. 1.6-18). The plume extended 7 km up the Keowee River arm and af fected waters to 7 m deep (Fig.1.6-8) . The lowest D0 concentration recorded at the discharge was 8.7 mg/1. Dissolved oxygen concentrations recorded in the Keowee River arm exceeded 8.0 mg/l (App. E, Table E-6). IV.

SUMMARY

AND CONCLUSIONS Discharge temperatures recorded during plume surveys ranged from 20.0 C in February to 29.9 C in August. DO concentrations at the discharge measured during plume surveys varied from 4.4 mg/l in August to 10.8 mg/l in February. Small thermal plumes were recorded during August'and September. Low operating capacities, high CCW flow, and hypolimnetic withdrawal of the intake contributed An to discharging cool water into the Keowee River arm of Lake Keowee. inverted thermal plume in the Little River arm also resulted from these operating conditions. Larger thermal plumes recorded in February, November, and December were smaller than those predicted in the 1972 Final Environmental Statement for similar situations. Plume data recorded during 1977 substantiate recommendations made in the Oconee Nuclear Station Environmental Summary Report to modify Technical Specification 1.6. Low DO concentrations were observed during August and September. Rapid mixing of the CCW with the receiving waters resulted in surface DO con-centrations at'the discharge of no less than 6.0 mg/1. During October, DO con-the l l plume inhibited the replenishment of DO to depths below 12 m. l centrations of the CCW were nearly the same as the receiving waters during " l i 1.6-4 ONS 12/77'

November. Operation of ONS during 1977 resulted in no dramatic change to the DO concentrations in Lake Keowee. 9 i 1.6-5 LONS 12/77 l

LITERATURE CITED Duke Power Company. 1973a. Appendix B to Facility Operating License Nos. DIR-38, DPR-47, and DPR-55, *?echnical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company. U. S. Atomic Energy Commission Docket Nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, D. C. 1973b. Oconee Nuclear Station. Semi-Annual Raport, Period Ending December 31, 1973. 1976.. Oconee Nuclear Station. . Annual Report. Period Ending , December 31, 1976. 1977. Oconee Nuclear Station. Summary Report. United States Atomic Energy Commission. 1972. Final Environmental Statement relate to operation of Oconee Nuclear Stations Units 1, 2, and 3. Duke Power Company Docket Nos. 50-269, 502-70, 50-287, Washington, D. C. i s i l l i i

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-                                                                                      i S

I EI P g D L P i E C U A F H NM l 4 EE M O EM R NU F OL i CP g g a '[ i E C N A O 7 7 4 1 T -

                           -        -                                                                      S           4 0                      I 3 I

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                             -                                                                                               A

D i

g I 2 i g

                .'             t' i

y [ 0 7 1 i [ I i I 8 6 l g E i R _ U _ y G _ I _ _ - U - - - -

                                                                                                ,O F                        _

l

              ,              -                                     ,         2 4                0                     ,

2 4 6 . 0 2 1 .1 , 2 2 O 1 i eW ?.s ri !y

r 40 e -

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.H
                 - 12 g i4  -
                                               \

16 - ff -

                   ,. _                        )                                                                                   -

10.0 10.0 20 - - , 22 - -

= i i I i i I i i I i i i i I i i I i i i i i i

!g O 1 2 3 4 5 6 7 8 9 FIGURE : 1.6-9 DISTANCE FROM THE DISCHARGE (KILOMETERS) - OCONEE NUCLEAR STATION PLUME MAPPING STUDY DATE : 2-24-77 PARAMETER DISSOLVED OXYGEN (mg/l)

j

                                                     ,                                                      l           l 9

U - - - - - - - ] l I

                                                                                                                )

I m_ / I l g ( m 8 N E

                                                                               -                                 G 0     l                            Y I

4 X O I l D E V 7 L l O S l IS I e D s -

             +                                                               r       l R

3 E

                                                                                                      )

T 6 S E R M E A T R E l M A 1 O N P L I K OY l ( T' D 1 0 AU 0 0 0 E TT 8 7 6 5 5 G SS R A H RG l C AN l S I EI P D L P l E C U A l H T N M 4 M EE O EM R NU F O L CP l l s. 4 4 E O 7 C 7 l N - A 0 T 3 S 3 I D 8 l E T I A D l 2 l 1 t 1 e s 1 0 1 l 6 1 l E {th> l R l U G 4, 4 - - - - - - - O IF 8 0 2 4 2 6 8 O i 2 i 4i 6i 1 2 2 2

                                         ;e:U5 Itg g

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ll1l l i l ll o 9 a - - - - - - - I i

                                                                                              )

l I / g ( m 8 N E G I i Y X O I i D 0 E 7 V l l 7 L O S I i S I l D . I i R E

                                                                                      )

T l 6 S E R M E A T R l 0 0 E 6 5 i M A O N P L l I K OY I i ( TD AU E TT l l 5 G SS R A H RG I

• i C AN

                              *-                                                       S I

EI P 4 D L P I i E C U A H T NM l 4 M EE O EM R NU i F OL CP E O 7 I C 7 i N - A 1 T 2 S l I l 3 D 9 I i E . T _ a1 A _ l i D _ N l l 2 I i l i 0 l 4 l I 1 1 I i 6 1 l m E

o. i R

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I K OY l ( I D T AU E TT 5 G SS l R A H RG 0 C AN

       '                                                 6 S

I D EIP L P E C U A N M l

        '                                                                                       H T

4 M EE l O EM R NU F O PL

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                                                           +                                     E C

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             ,                                                                                                  T
             .                                                                                                  A
             .                                                                                                  D 2

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O I I I I I I I I I I I I I I I I I I I I I I I I I I ,s.: l z. 4 - 6 - g) s: ,ge ., _ g G [U i2 - 8.0 , f

a. -

g i4 - i 16 - is - 20 - [* M' - 2 g ,, i i I i i I i i I i i li i I i i I i i I i i Ii i 2 3 4 5 6 7 8 9 g O I FIGURE : 1.6-13 DISTANCE FROM THE DISCHARGE (KILOMETERS) OCONEE NUCLEAR STATION

• PLUME MAPPING STUDY DATE : 11-22-77 PARAMETER : DISSOLVED OXYGEN (mg/l)

l REFERENCE TEMPERATURE

,. y

                                                                                                 ,     ,s u

O O5 1SO O

                                                                                                           .n 0

(

                                                                   .g                        ie    -               ,                                                            ,

b 4 e-

                                                                          -g q

6

• 9 2.0 2.5

                                                                                                                                                            *1 f

2* l g-

                                                      .rs
                                                                                                \

EOWEE DAM

                                                                                                   ,                                                     N h                            8               SURFACE E   t E a          O.3 %

3.0 C*- 0.3 ka - 2.5 C*- 2.4 km - 3.2 % 2.0 C*- 5.1 kos - 6.9 % 5 2

8. 6 % 0 1 1.5 C*- 8.4 km8 - 4 8 15. 8 %

1.0 C*- 11. 7 km - SCALE IN MILOMETUtS

0. 5 C*- 18.2 km*- 21.8 ef, $. .

Date : 2 -2+ 77

                                        "" *-                          Oconee Nuclear Station Plume Mopping Stud'y-C* Above Reference 1.6-20                                                                                          ONS 12/77

REFERENCE TDIPERATURE W , go a *% i l C gh O _ C n 1 7- &

                                                       'e O

o

                                                                                                                   *1
           /                                                                           '.                       i
                                                                 ~         ,

OWEE AM i SURFACE j E PER E 0.5 C*- 0,1 kna- O. I % i 4 0 1 2

                                                                  \           .                      .
         '*     '**-'8 Oconee helear Station                                 08te : s 77 Plume Mapping Stud'y i                                                      C' Above Reference 1.6-21                                                  ONS 12/77

REFERENCE TD4PERATURE *

                                 ,.                                         tF
                                                                                           ,     ,s 1**

a p G 9 db o n 6 k - 3 4 9 k 3

                                                                                                                                         *s a

as

                      /                                                      Y                                               gg AM -

l 0 fE

                        &%                                            I

[h* 0.5 Co - 0.8 km* - O.1% 5 0 2 s 4 one.: s 77 Figwte:1,6-16 Oconee Nuchar Statio9 Mume NPI"9 5t"dy C* Abwe Reference 1.6-22 ONS 12/7.7

l REFERENCE TDAPERATURE , 9 Y 1** O L D &O _ O t /: o.s I N Q .

                                            'e I

i.o g

                                                                                                                                /

b Q

                                                              ,,                                                           of                                     1
                                                               \~                                s.s

g. \

EOWEE DAM l3 a E

                                                          \

2.0 C'- O.3 km _ o3g

1. 5 C'- 0.8 km*- 1.0 %

l .0 C'- 3.9 kma

                               - S.2 %

0.5 C' - 10.0 km - 13.4 T. 0 1 2 4 SCALE IN KILORETUIS Figure : I . 8 -17 Oconee Nuclear Station hie :lO 77 Plume Mapping Stud'y l C' Above Reference l l 1.6-23 ONS 12/77 l

REFERENCE TDAPERATURE ,

                              .                       y     "
                                                                     ,         ,s l                                  ,

O* f

                                &                                 SO

+ 4 I 160 ' C W* n4 o n

                                                                                     +N j

f ( " i.5 l y 1 s ,

      .                       s, 5
                                                                                             \

2.0 W

                                'g6
                         > g-QS                      ;                EOWEE AM i                   SURFACE PER     E 3.OCS- o.lkma _              o,i g 2.0 ca - 2.s km" -           3.5 %

1.5 co- s.2km* - II.I % o i 2 i.o co -is.5 md- 20.9 % 0.5 c*-17.e ks - 23.7 % '

                                                                                                   *

• 33
• 7 7 Figwe : 1.e -la Oconee Nuclear Station Plume Mapping Stu d'y C' Abeve Reference

 '                                                   .1.6-24                                               ONS 12/77

REFERENCE TDIPERATURE , I gb

                                                         ?

9 C7 94 o 1.0 n I. 5 l 30 ( .

s. .

2.5 [ , 25 1

                                                                                   . _M AM 1           . gyngacg E

4.0 C'- O. I tm8- O.1 %

      . 3.0 C*-   0.3ke' -     0.4 %

2.s C*- 2.7km' -

3. 8 %

2.0 C*- e.Okas" - 8.I % i.s C*- s.o mm' - lo.s % o i 2 I.o c*- lo.s ms* - 14.2 % scale in si 0.s c*- 1s.4 kas* - 22.0% g

• Figwe: I .e-l9 " ;'Ed4~77 Oconee Nuclear Station, l Plume Mopping Study C' Above Reference 1.6-25 ONS 12/77

l.7 GAS BUBBLE DISEASE STUDY Specification: A. The fish collected as a part of the population dynamics study (1.3.2) shall be examined for symptoma of gas-bubble disease. Those fish which exhibit symptoms of gas-bubble disease shall be identified, weighed, and measured; this data plus the date and location of capture will be tabulated (Duke Power Company 1973a). I. INTRODUCTION The relationship between gas-bubble disease and the operation of steam electric stations has been discussed previously (Duke Power Company 1973b). , II. METHODS AND MATERIALS The methods and materials used in monitoring gas-bubble disease in Lake Keowee fishes were presented in the Oconee Nuclear Station, Semi-Annual j Report for the period ending June 30, 1973 (Duke Power Company 1973b). ' III. RESULTS AND DISCUSSION Southeast Reservoir Investigations has not observed gas-bubble disease in Lake Keowee fishes during this reporting period. IV.

SUMMARY

AND CONCLUSIONS I The lack of observed gas-bubble disease symptoms in Lake Keowee fishes to date indicates that the problem does not exist in the lake. LITERATURE CITED Euke Power Company. 1973a. Appendix B to Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Power Company, U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 1, 1975, NRC), Washington, D. C. l Duke Power Company. 1973b. Oconee Nuclear Station. Semi-Annual Report, Period ending' June 30, 1973. 1.7-1 _0NS 12/77

1.7 CAS BUBBLE DISEASE Specification: B. Determination of the percent saturation values of the gases _ oxygen and nitrogen dissolved in Lake Keowee waters shall be made at Stations 502, 504, 505, intake structure, discharge acructure, and discharge cove at depths of 1, 5, 10 and 20 feet. The study shall be performed monthly during the winter period, November to April, starting in November,1973 (Duke Power Company 1973a). I. INTRODUCTION . Supersaturation of dissolved gases has previously been found in the discharge of steam plants. A discussion of this phenomenon may be found in the ONS Semi-Annual Report for the period ending June 30, 1973 (Duke Power Company 1973b) and the Environmental Summary Report, 1971-1976 (Duke Power Company 1977). II. METHODS AND MATERIALS i discussion of the methods and materials used in this study for January through December,1977, may be- found in the Oconee Nuclear Etttion Semi-Annual Report for the period ending June 30, 1974 (Duke Power Company 1974). III. RESULTS AND DISCUSSION The results of sampling during 1977 are summarized in Table 1.7-1 as percent saturar*on of oxygen and nitrogen. Figures 1.7-1 through 1.7-6 depict the mean percent saturation and standard deviations of dissolved gases for each location for each month of sampling. Generally the highest average saturation values were recorded for the ONS discharge (Location 508.0). The following is a summary of the sampling location minimum and maximum values for each of.the six , sampling periods (these values were obtained by averaging the four sampling' depths):

                                         % Nitrogen Saturation Minimum                           Maximum Date_

January 7 92.9% - Location 501.0 105.8% - Location 508.0 February 4 89.4% - Location 501.0 101.8% - Location 502.0 93.9% - Location 502.0 103.8% - Location 504.0 March 4 110.3% - Location 508.0 April'1 90.0% - Location 502.0 79.4% '- Location 509.5 99.0% - Location 501.0 November 18 91.7% - Location 504.0 101.4% - Location 508.0 December:9 l 1 I i , 1.7-2 ;0NS 12/77

                                     % 0xygen Saturation Date                  Minimum                         Maximum January 7          88.7% - Location 505.0           106.7% - Location 508.0 February 4         85.9% - Location 501.0            99.8% - Location 508.0 March 4            91.0% - Location 502.0-           99.8% - Location 504.0 April 1            87.4% - Location 502.0           106.4% - Location 508.0 November 18        75.6% - Location 509.5            89.8% - Lccation 501.0 December 9         82.4% - Location 503.0            93.8% - Location 508.0 Even though supersaturation of nitrogen was most common in the DNS dis-

! charge the condition existed at each of the remaining sampling locations at least once during the six sampling periods. Supersaturation of dis- - solved oxygen was less evident than nitrogen. Supersaturation of oxygen was primarily associated with the ONS discharge (Location 508.0). Supersaturation of both gases in the ONS discharge seemed to have dis-sipated by the time the thermal discharge plume reached Location 508.5 approximately 200 m out in front of the discharge structure. IV.

SUMMARY

AND CONCLUSIONS Slight' supersaturation of both, nitrogen and oxygen, h&c been documented both near and distant to the discharge area of ONS quring each of the past four years of sampling. Supersaturation of these two gases in the discharge was attributed to the increase in temperature and pressure as the lake water passed through the Condenser Cooling Water system during ONS operations. However, supersaturated conditions at distant locations from the ONS discharge i show that.even under natural conditions slight supersaturation of nitrogen j and oxygen can and has occurred in the lake. 1 The absence of symptoms of -gas-bubble disease (GBD) in Lake Keowee 1 fishes in the area of the ONS discharge may indicate that fish do not I remain in the warm water discharge long enough to develop symptoms of GBD and/or that the concentrations of these two gases are not high enough to result in the symptans of GBD. The presence of supersaturated conditions in waters distant to the discharge. suggests _the latter. LITERATURE CITED Duke Power Company. 1973a. Appendix B'to Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, Technical Specifications for the Oconee Nuclear Station Units 1, 2, and 3, Duke Pcwer. Company. U. S. Atomic Energy Commission, Docket Nos. 50-269, 50-270, and 50-287 (revised August 19, 1974, NRC), Washington, D. C.

                            . 1973b. Oconee Nuclear Station. Semi-Annual Report, Period Ending June 30,=1973.-

i

                            . 1974. Oconee Nuclear Station. Semi-Annual Report,         l Period Ending June 30, 1974.
                            . 1977. Oconee Nuclear Station. Environmental S unnary . Report, 1971-1976.

1.7-3 ONS 12/77

1101 4123 0882 1334 8646 2 5017 2 . N 1 976 3615 0000 9999 e 9999 9999 1 111 f s o 0 M 8874 2604 3174 8848 1 5 T 2 4251 8182 9664 7314 0 0 8989 8989 9990 9999 e g 5 5 039 L 77 65

                                                                   ;            051 a                        p          )
                                                    ]
                                                       . t. t.      . t.

F m e C 2222 1 100 1111 3332 1111 5555 1111 1111 T ( 2 9 ' - 0 2 4

                                                     '.       t.

(

                                                                      . t. t.

7502 4 1 5630

                                                                                                            . f.

9940 2 2908 0000 9910 1 N 0999 9909 1 1 11 1

                                    .                1                             1 t

41 24 0 S

                                                        .t.
                                                              )

4 1 (. 0, 7 e. 4 2 5 297 4 4 2 0524 3466 2005 0  % 0 0989 9998 0009 9809 1 1 111 5

                                           )         9998               2221                4446                5544 C        4444                2221               4443                 6665 1 1;1              1111                1 111               111 1

( 7042 1 235 4868 7 0411 5567 9398 0433 2 7 t N 6942 9909 0099 9999 9 a 9999 1 11 1 0 S 8622 2643 . r 7405 001 2 e 3  % 2 1540 6439 2874 8894 b 0 0 9999 8898 0889 8888 m 5 e J. J. 2 1 83 3 0 6281

t. 0 1

0 2 c p ) e m 8888 3200 5544 e C 2211 D 11 11 111 1 111 1 T ( d n 8474 3450 2432 0281 a 2 1395 2067 6532 9537 r e t

                                      .      "         0099                9999               9009   1 1 0099 1 1 1 1 b              5          a                                                                    .1 m                     S                     5461                6773               1 '.                2628 e             8                     2                                              604 4 v            0       %           0         7692                3239               909        9        2556 9998 o            5                             9989                9988                      1 N

p 7745 0816 2 385 6583

              .                              )

l mC e 6632 2109 3322 7655 1111 i 111 1111 r S T ( 111* p N 0734 3411 5974 8589 A O I 2 3667 1290 2248 8172 hg T .

                                             #          0000                090011             0009               0101 A                t                  1 1 1 1             1                  111                1111 u      C                 a o      O     0         S                   251           0     8465               4949               1933 r      L h              8         %           2       2683                4995               1894               64S9 t       G     0                  0          0O01                0809               0999                00OO N     5                             1 L 1 1              1        1         1                  1 1 L L y      I r      L                p       )          4455                7220               6565               5498 a      P                 m u     M                 e C               9999                 6460               13)3               9997 n       A              T        (          1 1 1 1              1 1 1 1            1 1 t1             1 1 1 1 a      S J                                           9094                 7030               7396               2876
               .                                2       1955                 8661               6921               2717 e                         .

N 9999 8999 990011 0009 e t a 1 1 1 w S o 0 4462 1910 0156 1950 e 2 K 9 2 4275 1985 2295 0527 0 0 8989 8888 8999 9998 e 5 1888 k p ) a 7444 2222 8881 L m C 0999 e 9999 6666 7778 1 r T ( o 0020 f 4611 2684 9818 y 1199 s . N 2265 3066 4595 e t 9999 1099 9989 9988 u a 1 1 l 0 S a 1423 9423 9175 7829 v 2 2 2 3540 8847 0 0 2634 8273 8888 n 5 9899 9988 9989 o 7633 i p ) 6554 0099 3130 t m a r e C 0000 8877 1100 1 11 1 5554 1111 T ( 11 11 u 5960 t 9998 9008 7728 a g 9139 s 1 142 5001 5954

                                          . N          9999                 8999               9990               0998 s                       t 1     1 a           0 aS                                                                                    9086 g
                              .                           6298                 2213               3016 d            1                     y                            4676               2339               8188 0 2                 O         2033                                    9999               0988 e                                        9999                  8888 v          5                                                                                        1 l

o p ) 6666 4433 9853 4418 s m e*C( 8888 5553 s 8888 5555 11 1 1 i T D h ) 3501 t 3501 3501 3501 1 p m

                  -                      e (               0136                 0136               0136              0136 7                       D 4                 1 1                                          7                    4 0                    0                  0                 0 e                      a                 /                    /

2

                                                                                                   /

3

                                                                                                                     /

4 l t 1 b a 0 0 0 0 t a D 77* oE CO~ D m&

Page 2 of 2 Table 1.7-1 Dissolved gas saturation values for take Keowee January through April, November and December 1977 (Cont.). SAMPLING LOCATIONS 301.0 -502.0 509.0 50?.0 508.5 503.0 5 04.0 505.0 Date Depth Temp  % Sat. Temp 2 Sat. Temp 2 Sat. Temp  % Sat. Temp  % sat. Temp I sat. 2 s;:r. Temp i St. (m) ('C) 0 2 N 2 ( C) 0 2 Ny ( C) 02 lN 2 ( C) 0 2 N 2 ( C) 0 2 Ng ( C) 0 2 N 2 ( C) 0 2 "2 ( C) 0 2 2 11/18 0.3 17.1 85.7 90.2 17.5 84.0 92.7 16.9 19.4 79.8 22.' 89.t1 93.6 19.. 80.0 91.9 18. 86.1 94.5 19.4 82.7 93.0 18.6 82.1 90.9 1.5 17.1 92.3 110.4 17.4 61.5 74.5 17.1 72.4 77.3 20. 80.] 87.1 19.4 94.4 99.0 18.t 87.3 101.5 19.3 84.4 95.5 18.8 80.N 88.2 3.0 17.0 79.6 82.8 17.3 90.0 98.0 17.2 77.4 82.2 20.e 78.2 87.8 19.' 95.2 109.1 17.' 84.8 91.2 19.3 85.3 102.0 18.8 83.7 91.8 6.1 17.0101.6 112.8 17.3 86.2 92.1 17.1 73.2 78.4 20.' 82.0 88.7 19.4 84.6 96.1 17., 82.6 98.8 19.3 83.4 82.7 18.6 76.9 81.4 Y 7 v' 12/09 0.3 13.N 95.8 100.1 14.5 84.2 93.6 14.9 97.8 104.8 21. ! !!0.5112.2 17.5 91.3 95.8 15.5 71.1 84.1 16.8 88.3 94.5 15.9 85.1 95.9 1.5 13.h 97.3 105.3 14.6 90.9 LOI.2 14.6 92.6 100.2 21.1 82.ti 92.8 17.2 83.1 89.9 15.' 91.2 100.5 16.8 80.9 88.7 15.6 91.J 95.1

3. 0 13. h 92.4 98.0 14.5 88.0 97.5 14.6 89.2 96.6 21.0 90.5101.4 17.0 85.9 94.9 15.! 88.4 100.0 16.7 78.2 93.5 15.6 74.4 85.1 6.1 13.h 89.6 99.8 14.5 87.8 98.7 14.6 89.7 99.5 19.5 91.8 99.1 16.7 87.5 96.6 14.N 79.1 89.2 16.7 84.2 90.3 15.7 84. t> 93.7 8

m M-b

                                    ~

4

115 0xygen 112 - - - - - - - - - Nitrogen 109 - 106 - a

                                           .. N
                                            /       \      "

103 . \

                                          /                                --

j \ " 100 ---------- f--- - -N % -

                                                                                                 ~
                                     /

N..% ,-

                                                                              's,

}y 97 g 94 " ",j  %

             ~                     .

m - p 91  % 1 88 85 82 79 76 73 - 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locations Figure 1.7-l' Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for January 7, 1977. I l 1.7-6 ONS 12/77 1 a 1

                                                                                               ,   .i

115 - Oxygen 112 - - - - - - - - Nitrogen 109 - 106 - 103 -- A -- 100 - - - - - -/- N----- - A-------

                                                                   \

a / r O \ \ O 97 g

                           /

I'

                                         \

g-- N g-,/

                                                                                /

N C- s a u 94 - / \ / -se 's' y e -- / _. -. m j ..

                                                                                ~

H 91 -

                   ,/                      ..            _

88 ..

              ../"                                                                                    "

85 - -- -- 82 - 79 - 76 - 73 - 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locations Figure 1.7-2 Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for February 4, 1977. 1.7-7 ONS 12/77

115 - Oxygen 112 - -- - Nitrogen 109 - .. 106 -

                                              "                            '~                     ~ "--

103 ..

                                                           -~~~               ,-        '-
                                                   '~

100 -- e s ' N " N 0 ta 97 - s

                                , -- /

s N

                                     /                                                          "         -'
                                ,V
  $ 94 u

N .. e 91 4 n 88 85 - 82 - 79 - 76 - 73 - . . . . 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locations Figure 1.7-3 Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for March 4, 1977. l 1.7-8 ONS 12/77 l f I

Nitrogen 115 - Oxygen

                                                                       ~~

112 - 109 - A

                                                                 ./       \
                                                                      .. g 106 -
                     ,,                                      j              \
                                                          /
                                                                              \

103 - \ "/s f j \ -- f N 8 100 t

                                                 /

l ----

                                                                            ---k g----/s                             -

h--- i-

                                                                                                                                                                             ~
                                                                                                                                  \

8 97 o

             -                                 l      -
                                                                                -\
                                                                                        \
                                                                                                 --           l' l

s / / Y \ / .. \ N - m 94 - K s -j Ng/ n \ / l 91 -

                                  .hr                                                    _   , ,                                                                                  l 88  -
                                     /
                                                                                        \/                        --

85 .. .. . 82 - 1 l 79 - 76 j l 73 - - - . . . . . . . . . . l 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locationc Figure 1.7-4 Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for April 1, 1977. 1.7-9 ONS 12/77 l H

1 1 l 115 - Oxygen

                                           ------ Nitrogen 112 -

109 - 106 - 103 e 100 o \

    " 97     -            \                                                   ,
                                                                                 - _ .          s y
                            \                                            -f                       N  N
                              \

ue 94 f s

                                \
                                 $-                             -- /                          ..             's s        ..
    ** 91     -                    \                                /                                             \

s /

                                                                                                                        \

88 -

                  \                      g                 .. /                        -.             ..
                                                            /
                                                          /                                                 ..

85 -

                                           \            j                                                           ,,

82 - \' ..

                                               \    /

79 -. 76 - l-

                                                              . i           . .           . .            ..            . .

73 i 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locations

                                                                                   ~

Figure 1.7-5 Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for November 18, 1977. f 1 1.7-10 CNS 12/77 L

                             .c

115 - Oxygen 112 - - Nitrogen 109 - -- 106 - -- 103 - s g 100 --- N q- --/ '-- - A'------ --------- w s,- .. N --

 +.     '                                                       s     ..

• 97 -- --

s -- u - M  % a 94 - --

                                                                         ' ~~

n - ,_ -- N,,- 93 -- 88 - 1 "' 85 - 82 - 79 .. 76 - 73 - i - - - - . . . . 501.0 502.0 509.5 508.0 508.5 503.0 504.0 505.0 Sampling Locations Figure 1.7-6 Mean dissolved gas saturation values for the various sampling locations on Lake Keowee and the associated standard deviations for December 9, 1977. 1.7-11 ONS 12/77 .

i l l SECTION II l

1. NtJAL OPERATING REPORT l

l l

2. INTRODUCTION _

This section of the Annual Operating Report is submitted pursuant to Section 6.6.1.2 of the Oconee Nuclear Station Technical Specifications. This section summarizes operation of Oconee Nuclear Station Units 1, 2, and 3 from January 1, 1977 through December 31,.1977. ' A e 2-1l

2.1 REPORT FOR JANUARY, 1977 e 2.1-1

2.1.1 OPERATIONS SU.TfARY 2.1.1.1 Unit 1 2.1.1.1.1 Operating Experie *e Oconee. Unit 1 began the month of January at 100 percent full power. On January 15, 1977 the unit was shutdown for steam generator tube repairs on the "1B" OTSG. Repairs were completed on January 25, 1977 but the outage was extended due to the failure of a position indication tube on the group 3 rod 4 control rod drive during startup. The unit was placed back in service the evening of January 25, 1977 and reached 100 percent full power on January 27, 1977. The unit remained at the power level until January 30, 1977 when the unit ranback to 53 percent full power due to group 4 rods dropping into

• core. The unit was returned to 100 percent full power the uame day and re-mained at that level for the duration of the month.

2.1.1.1.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during January,1977.

1. Revisions 6 and 7 of Station Modification ON-98 were completed. The

, ' modification involves the installation of pH, flow and turbidity in-strumentation for the oil collection basin.

2. Revision 0 of Station Modification ON-332 was completed. The modi-fication involves the replacement of the 1-pen total vent flow recorder )

with a 2-pen recorder. The second pen will monitor Reactor Building purge exhaust flow.

3. Revisions 0 and 1 of Station Modification ON-396 were completed. The modification involves the-relocation of gaseous waste disposal radiation monitors RlA-37 and 38 to the sixth floor of the Auxiliary Building and adds a sample line and air purge capability for background reduction.

4. Revision 0 of Station Modification ON-593 was completed. The modifi-cation involves the inspection of all General Electric type HFA and HGA relays and replacement of all defective relay coils as recommended 4

by NRC OIE Bulletin 76-02.

5. Revision OB of Station Modification ON-619 was completed. The modifi-cation involves the replacement of the non-radioactive waste disposal dumpster with a trash compactor.

6. Revision 0 of Station Modification ON-676 was completed. The modi-fication involved the addition of elasped time meters to. the Reactor Building purge, mini-purge and spent fuel pool ventilation fans.

7. Revisions 0'and 1 of Station Modification ON-685 were completed. The modificat!on involved maintenance on the spent fuel pool 100 ton cranes to reduce wear on the block sheave bushings and the crane cables.

8. Revision 0 of Station Modification ON-720 was completed. The modifi-cation involves the addition of a 600V-208V-120V transformer to supply power for lighting panels and wall outlets in the warehouse and shop.

2.1-2

9. Revision 0 of Station Modification ON-722 was completed. The main steam radiation monitors, RIA-16 and 17, were modified to improve check source operation.

10. Revisions 1 and 2 of Station Modification ON-725 were completed. The modification involved the plugging and stabilizing of leaking and questionable "1B" steam generator tubes.

11. Revision 0 of Station Modification ON-737 was completed. The modifica-tion involved changes to the off gas fill head in the radwaste solidifi-cation e-ea ventilation systems which will reduce contamination of the radwaste shipping cask. .

12. Revision 0 of Station Modification ON-741 was completed. The modifica-tion involved various electrical and mechanical changes necessary for the installation of the Chem-Nuclear Mobile radwaste solidification units to the Interim Radwaste Building.

13. Revisions OA and OB of Station Modification ON-751 were completed. The I

modification replaced valves SD-84 and 85 and FDW-258 and 259 with more reliable Kerotest valves. l I 2.1-3

                                                                                                                                 .fanuary 1977       gg ,    1 HAltgr. NANCE                                HONrl! 0F 2.1.1.1.3 EFFECT ON                                   PRECAUIIONS OPERATIO:I'S           COMPONENT                                              MALWNCTION
                                                                                                         -      SAFE             CORRECTIVE ACTION              FOR RESULT          DPERATION                                   REACTOR SAFETY NAME   NUMBER        M/JIUFACTURER -HODEL/ SIZE             W.R."Nbr. CAUSE                                                                .

Chem Add ,18 Crinnell - Diaph.1-1/2" 19182 Bad Diaphragm Leakage None' Iteplaced Diaphragm None Reg'd OTSC tube Babcock & Wilcox 95749 Not been Tube Leakage Plugged Tubes Unit off-lit e Leik determine

                                                                                                      ~

Personnel W. J. Wooley 19591 Needed Not closing None- Cleaned and adjusted , Unit of f-lir e e llatch Inter 1 Adjustment properly cables  ; 19489 Bad Seat Leakage None Lapped seat . Unit off-lir e "0" Ring 'Velan.

                       ~

Press Cauge Vent Valve Vent Valve Velan 18970 Packing Leakage None Repacked Unit Off-lire On Main Stear i Lina RC 14 Velan 3[4" 19494 Packing Repacked RC-3P Rockwell Clobe 2 1/2" 19495 Repacked Valve RC-3B 19496 RC-14 Velan 3/4" 19498 Building Spray Velan 1" 19488 Bad Seat Burr on globe , 23 filed off SD-154 Velan 19599 Packing Repacked Valve

                                                                               "    ~

SD-152 Velan 19597 eesmage *** 3 =

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    'i'                                  '

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JANUARY 1977 g3g7 y 1 HAINIEN NCE HO:mt OF Page 2 of 2

                                                                                                                                                               'PRECAUTIO:s EFFECT ON COMPONENT                                        HALFUNCTION                         CORRECTIVE ACTION             FOR OPERATION'S                                                                                    SAFE OPERATION                      .      REACTOR SAFETY W.R.' Nbr. CAUSE             RESULT NAME         NUMBER        HANUFACTUPIR -HODEL/ SIZE SD-153                    Velan                            19598           Packing           Leakage       None     Repacked Valve            Unit of f-lir e
                                                                                    ~

RC-14 Velan 3/4" 19497 CRD-54 Diamond, Power 19110 Rounded.off cannot be  : Replaced Bonnet Vent VaIve - vented with tool B Steam / Gen Velan '9582 1 Bad Gasket Leakage Replaced Bonnet 3 Inst. Root V. SD-151 Turb. Velan 19643 Packing Leakage Repacked Stop Valve . IIP-120 Leslie 2 1/2" 18744 Bad Seat Repacked RC-66 Dresser 2 1/2" X 6" 18953 Bad Seat Relapped Seat IIP -322 Velan Globe 1" 19487 Bad Seat 19629 Caskets Repaired by replacemtot OTSG FDW Bab' cock & Wilcox of gaskets Nozzle e

                             'I U                                                                                                           .

DOCKET NO. _50-269 2.1.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 1 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH January, 1977 SYSTEM RADIOACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 1/15/77 Unit was shutdown from 100 percent 222.20 A RO 269/77-2 The leaking tdbe and one other Liquid: full power to repair tube leaks on RO 269/77-3 questionable tube was plugged. 21.3% of the "1B" once-through steam generato- . The OTSG vendor, Babcox and annual release Wilcox is conducting a detailed Caseous: evaluation of the tube failures 40.0% of annual release (See summary) 1/25/77 Previous outage extended due to the 20,75 A The control rod drive P1 tube failure of a control rod drive was replaced. P1 tube during startup. 1/30/77 Unit ran back to 53 percent full 11 Relatched rods power from 100 percent due to droppe< Group 4 control rods. Summary: A discussion of the ia-advertent radioactivity re-leare on January 19, 1977 associated with the outage beginning January 15, 1977 ' is contained in R0-269/77-3 transmitted by our letter ol !* February 3, 1977 to Mr. N. C. Y Moseley, NRC/0IE, A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION Atlanta, Georgia. B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN) O

2.1.1.2 Unit 2 2.1.1.2.1 Operating Enperience The unit operated at 100 percent full power until January 12, 1977 when power was reduced to 95 percent full power for a performance test. Full power operation resumed on the same day. On January 20, 1977 power was reduced to 92 percent full power .for repair work on the "2D2" heater drain pump. Full power operation resumed the same day and continued until January 26, 1977 when power was reduced to 87 percent full power to repair a faulty temperature sensor on the reactor coolant piping. The unit returned to 100 percent full power the same day and continued at this level for the re- - mainder of the month. 2.1.1.2.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during January, 1977.

1. Revision 0 of station modification ON-10 was completed. The modifi-cation involved the installation of a key-operated bypass switch to allow operation of the fuel transfer carriage drive mechanism from outside the Reactor Building. The bypass switch will eliminate the need for personnel to enter the Reactor Building for fuel transfer carriage testing.

2. Revisions 6 and 7 of Station Modification ON-98 were completed. The modification involves the installation of pH, flow and turbidity in-strumentation for the oil collection basins.

3. Revision 0 of Station Modification ON-332 was completed. The modi-fication involves the replacement of the 1-pen total vent flow recorder with a 2-pen recorder. The second pen will monitor Reactor Building purge exhaust flow.

4. Revisions 0 and 1 of Station Modification ON-396 were completed. The modification involves the relocation of gaseous waste disposal radiation monitors RIA-37 and 38 to the sixth floor of the Auxiliary Building and adds a sample line and air purge capability for background reduction.

5. Revision 0 of Station Modification ON-537 was completed. The modifi-cation involved the installation'of thermocouple wells in each low pressure service water pipe to or from the Reactor Building cooling units.

6. Revision 0 of Station Modification ON-532 saa completed. The modi-fication will effectively disable the by-pass dampers on the Reactor Building purge filters and seal the exit of the bypass dampers.

7. Revision 0 of Station Modification ON-593 was completed. The modi-fication involves the inspection of all General Electric type HFA and HGA relays and replacement of all defective relay coils, as recommended by NRC OIE Bulletin 76-02.

2.1-5 _v

8. Revisions 0, 1, 3 and 4 of Station Modification ON-614 were completed.

The modification involved the replacement of valves HP-66, 2HP 146, 2HP146A, 2HP146B and 2HP147 with Kerotest valves. Also, valve hangers were modified.

9. Revision 0 of Station Modification ON-616 was completed. The piping on the Keowee governor compressor after cooler was modified to facilitate maintenance on the cooler.

10. Revision OB of Station Modification ON-619 was completed. The modifi-i cation involves the replacemeat of the non-radioactive waste disposal dumpster with a trash compactor. ,

11. Revision 0 of Station Modification ON-673 was completed. The modi-fication involved the transfer of the Administration Building electrical load to a non-loadshed load center.

12. Revision 0 of Station Modification ON-676 was completed. The modifi-cation involved the addition of elasped time meters to the Reactor Building purge, mini-purge and spent fuel ventilation fans.

13. Revision 0 of Station Modification ON-720 was completed. The'modifi-cation involves the addition of a 600V-208V-120V transformer to supply power for lighting panels and wall outlets in the warehouse and shop.

14. Revision 0 of Station Modification ON-726 was completed. The modifi-cation involves the redesign of the control rod drive power supplying failure detector canunciator.

2.1- 6

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DOCKET NO. 50 - 270 2.1.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT HONTH January, 1977 SYSTEM RADIDACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED REASON (HOURS) OCCURRENCE NO. EXPOSURE Summary: There were no outages or forced power reduction of over 20 percent of design power level this month. There was no single release of radioactivity or unusual radiation exposure specif1-cally associated with any outage which accounted for more than 10 percent of the allowable annual values. w A-EQUIPMENT FAILURE (EXPLAIN)

• E-OPERATOR TRAINING AND LICENSE EXAMINATION s B-MAINTENANCE OR TESTING F-ADMINISTRATIVE d, C-REFUELING G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.1.1.3 Unic 3 2.1.1.3.1 Operating Experience Oconee Unit 3 operated at essentially 100 percent full power for the entire l month of January, 1977. i 2.1.1.3.2 Changes Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during Janaury, 1977.

1. Revisions 6 and 7 of Station Modification ON-98 were completed. The ,

l modification involves the installation of pH, flow and turbidity in-strumentation for the oil collection basin.

2. Revision 0 of Station Modification ON-522 was completed. The modifi-cation involved removing the floor slab from the Reactor Building stair-l

way opening to the basement area and properly storing the slab. Re-I moval of the slab will facilitate maintenance activities and has no safety-related implications.

3. Revision 0 of Station modification ON-537 was completed. The modifi-cation involved the installation of thermocouple wells in each low pressure service water pipe to or from the Reactor Building cooling units.

4. Revision 0 of Station Modification 3N-559 was completed. The modifi-cation will effectively disable the by-pass dampers on the Reactor Building purge filters and seal the exit of the bypass dampers.

5. Revision 0 of Station Modification ON-593 was completed. The modifi-cation involves the inspection of all General Electric type HEA and HGA relays and replacement of all defective relay coils, as recommended by NRC OIE Bulletion 76-02.

6. Revision 0 of Station Modification ON-616 was completed. The piping on the Keowee govenor compressor aftercooler was modified to facilitate maintenance on the cooler.

7. Revision OB of Station Modification ON-619 was completed. The modifi-cation involves the replacement of the non-radioactive waste disposal dumpster with a trash compactor.

8. Revisions 0 and 1 of Station Modification ON-685 were completed. The modification involved maintenance on the spent fuel pool 100 ton cranes to reduce wear on the block sheave bushings and the crane cables.

9. Revision 0 of Station Modification ON-720 was completed. The modifi-cation involves the addition of a 600V-208V-120V transformer to supply l

power for lighting panels and wall outlets in the warehouse and shop. l 2.1-8

10. Revision 0 of Station Modification ON-726 was completed. The modifi-cation involves the redesign of the control _ rod drive power supply failure detector annunciator.

11. Revision 0 of Station Modification ON-737 was completed. The modifi-cation involved changes to the off gas fill head in the radwaste to the solidification area ventilation system which will reduce contamination of the radwaste shipping cask.

12. Revision 0 of Station Modification ON-741 was completed. The modifi-involved various electrical and mechanical changes necessary for the installation of the Chem-Nuclear Mobile radwaste solidification units to the Interim Radwaste Building. ~

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DOCKET NO. 50 - 287 2.1.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH January, 1977 SYSTEM RADIOACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE .- AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE Sununary: There was no outages or forced reductions in power this month. There was no i single release of radioactiv ity or unusual radiation exposur e specifically associated with any outage which accounted for more than 10 percent of the allowable annual values.

             ."                                                        A-EQUlPMENT FAILURE (EXPLAIN)     E-OPERATOR TRAINING AND LICENSE EXAMINATION Y                                                         B-MAINTENANCE OR TESTING          F-ADMINISTRATIVE o                                                         C-REFUELING                       G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

.t i i I 2.2 REPORT FOR FEBRUARY, 1977 , 5 h i 1 4 i 4 i f i I, 1 4 (' e l 2.2-1 i L I e.~ ----. , _ _ . _ _ _ . _ _ _ -----,nr. . wm,_.-,..m _. _ _ , _

2.2.1 OPERATIONS

SUMMARY

2.2.1.1 Unit 1 2.2.1.1.1 Operating Experience The unit was at 100 percent full power on February 1,1977 when a reactor shutdown was initiated to repair a leak in the control rod drive vent mechanism. Unit startup was commenced on February 8, 1977 and approximately 100 percent full power operation was reached on February 10, 1977. Full power e seration continued until February 28, 1977 when increases in radiation levels in the secondary system indicated a primary-to-secondary leak in the "1B" once- . through steam generator. While evalaating this incident, a control rod drop occurred due to a control rod stator causing high quadrant tilt. A reactor shutdown was initiated. The tube leak was repaired and the control rod stator replaced. 2.2.1.1.2 Changes, Test and Experiments Not Requiring Prior NRC Approval

                                                                                       ~

The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during February,1977.

1. Revision 0 of Station Modification ON-548 was completed. The modification involved the relocation of meterlogical equipment to a height of 10 meters above the base elevation of the microwave tower from a lower location. The relocation will standardize the data obtained from this equipment.

2. Revision 0 of Station Modification ON-559 was completed. The modification will ef fectively disable the by-pass dampers on the Reactor Building purge filters and seal the exit of the bypass dampers to prevent leakage.

3. Revision 1 of Station Modification ON-624 was completed. The modification will replace a Keowee turbine guide bearing oil cooler.

4 Revision 0 of Station Modification ON-649 was completed. The modification will add a monorail above the leak rate compressor motors to facilitate maintenance.

5. Revision 0 of Station Modification ON-667 was completed. The modification will upgrade the seismic supports of transformers CT-1, 2 and 3.

6. Revision 0 of Station Modification ON-736 was completed. The modification will remove the trace heater from the liquid waste discharge tanker fill line. This line is no longer being used.

7. Revision 0 of Station Modification ON-763 was completed. The modification will provide a method to contain and transfer potentially radioactive condensate leakoff in the Turbine Building.

8. Revision 0A of Station Modification ON-764 was completed. The modification will install a temporary extension of the four air inlet ducts nearest the control rod drive service structure to direct more cooling air on the

       . structure.

2. 2- 2 t-

1977 g:317 p 1 ltAIllTD: Ants M0!!Til CF FEBRUARY 2.2.1.1.3 EFFECT 0:1 PRECAUTIO::S C01:PONEt2 HALFUNCTICN CORRECIIVE ACTION FGK OPERATION'E SAFE DPERATION . JREACTOR SAFLTY W.R.' Nbr. CAUSE RESULT NAME NUMSER MANUFACTUP.ER -HODEL/ SIZE 1" Linkage Valve Inoperat le

• N'ne Replaced set screw in None Req'd LWD - 226 , Velan Globe [9848

                                                                                                                                                                         .                                 by.the Rdach                                reach rod Rod                                                                                               .

Bad Diaph. Leakage

                                                                                                                                                                                                                                                "       Installed new diaphragm                        Unit Down CA-18         .

Crinnell 1 I/2" 19834

                                                                                                                                                                                                                                               **                                               i
 'LD Filt'et           Fluid Dynamics                                                                                            .                    19'974            Warn Casket'                         Leakage                             "      Re'placed Filter Casket                          ".
   "B"                               .
                                                                                                                                                                                                                                            .                                                    ,       n        n n                        .
                                                                                                                                                                                                                                                 "                                                I RC-22                Vdlan'Clobe                                           1"                                                      :                19858             Loose Packing                                  .                                Repacked                    .

I j . . Welded Steam Cut FDW-263 vplan 19859 Steam Cut Leakage

                                                                                                                                              .                                                                                                          Installed new ha'skei:             -
  "B"   L.D. Filti e           Fluid Dynamics                                                                                                          19847            Worn Casket.                         Leakage                                     Peplaced gasket 52305'            Nick in           "o"                Leakage          *              "
                                                                                                                                                                                                                                                        ~happed seating surface                     ;UnitDown CRD - Motor           DjamondPower                                                                                                                                                                                                               .

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DOCKET NO. 50 - 269 2.2.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 1 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH February, 1977 SYSTEM RADI0 ACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RAD!ATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 2/1/77 Reactor was shutdown from 100 percen . 169.49 A Repaired control rod drive full power to repair a leak in the ' closure assembly leak and' re-control rod drive vent mechanism. placed deteriorated control rod drive mechanism power cables. 2/28/77 Unit shutdown from 100 percent full 3.20 A Ro 269/77-8 power to repair OTSG tube leak and Leak in "1B" steam generator was repaired and a failed control replace control rod stator, red stator was replaced. In-vestigating long-term solutions. Summary: There was no single release of radioactivity or unusual radiation exposure speci-fically associated with any outage which accounted for more than 10 percent of the allowable annual values. Y A-EQUlPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-0PERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.2.1.2 Unit 2 2.2.1.2.1 Operating Experience The unit operated at essentially 100 percent full power the entire month of February, 1977. 2.2.1.2 2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during February, 1977. Revision 1 of Station Modification ON-13 vas completed. This modifi- , 1. cation replaces the Electro Hydraulic Control first stage pressure transmitters with more reliable Rosemount transmitters. The

2. Revisions 0, 2 and 3 of Station Modification ON-442 was completed.

     . modification involved the installation of an interlock on the Reactor Building purge which will prevent the operation of the mini-purge fan; when the large purge fans are in operation.

3. Revision 0 of Station Modification ON-548 was completed. The modifi-cation involved the relocation of meteological equipment to a height of 10 meters above the base elevation of the microwave tower from a lower location. The relocation will standardize the data obtained from this equipment.

4. Revision 1 of Station Modification ON-624 was completed. The modifi-cation will replace a failed Keowee turbine guide bearing oil cooler.

5. Revision 0 of Station Modification ON-649 was completed. The modifi-cation will add a monorail above the leak rate compressor motors to facilitate maintenance.

6. Revision 0 of Station Modification ON-667 was completed. ~he modifi-cation will upgrade the seismic support of transformers CT-1, 2 and 3.

7. Revision 0 of Station Modification ON-736 was completed. The modifi-cation will remove the trace heater from the liquid waste discharge tanker fill line. This line is no longer being used.

8. Revision 0 of Station Modification ON-747 was completed.' The modifi-cation will add a strip heater to the borated water storage tank (BWST) t temperature transmitter enclosure. The heater will improve the re-liability of the BWST level' instrumentation.

9. Revisions 0 of Station Modification ON-763 was completed. The modifi-cation will provide a method to contain and transfer potentially radio-active condensate leakoff in the Turbine Building.

2. 2 i

                   . .  .2.3                                 MAINTENANCE                              MONTil 0F_ FEBRUARY -1977 UNIT # 2 OCONEE NUCLEAR STATION                                   ^

MONTilLY DATA SilEET F.FFECT ON PRECAUTIONS OPf.RATIDh*' S ('O'IPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR W.R. NBR CAUSE RESULT OPERATION REACTOR SAFE 1 IWIE Nil:4EER  !!ANUFAC1URER - MODEL/ SIZE Aux-Serv. Ingersoll Rand 19460 Bad Packinl; Leakage None Repacked None Req'd Water Pmp CWD-59 Velan Globe 1" 19529 Valve Failed Replaced Valve HPI Pmp "A" Westinghouse 12110 Bad Rotor Trips Replaced Rotor Motor Root Valve Velan 20577 Packing Leakage Tighten Packing

 .LPI Sys.

LP-28 B&W 14" 20598 Packing Note: No generating time los :.

DOCKET NO. 50 - 270 2.2.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT HONTH February, 1977 RADIOACTIVITY SYSTEM CORRECTIVE RELEASE OR CAUSE OR REPORTABLE A".TIONS RADIATION COMPONENT DURATION REASON OCCURRENCE NO. EXPOSURE DATE AFFECTED (HOURS) Summary: There were no outages or forced power reductions '.hL month. There was no single release of radioactivity or unusual radiation exposure specifically associated witl any outage which accounted for more than 10 percent of the allowable annual values. p A-EQUlPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMlHAT10tl y B-MAINTENANCE OR TESTING F-ADMINISTRATIVE vi C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

l i i i 2.2.1.3 Unit 3 2.2.1.3.1 Operating Experience

     'The unit operated at 100 percent full power until February 14, 1977 when the unit was shutdown to repair a tube leak in the "2B" once-through steam generator. Power escalation was commenced on February, 23, 1977 but on February 24, 1977 the unit was shutdown from approximately 70 percent full power to correct high chloride concentration in the Reactor Codlant System.

Unit startup was commenced on February 25, 1977 but the reactor was held at 15% full power for repairs to a trip coil on the generator. Power escalation resumed on February 26, 1977, and reached 98% full power by the end of the month. - 2.2,1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant,to 10CFR50.59 during February, 1977.

1. Revision 0 of Station Modification ON-10 was completed. The modifi-cation involved the installation of a key-operated bypass switch to allow operation of the fuel transfer carriage drive mechanism from outside the Reactor Building. The bypass switch will eliminate the need for personnel to enter the Reactor Building for fuel transfer carriage testing.

2. Revision 0 of Station Modification ON-332 was completed. The modifi-cation involved the installation of a two pen recorder in place of the present total vent flow recorder. The second pen will be used to monitor Reactor Building ourge exhaust flow.

3. Revision OB of Station Modification ON-398 was completed. The modifi-cation will increase the capacity of the feedwater pump seal leakage collection system.

4. Revisions 0 and 1 of Station Modification ON-495 were completed. The modification involves the installation of portable shield blocks in the letdown filter hatch area for letdown and seal supply filter changes.

5. Revision OB of Station Modification ON-502 was completed. The modifi-cation replaced and relocated valves RC-4 and RC-66 to increase the reliability of these valves.

6. Revision 0 of Station Modification ON-548 was completed. The modifi-cation involved the relocation of meteological equipment to a height of 10 meters above the base elevation of the microwave tower from a lower location. The relocation will standardize the data obtained-from this equipment.

l

7. Revision 0 of Station Modification ON-578 was completed. The modifi-cation deleted the RIA 4X and 3RIA 4X relays from the circuitry on the. spent fuel pool ventilation system. The change removes the auto-matic shutdown by high radiation signal which would cause vented air to bypass the filters.

l l

2. 2-6 I

l 1 l

8. Revision 1 of Station Modification ON-624 was completed. The modifi-cation will replace a f ailed Keowee turbine guide bearing oil cooler.

9. Revision 4 of Station Modification ON-640 was completed. The modifi-cation will replace 3RC-1, reactor coolant spray control valve, with a solenoid operated valve.

10. Revision 0 of Station Modification ON-649 was completed. The modifi-cation will add a monorail above the leak rate compressor motors to facilitate maintenance.

11. Revision 0 of Station Modification ON-667 was completed. The modifi- -

cation will upgrade the seismic supports of transformers CT-1, 2 and 3.

12. Revision 0 of Station Modification ON-676 was completed. The modifi-cation involved the addition of elasped time mete'rs to the Reactor Building purge, mini-purge and spent fuel ventilation fans.

13. Revision 0 of Station Modification ON-736 was completed. The modifi-cation will remove the trace heater from the liquid waste discharge tanker fill line. This line is no longer being used.

14. Revision OA of Station Modification OM-750 was completed. The modifi-cation will replace 3GWD-58, the reactor coolant pump seal filter vent valve, with a Kerotest valve. .

15. Revision 0 of Station Modification ON-763 was completed. The modifi-cation will provide a method to contain and transfer potentially radio-active condensate leakoff in the Turbine Building.

16. Revision 0 of Station Modification ON-771 was completed. The modifi-cation involved the addition of a " tee" and two valves in the shell drain line for the "3Al" feedwater heater to allow instrumentation to be attached for testing purposes.

l l 4

2. 2- 7

2.2.1.3.3 MAINTENANCE MONTil 0F FEBRUARY - 1977UNITI 3 OCONEE NIICLEAR STATION PACE I of 2 MONTilLY DATA SilEET 1.FFECT ON PRECAUTIONS OPERATION'S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR W.R. NBR CAUSE RESULT OPERATION REACTOR SAFE 1 NAME NUEEER HANUFACTURER - MODEL/ SIZE

 - IIP-206                                           Velan        Globe         1" 20280    Loose Packing       Leakage     None    Repacked Valve             Unit Down RC-3                                               Crinnel                       20560    Pipe Movement Damage to         None      Rebuilt Suppressor         None Require Suppr> asor                                                                                                 Restraint             Repair Restraint liydraulic                                         Grinnel                       51870    Pipe Movement Damage to         None Suppressor                                                                                                  Restraint
                                                                                                                             "                                   None Require 3B Letdown                                         Fluid Dynamics                20690    Worn Gasket       Leakage                Replaced Filter Filter RT Valve                                           Velan        Globe   1"       52167    Dirt Collected on Seat Sur '. Leakage                 Cleaned Stem & Seat Surfai  e Repacked             Unit Down Root Valv'e                                        Velan                         20293    Loose RC System                                                                                 Packing           Leakage               Repacked Valve               Unit Down llP-240                                           Velan Globe          1"        20291    InsufficienL      Leakage               Repacked Valve Packing Root Valve                                                                       20287                                            Repacked Valve RC System.

Nitrogen -125 Velan Globe 1" 20286 IIP-200 Velan. Globe 1" 20329 Plug Seal Leakage None Repacked and put Teflon-on Plug CF-5 Rockwell Cate 1" 20305 Bad Weld Leakage None Rewelded IIP-254 Velan Globe 1" 20284 Plug Leak Teflon the plug CRD Mtr Tube Diamond Power 20310 11ead Leaks Replaced Closure insert and Vent Valve Faerg. Fd Wate r Bingham Willamette 19884 Rust Build- Oil Leak

                                                                                                                                                                   "         "~

Pump Tank Up Cleaned rust from oil

                  ,N                                                                                                                deflector ring IIP-214 y                                          Velan         Globe           20281    Loose Packir g Leakage                  Repacked Valve E

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                       . N DOCKET NO. 50 - 287 2.2.1.3.4              OUTAGES OR FORCED REDUCTIONS IN POWER                           UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours)         REPORT MONTH February, 1977 SYSTEM RADI0 ACTIVITY CAUSE          OR                                                                     CORRECTIVE               RELEASE OR COMPONENT                DURATION              REPORTABLE                ACTIONS                  RADIATION DATE                   AFFECTED                   (HOURS)  REASON     OCCURRENCE NO.                                      EXPOSURE 2/14/77 . Unit shutdown from 100 percent full        222.46    A      Ro 287/77-2        The tube leak in the "3B" steam power to repair OTSG tube leak,                                                 generator was repaired. In-vestigating long-term solutions.

2/24/77 The unit was shutdown from -36.38 D Ro 287/77-3 Condition was corrected. Also approximately 70 percent full power repaired trip coil on generator . pursuant to Technical Specification 3.1.5.4 to correct high chloride concentration in RCS. Summary: There was no single release of radioactivity or unusual

                    -radiation exposure speci-fically associated with any outage which accounted for more than 10 percent of-the allowable annual values.

s 4 I# A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATI0tt Y' B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN) 8

2.3 REPORT FOR MARCH, 1977 G 2.3-1 l

2.3.1 OPERATIONS

SUMMARY

2.3.1.1 Unit 1 2.3.1.1.1 Operating Experience The unit was shutdown for repair of a tube leak in the "lB" OTSG until March 13, 1977. Power escalation commenced on that date and reached 90 percent full power on March 14, 1977. The unit was held at this power level due to maintenance on the "B" hotwell pump. On March 17, 1977 the unit ranback to 60 percent full power when the "lB" feedwater pump turbine tripped. The unit was returned to 90 percent full power the same day. On March 18, 1977 power was increased to 95 percent full power and on - March 19, 1977 power was reduced to 65 percent full power for performance of control valve and turbine valve movement tests. The unit was returned to 100 percent full power on March 20, 1977 and continued power operation until March 23, 1977 when the unit was shutdown to repair a tube leak on the "lB" OTSG. On March 30, 1977 the outage was extended because of re-pairs to a turbine turning gear oil pump and the unit remained shutdown the balance of the month. 2.3.1.1.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during March,1977.

1. Revision 0 of Stacion Modification ON-535 was completed. The modifi-cation will involve the redesign of the platform blocks on the second level-radioactive waste drumming station hoist area to provide a minimum load strength of 17,000 lbs.

2. Revision 0 of Station Modification ON-629 was completed. The modifi-cation involves the illumination of the protected area fence and valves and gauges in the bulk hydrogen storage shed.

3. Revision 0 of Station Modification ON-654 was completed. The modifi-cat *on will provide air intakes in the east wall of the Turbine Building '

to improve ventilation.

4. Revision 0 of Station Modification ON-704 was completed. This modifi-

' cation will eliminate glare on the spent fuel pool closed circuit tele-vision monitors created by the pool area lighting by replacing certain lamps with " glare stopper" lamps.

5. Revision 3 of Station Modification ON-725 was completed. The modifi-cation involved the plugging and stabilizing of leaking and questionable "lB" steam generator tubes.

6. Revision 0 of Station Modification ON-729 was-completed. The modifi-cation involves welding connecting angles of certain switching station relay house cabinets to the embedded steel at each shock mount. This modification upgrades the seismic restraints of these cabinets.

2. 3- 2

7. Revision 0 of Station Modification ON-757 was completed. The modifi-cation will remove the incore instrumentation at location R-7Safety from service and weld a cap over the location to repair a leak.

implications.of this modification were evaluated.

8. Revision 0 of Station Modification ON-783 was completed. The modifi-cation blanks the auxiliary feedwater nozzles that empty into the OTSG open tube lanes to help eliminate vibration in the lane.

J l i

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2. 3-3 I. . _ . . -

U UNIT #1 MAINTENANCE MONTil 0F

                      * *  *I*

OCONdE NUCLEAR STATION 1 of 2 PACE MONTilLY DATA SilEET ~ ~ ~ fFFECT ON PRECAUTIONS COTONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR _OZER[ man'S REACTOR SAFE 1 RAE  !!IlhE ER  !!ANUFAC1URER - MODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION MS-24 Crane - Gate 1" 18586 Bad Switch Inoperab le none ' Replaced Switch none reg'd electrical Ly Personnel llatch inter -W. J. Wooley 20854 Out of Not opening None Adjusted ratchet paw " " adjustment properly lock UP-79 Lonergan 2" X 3" 20432 Gasket Leakage None Replaced Gasket Unit Down I!P-57 Velan Gate 2 1/2" 19798 Broken liard to None Rr placed Valve Stem Nut Operate es B& W 20392 Unknown Tube leakage None Plugged tubes " " Closure Plug Diamond Power 20856 Gasket Leakage Replaced Gaskets Unit Down D Tub & Lapped Seating OTSG Tubes B&W 95806 Unknown Tube leakaqe None Repaired 1B Flow Meter Foxboro 20428 Pipe Plug Leakage None Replaced Pipe Plug Unit Off HPI Sys. Line' FDW-247 Crane Check 20913 Gasket Leakage Replaced B/B Gasket FDW- 37 Crane Check 24 20914 Worn Gask0t Leakage Replaced Gasket on liinge l'in IIP-283 Velan Globe 1 1/2 21147 Loose Pac) ing Leakage " Replaced packing None reg'd HP-286

• Velan Globe 1 1/2" 21386 Loose Pac) ing Leakage "

Replaced packing * " Y

c Y d 'q S T E F

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DOCKET NO. 50 - 269 2.3.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 1 q

               '~

(Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH March, 1977 CAUSE < j/ SYSTEM OR CORRECTIVE RADIOACTIVITY RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE- AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 3/1/77 Continuation of previous outage for 300.53 A Ro 269/77-11 Leaking and questionable tube s OTSG tube repairs were plugged. Investigation in progress. 3/23/77 Unit was shutdown from 100 percent 177.74 A Leaking and questionable tubt s full power to repair a tube leak in were plugged. Investigation the "1B" OTSG in progress. 3/30/77 Previous outage extended to repair 35.52 A Pump was repaired, a turbine turning gear oil pump. Summary: There was no single release of radioactivity or unusual radiation exposure speci-fically associated with any outage which accounted for more than 10 percent of the allowable annual values.

."                                                                                   A-EQUIPMENT FAILURE (EXPLAIN)    E-OPERATOR TRAINING AND LICENSE EXAMBHATION

-Y B-MAINTENANCE OR TESTING F-ADMlHISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.3.1.2 Unit 2 2.3.1.2.1 Operating Experience The unit operated at 100 percent full power until March 4, 1977 when power was reduced to perform maintenance on the 2D2 heater drain pump. Power was increased to 100 percent full power on March 5, 1977. On March 7, 1977 power was reduced to 94 percent full power to secure the 2D2 heater drain pump. Repairs, including replacement of an o-ring seal and packing sleeve, were made. Power was reduced to 70 percent full power on March 14, 1977 to correct the high temperature on the inboard bearing on the 2B and 2C condensate booster , pumps. Modifications were also made to the 2B and 2C condensate booster pumps oil system'. Repairs were completed on March 15, 1977 and power was increased to 90 percent full power and held at this level to stabilize feed-water swings. On March 21, 1977, the "B" HP1 pump came on automatically. The "A" HPI pump was determined to have a low oil level in the upper bearing and a sheared pump shaft. The "A" HPI pump was replaced. Power level continued at 90 percent full power until' March 23, 1977 whea the reactor was inadvertently tripped during a control rod drive breaker test due to a personnel error. The unit-was brought back on line the same day and the power level reached 65 percent full power en March 24, 1977. The unit was held at this level to repair a main steam valve and then increased to 70 percent full power and held due to maneuvering limitations. Power was then increased to 78 percent full power when the group 6 control rods dropped causing power to runback to 66 percent full power. Fuses were replaced on rod 3 and and investigation is being conducted to determine the cause of the drop. On March 25. 1977 power was increased to 90 percent full power and remained On at this level due to continuing repairs on the 2D2 heater drain pump. March 27, 1977 repairs were completed and power was increased to 100 percent full power. On March 29, 1977 control rod 2 of group 1 dropped while performing a control rod drive movement test. Power was reduced to 55 percent full power and then to 35 percent full power to stabilize the reactor. The dropped rod was picked up and power was increased to 100 percent full power. This power level was held for the remainder of the month. 2.3.1.2.2 Changes, Tests and Experiments not Requiring Prior NRC Approval. The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during March, 1977.

1. Revision 0 of Station Modification ON-629 was completed. The modification involves the illumination of the protected area fence and valves and gauges in the bulk hydrogen storage saed.

2. Revision 0 of Station Modification ON-654 was completed. The modifi-cation will provide air intakes in the east wall of the Turbine Building to improve ventilation.

2. }- 5

3. Revision 0 of Station Modification ON-704 was completed. This modifi-cation will eliminate glare on the spent fuel pool closed circuit tele-vision monitors created by the pool area. lighting by replacing certain lamps with " glare stopper" lamps.

4. Revision 0 of Station Modification ON-729 was completed. The modifi-cation involves welding connecting ang.es of certain switching station.

relay house cabinets to the embedded steel at each shock mount. This modification upgrades the seismic restraints of these cabinets.

                                     ~

2.3-6

l. I O

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FO T C C e A E _ 8- M R I i t

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                   .                    R 3             eN       E O        B I       M 2              T        U A        N R               5 E

P 9 O E - M A P FY? N L

     )%C

l DOCKET NO. 0 - 270 2.3.1.2.4 0UTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH March, 1977 1 SYSTEM RADIDACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE

    '3/14/77  Power was reduced from 94 percent to                   A                        Condition corrected. Modificatjo..s 70 percent full power to correct hig       i were made to pump oil system.

temperature on bearings of the 2B an< l 2C condensate booster pumps. 3/23/77 Reactor tripped from 90 percent full 7.27 A Conditions leading to incident power due to personnel error during investigated and corrected. a control rod drive breaker test.

   -3/29/77   Reactor runback from 100 percent to                    A                       Picked up dropped rod. Investi-55 percent then 35 percent full powel                                           gation of cause, after control-rod 2 group 1 dropped into core.

Summary: There was no single release of radioactivity or t.nusual radiation exposure specifi-cally associated with any outage which accounted for more than 10 percent of the allowable annual values. [ A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPEPATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THtR (EXPLAIN) si _ _

2.3.1.3 Unit 3 2.3.1.3.1 Operating Experience

    ' e unit maintained 100 percent full power until March 15, 1977 when a steam trak on the high pressure turbine exhaust piping caused power to be reduced ta 10 percent full power. Repairs were made and on March 16, 1977Powerpower was was increased to 90 percent full power to await xenon equilibrium.

increased to 100 percent full power on March 18, 1977. On March 19, 1977 an instrument air line failure on valve to close reducing flow to the "B" OTSG. Power automatically ranback to 41 percent full power 3FDW-40 was placed under manual control and the unit was returned to 100 , percent full power operation on March 20, 1977. Full power operation con-tinued for the remainder of the month. 2.3.1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during March,1977. i

1. Revision 0 of Station Modification ON-006 was completed. The modifi-cation upgraded the Unit 3 polar cranes to withstand a higher load limit.

2. Revision 0 of Station Modification ON-629 was completed. The modifi-cation involves the illumination of the protected area fence and valves and gauges in the bulk hydrogen storage shed.

3. Revision 0 of Station Modification ON-654 was completed. The modifi-cation will provide air intakes in the east wall of the Turbine Building to improve ventilation.

4. Revisions 0 and 1 of Station Modification ON-655 were completed. The modification involves the installation of a prefabricated environmentally controlled gauge calibration room in the Unit 1 Auxiliary Building.

5. Revision 0 of Station Modification ON-729 was completed. The modifi-cation involves welding connecting angles of certain switching station relay house cabinets to the embedded steel at each shock mount. This modification upgrades the seismic restraints of these cabinets.

6. Revision 0 of Station Modification ON-772 was completed. The modifi-cation involved the plugging and stabilizing of leaking and questionable "3B" steam generator tubes.

?.

2. 3- 8

\

                                                            .            MAI!GENENCE Hum 11 0F      MARCII             UNIT #      1 2.3.1.3.3 EFFECT ON                                     PRECAUIIONS OPERATION'S           CO:20NENT

• MALFUNCTION SAFE CORRECIIVE ACTION FOR IfANUFACTURER -HODEL/ SIZE CAUSE RESULT OPERATION REACTOR SAFETY NAME NUMBER W.R.' Nbc. .

FDW-106 Rockwell Stop Valve , l 20356 Bad Packing Leakage None Repacked None reg 'd SF-76 Velan Globe 1" 20294 Bad Gasket' B/B. Leak None Replaced gasket " LP-21 Rockwell 2.0174 Loose Packiag Leakage None Tightened packing ,None req'i Personnel

• i IIatch Inner W. J. Wooley 90811 Loose Nut Not closing None Adjusted Valve None reg's Door properly '

ilydraulic Grinnell 51869 Failed Leakage None Replaced Suppressor tione reg'd Suppressor Seals FIPI Loop . Plow orfice. Ingersoll Rand 10335 Bad Gasket Leakage None Replaced Gasket Jone reg'd 3B Seal Supply Fluid Dynamics 2076'O Bad "o" Leakage None Installed new "O= lone reg'd Ring Ring 3B Seal 21253. Supply'd/p Transmitter Worn Threado Leakage None Replaced packing nu LNone reg 'c on packing Icol. Valve nut Piping leak Lonergan Relief 19922 Worn gasket Leakage None apstream of Replaced gasket None reg'd 'tS 92 - 3 M$- 4 85 ** O Y R . 4

                                                                                                                                               ~

DOCKET NO. 2.3.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH March, 1977 RADI0 ACTIVITY

                                               .           SYSTEM                                                                                          RELEASE OR CORRECTIVE CAUSE          OR                                                                                            RADIATION DURATION            REPORTABLE               ACTIONS COMPONENT                                                                                        EXPOSURE AFFECTED                  (HOURS)    REASON  OCCURRENCE NO.

DATE Reactor power was reduced from 100 5.13 A Weld leak was repaired. 3/15/77 percent to 10 percent full power. Turbine was taken off line to repair a steam leak on a high pressure turbine exhaust piping weld. Summary: There.was no single release of radioactivity or unusual radiation exposure specifi-cally acsociated with any outage which accounted for more than 10 percent of the allowable annual values. A-EQUIP;iENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMillATION

          -Y                                                                                                        F-ADMINISTRATIVE
          '*                                                                      B-MAINTENANCE OR TESTING C-REFUELING                      .G-0PERATIONAL ERP.0R (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

l

                                                         )

2.4 REPORT FOR APRIL, 1977 j 1 i

                                                         )

O l 4 2,4-1 L.

d 2.4.1 OPERATIONS

SUMMARY

2.4.1.1 Unit 1 2.4.1.1.1 Operating Experience The unit was shutdown for maintenance on the turning gear oil pump and turbine bearings until April 3,1977 when startup commenced. The unit tripped however from 12. percent full power due to high reactor coolant system pressure caused by the loss of the "B" loop feedwater control. The unit was returned to service after repair of the control module circuitry and reached 100 percent full power operation on April 5, 1977. . On April 23, 1977 power was reduced to 50 percent full power to perform a routine test on control rod withdrawal. While at this power level, control valve and stop valve movement tests were also performed. On April 24, 1977 a turbine trip occurred due to high water level in the moisture separator due to a failed drain valve causing a reactor trip. Repairs were made and the unit was returned to 50 percent full power on April 25, 1977 for completion of the control rod withdrawal tests. On April 26, 1977 power was increased to 90 percent full power and then reduced to 80 percent full power due to a steam leak on the "A" bleed line. Repairs were made and on April 28, 1977 the unit reached 100 percent full power operation. This power level was maintained the remainder of the month. 2.4.1.1.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during April 1977.

1. Revisions 0, 1, 2 and 4 of Station Modification ON-566 were completed.

The modification involves the replacement of the "lA" and "lB" OTSG root valves with more reliable Kerotest valves.

2. Revision OA and 1 of Station Modification ON-619 was completed. The modification involves the replacement of the non-radioactive waste dis-posal dumpster with a trash compactor.'

3. Revision 0 of Station Modification ON-639 was completed. The modifi-cation will replace the "y-strainer" upstream of the purifier feed pump with a duplex strainer.

4. Revision 1 of Station Modification ON-655 was completed. The modifi-cation involves the installation of a prefabricated environmentally controlled gauge calibration room in the Unit 1 Auxiliary Building.  !

                                                                                       -\

5. Revision 0 of Station Modification ON-664 was-completed. The modifi-cation will add angle bracing between the two A-frames making up each )

of the shield wire pull-off-frames on the roof of the Turbine Building. -

                                                                                         ]

1

2. 4-2

                                                                                 }

6. Revision 0 of Station Modification ON-669 was completed. The modifi-cation involved the installation of an air conditioning unit in the wall of the fif th floor canteen.

7. Revision 0 of Station Modification ON-673 was completed. The modifi-cation will change the area radiation monitor circuitry so the operator can read the "high" alarm setpoint on the module meter.

8. Revision 0 of Station Modification ON-711 was completed. The modifi-cation involves the seismic upgrade of the structural steel superstructure of the relay houses for the 230 KV switching station, D. C. test panal, battery chargers and D.C. panelboards.

                                                                               ~

9. Revision 0 of Station Modification ON-712 was completed. The modifi-cation will revise setpoints on the undervoltage relays as required to insure minimum operating voltage to safety-related equipment.

10. Revision 4 of Station Modification ON-725 was completed. The modifi-cation involved the~ removal of tubes from service in the "1B" OTSG.

11. Revision 0 of Station Modification ON-734 was completed. The modifi-cation involved the addition of a redundant "hi-hi" temperature switch to shutdown the lube oil purifier heaters at high temperatures.

12. Revision 0 of Station Modification ON-747 was completed. The modifi-cation involves the addition of a strip heater to the borated water storage tank temperature transmitters to prevent freezing of these lines during cold weather.

13. Revision OB of Station Modification ON-764 was completed. The modifi-cation will install a temporary extension of the four air inlet ducts nearest the control rod drive service structure to direct more cooling air on the structure.

2.4-3

MAINTEN NCE MONIH OF Apri1 UNIT I 1 2.4.1.1.3 1977 EFFEC" ON PRECAUTIONS COMPONENT MALFUNCTION TOR OPERATION'S SAFE CORRECTIVE ACTION OPERATION . REACTOR SAFETY 1RRBER MANUFACTURER -NODEL/ SIZE W.R.' Nbr. CAUSE RESULT NAME CA-ll Grinnell 3" 22150 B/B Gasket Leakage None Replaced Diaphragm None Reg'd LPSW-82 Crane , 8" 22205 Loose Packilig Leakage None Tighten Packing None CS-70 Grinndll 1" 21564 Loose S.et Inoperable None Replaced Set Screws .None Screw , and tighten Suppressor Grinnell 52574 Failed FDW-piping Seals Leakage None Replaced suppressor Unit Down 1 Suppressor Main Steam Grinnell 52416 Failed Leakage None Replaced Suppressor Unit Down Piping Seals P O e T u S 0

DOCKET NO. 50 - 269 2.4.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 1 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH April, 1977 RADIOACTIVITY SYSTEM CORRECTIVE RELEASE OR CAUSE OR DURATION REPORTABLE ACTIONS RADIATION COMPONENT OCCURRENCE NO. EXPOSURE DATE AFFECTED (HOURS) REASON 4/1/77 Continuation of previous outage for 66.94 . Repair and inspection were made. repair of turning gear oil pump bearing and inspection of turbine bearing for damage. 2.46 A The control module circuitry was 4/3/77 The unit tripped from 12 percent repaired. full power due to a failure in the ICS feedwater control module circuitry. The unit tripped from 50 percent ful. 11.24 A Valve was repaired. 4/24/77 power due to high level in the moists re separator reheater resulting from a failed drain valve. 4/26/77 Power was reduced to 80 percent full A Leak was repaired. power due to a steam leak on the "A" reactor coolant bleed line. Summary: There was no single release of radioactivity or unusual rac l-ation exposure specifically associated with any outage which accounted for more than

!"                                                                  10 percent of the allowable "I                                                                  annual values.

• A-EQUlPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.4.1.2 Unic 2 2.4.1.2.1 Operating Experience The unit operated at 100 percent full power until April 22, 1977 when the unit decreased power to 63 pereent full power to perform control valve and stop valve movement tests. The unit was returned to 100 percent full power on April 24, 1977. On April 29, 1977 power was decreased to approximately 94 percent full power to make repairs to the "B" feadwater loop controller. Repairs were completed and power was escalated to 98 percent full power the same day. The unit operated at this level for the remainder of the month. 2.4.1.2.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during April, 1977. '1. Revision 0 and 1 of Station Modification ON-264. The modification in-volved the installation of a solenoid valve in the suction supply line of the oil purifier. The valve will close on loss of power or stopping of purifier.

2. Revision 1 of Station Modification ON-419 was completed. The modifi-cation involved staking the inner shaft sleeve to the shaft on the "2A" high pressure injection pump.

3. Revision OA and 1 of Station Modification ON-619 was completed. The modification involves the replacement of the non-radioactive waste disposal dumpster with a trash compactor.

4. Revision 1 of Station Modification ON-655 was completed. The mcdifi-cation involves the installation of a prefabricated environmentally controlled gauge calibration room in the Unit 1 Auxiliary Building.

5. Revision 0 of Station Modification ON-664 was completed. The madifi-cation will add angle bracing between the two A-frames making up each of the shield wire pull-off frames on the roof of the Turbine Fuilding.

6. Revision 0 of Station Modification ON-669 was completed. The undifi-cation involved the installation of an air conditioning unit ir the well of the fifth floor canteen.

7. Revision 0 of Station Modification ON-711 was completed. The 1;odifi-cation involves the seismic upgrade of the structural steel scierstructure of the relay houses for the 230 KV switching station, D.C. te-st panel, battery chargers and D.C. panelboards.

8. Revision 0 of Station Modification ON-712 was completed. The modifi-cation will revise setpoints on the undervoltage relays as required to insure minimum operating voltage to safety-related equipment.

9. Revision 0 of Station Modification ON-734 was completed. The modifi-cation involved the addition of a redundant "hi-hi" temperature. switch to shutdown the lube oil' purifier heaters at high temperatures.

2.4-5

MAIrrrEN5NCE MO.Y nt OF APRIL _ UNIT f 2 2.4.1.2.3 . 1977 EFFECT ON PRECAUTIONS COMPONEhT *MALTUNCTION FOR OPERATIO:l'S SAFE CORRECIIVE ACTION OPERATION . REACTOR SAFETY ILuiUFACTURER -HODEL/ SIZE W.R.' Nbr. CAUSE RESULT NME NUMBER IIPI Letdowr Greenville Valve & 21614 Worn Ilose Leakage Nont Replaced flexible None Reg'd Filter.2B Fitting , hose. LPI-21 Rockwell 14" 21608 Set Screw Inoperable None Adjusted pinion None reg'd

                                                       .          on gear,                                        gear and tighten g                                                                                                                set screw .

CS-68 Grinnell 1 1/2" 22543 Ruptured Leakage None Replaced diaphragm None reg'd diaphragm CBAST Lapp CPES-4 22280 Worn Seals Leakage None Replaced seals None reg'd IIPI-Motor destinghouse 600 IIP 52633 Worn shaft inoperable None Repaired motor rotot None req. "2" T C .

                                                                                         .m i

l DOCKET NO. 50 - 270 2.4.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 2( Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH April, 1977 SYSTEM RADI0 ACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE Summary: There were no outages or forced reductions in power - this month. There was no single release of radio-activity or unusual radiatic a exposure specifically associated with any outage which accounted for more tha n 10 percent of the allowable , annual values. p-

 .T A-EQUIPMENT FAILURE (EXPLAIN)    E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING          F-ADMINISTRATIVE C-REFUELING                      G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-01HER (EXPLAIN)

2.4.1.3 Unit 3 2.4.1.3.1 Operating Experience The unit began the month at 100 percent full power and due to system load demand operated around this power level until April 19, 1977 with the ex-ccption of two reactor trips. The first trip occurred on April 6, 1977 due to the loss of the 125 volt D.C. power supply to the Electro-Hydraulic Control System. The unit was returned to 90 percent full power by April 7, 1977 and power was held at this level for xenon equilibrium. The unit reached 100 percent power on . April 8, 1977. The second trip occurred on April 13, 1977 due to a flux /ficw/ imbalance problem. The reactor commenced startup the same day and reached 90 percent full power on April 14, 1977. Power was held at 90 percent for xenon 15, 1977. equilibrium and was increased to 100 percent full power by April From April 19, 1977 until the end of the month the unit oper.sted around 96 percent full power due to chemistry problems. Investigations were being made to correct the problem. 2.4.1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval. The following changes, tests and experiments were carried out without prior NRC approval pursuant to the provisions of 10CFR50.59 during April, 1977.

1. Revision OA and 1 of Station Modificatiun ON-619 was completed. The modification involves the replacement of the non-radioac*ive waste disposal dumpster with a trash compactor.

2. Revision 1 of Station Modification ON-655 was completed. The modifi-cation involves the installation of a prefabricated environmentally controlled gauge calibration room in the Unit 1 Auxiliary Building.

3. Revision 0 of Station Modification ON-664 was completed. The modifi-

' cation will add angle bracing between the two A-frames making up each of the shield wire pull-off frames on the roof of the Turbine Building.

4. Revision 0 of Station Modification ON-669 was completed. The modifi-cation involved the installation of an air conditioning unit in the wall of the fifth floor canteen.

5. Revision 0 of Station Modification ON-711 was completed. The modifi-cation involves the se,ismic upgrade of the structural steel superstructure of the relay houses for the 230 KV switching station, D.C. test panal, battery chargers and D.C. panelboards.

6. Revision 0 of Station Modification ON-712 was completed. The modifi-cation will revise setpoints on the undervoltage relays as required to ersure minimum operating voltage to safety-related equipment.

7. Revision 0 of Station Modification ON-734 was completed. The modifi-cation involved the addition of a redundant "hi-lo" temperature switch to shutdown the lube oil purifier heaters at high temperatures.

2.4-7

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DOCKET NO. 50 - 287 Oconee Unit 3 2.4.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH April, 1977 SYSTEM RADIDACTIVITY OR CORRECTIVE RELEASE OR CAUSE COMPONENT DURATION REPORTABLE ACTIONS RADIATION AFFECTED REASON OCCURRENCE NO. EXPOSURE DATE (HOURS) 4/7/77 Reactor tripped from 100 percent 6.10 A 125 DC power restored. full power due to momentary loss of the 125V DC power to the turbine control system. 4/13/77 Reactor tripped f.om 99 percent full 6.11 A power due to flux / flow / imbalance problem. Summary: There was no single release of radioactivity or unusual radiation exposure spect(1-cally associated with any outage which accounted for

                                          . more than 10 percent of the
                              ."                allowable annual values.
                              .T A-EQUlPMENT FAILURE (EXPLAIN)   E-0PERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING        F-ADMINISTRATIVE C-REFUELING                     G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

1 2.5 REPORT FOR MAY, 1977

                                      )

2.5-1 m--

2.5.1 OPERATIONS

SUMMARY

2.5.1.1 Unit 1 2.5.1.1.1 Operating Experience The unit operated at 100 percent full power until May 7, 1977, when.the unit was shutdown to repair a tube leak on the "1B" steam generator. The unit was returned to service on May 23, 1977 and power was escalated to 70 percent full power. While performing an Emergency Feedwater System test at this power level on May 24, 1977, the unit tripped when condenser vacuum was lost due to a failed valve. . On May 25, 1977 the unit was returned to 70 percent full power and held at this level due to waste water storage problems. On May 30, 1977 power was increased to 90 percent full power and held at this level the remainder of the month. 2.5.1.1.2 Changes Tests and Experiments not requiring prior NRC approval. The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during May,1977.

1. Revision 0 of Station Modification ON-373 was completed. The modifi-cation will change high pressure extraction valve HPE-36 from an open/close valve to a throttle valve.

2. Revisions 5 and 6 of Station Modification ON-725 were completed. The modification involved the removal of tubes from service in the "IB" OTSG.

3. Revision 0 of Station Modification ON-814 was completed. This modifi-cation changes the Administration Building ventilation system by adding a supply duct to the whole body count room from the canteen area.

4. Revision OA of Station Modification ON-820 was completed. The modifi- I cation involved changing the turbine main stop valve test logic to I incorporate simultaneous testing of MSV 1 and MSV 3 together and MSV-2 and MSV-4 together.

l M 1 9 l l

                                                                                     \

2.52 y 1

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MAY UNITI 1 MAINTENANCE M0tml OF 2.5.1.1.3 OCONEE NUCLEAR STATION PAGE M HONTilLY DATA SilEET __ ZFFECT ON PRECAUTIOiS SAFE CORRECTIVE ACTION FOR COTONENT MALFUNCTION _O @ ] Al;T,fg 1 OPERATION REACTOR SAFE IIANUFACTURER - HODEL/ SIZE W.R. NBR CAUSE RESULT .42 5 Mllhl3El! None Reg'd Gate 4" 22685 Bad Pack- Leakage None Replaced Packing FDW - 104 Crane ing IIP-2 4 9 - Velan Globe 1 1/2" 22693 IIP-ll8

                                          "        Gate          4"           22696                      ,"

IIP-107 ' Crane Ga's 6" 22697 IIP-98 Crane Gate 6" 22694 , MS-88 Velan Globe 2" 22679 LPI Panp C Suction " " " " Pressure Velan 90840 Gauga Isol , Valve O e e Y V

DOCKET NO. 50 - 269 2.5.1 1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 1 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT HONTH May, 1977 SYSTEM RADI0 ACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 5/7/77 The unit was shutdown from 100 per- 382.00 A Tubes were plugged. Investiga t ia n cent full power to repair tube leaks of cause and possible solutions in the "1B" OTSG. in progress. 5/24/77 The unit tripped from 70 percent 4.26 A Valve was repaired. full power when condenser vacuum was lost during an emergency feed-water pump test due to a failed valv e 5/25/77 Unit held at 70 percent full power F Waste processing continuing. due to waste water storage problem. Summary: There was no single release of radioactivity or unusual radiation exposure speci(1-cally associated with any outage which accounted for more than 10 percent of the allowable annual values. [ A-EQUIPMENT FAILURE (EXPLAIN) E-OPEP.ATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.5.1.2 Unic 2

 . 2.5.1.2.1     Operating Experience The unit operated at 100 percent full power until May 6, 1977 when the reactor coolant loop A flow was momentarily lost to the ICS during an inspection of the flow instrumentation. The unit ranback to 75 percent full power. Power was escalated to the power level cutoff and then to 100 percent full power the same day.

On May 28, 1977 the unit was taken off line to commence refueling. . 2.5.1.2.2 Changes, Tests, and Experiments not Requiring Prior NRC Approval. The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during May, 1977.

1. Revision 0 of Station Modification ON-373 was compl'_ted. The modifi-cation will change high pressure extraction valve HPE-36 from an open/

close valve to a throttle valve.

2. Revision 0 of Station Modification ON-814 was completed. This modifi-cation changes the Administration Building ventilation system by adding a supply duct to the whole body count room from the canteen area.

I i I I e

2. 5- 4 m

2.5.1.2.3 HAINTENANCE MONTil OF MAY 1977 UNIT # 2 OCONdE NUCLEAR STATION PACE of MONTilLY DATA SIIEET ZFFECTONg PRECAUTIONS OPERarION'S CO'iPONEt3T MALFUNCTION SAFE CORREITIVE ACTION FOR

 @VIS ' tilitlEER   ttANUFACTURER - HODEL/ SIZE W.R. NBR     CAUSE         RESULT OPERATION                         REACTOR SAFI NO SAFE".T RELATED WORK PE 1 FORMED 1 IIIS MONTli e

e s e e e 9 e Y 4

DOCKET NO. 50 - 270 2.5.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 20 Percent af Design Power Level and Longer Than Four Hours) REPORT MONTH May, 1977 l RADIOACTIVITY SYSTEM CORRECTIVE RELEASE OR CAUSE OR REPORTABLE ACTIONS RADIATION COMPONENT L'JRATION EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE 4 76.26 Refueling commenced.

 - 5/28/77 Unit was shutdown from approximately                C 98 percent full power for refueling.

Summary: There was no single release of radioactivity or unusual radiation exposure specifi- , cally associated with any outage which accounted for more than 10 percent of the , allowable annual values. Y' i A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMlHATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

l 2.5.1.3 Unit 3 2.5.1.3.1 Operating Experience The unit began the month at 96 percent full power due to a chemistry problem. On May 4, 1977 the problem was corrected and power was escalated to 100 per-cent full power. Power level was held at approximately 100 percent full power the remainder of the month except for one power drop to approximately 60 per-cent full power for testing purposes. 2.5.1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval. The following changes, tests and experiments were carried out without prior

• NRC approval pursuant to 10CFR50.59 during May, 1977.

1. Revision 0 of Station Modification ON-373 was completed. The modifi-cation will change high pressure extraction valve HPE-36 from an open/

close valve to a throttle valve.

2. Revision 0 of Station Modification ON-814 was completed. This modifi-cation changes the Administ: tion Building ventilation system by adding a supply duct to the whole body count room from the canteen area.

3. Revision 0 of Station Modification ON-830 was completed. The modifi-cation involved the installation of General Electric instrumentation in the "3B2f' moisture separator reheater to collect data for generic studies on reheater reliability.

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DOCKET NO. 50 - 287 2.5.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH May, 1977 SYSTEM RADIDACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED '(HOURS) REASON OCCURRENCE NO. EXPOSURE Summary: There was no single release of radioactivity or unusual radiation exposure specifi-cally associated with any outage which accounted for more than 10 percent of the allowable annual values. No on tages or forced reduct-lons in power this month. [3 Y A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.6 REPORT FOR JUNE, 1977 l r l 2.6-1

2.6.1 OPERATIONS

SUMMARY

2.6.1.1 Unit 1 2.6.1.1.1 Operating Experience The month of June began with Unit 1 of 90 percent full power due to waste water storage problems. Power remained at this level until June 3,1977 when power escalation began. Power was increased as space became available for waste storage and reached 98 percent full power on June 6,1977. At this time the unit tripped when testing was inadvertently conducted on the Unit 1 turbine shaft oil pump - instead of the Unit 2 pump. The unit was returned to service the same day but at 26 percent full power the turbine tripped causing reactor pover to runback to approximately 12 percent full power. Investigation revealed no cause for the trip. Normal power escalation commenced on June 7,1977. The unit reached 100 percent full power on June 9,1977 and remained at this power level for the remain-der of the month. 2.6.1.1.2 Changes, Test and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during June,1977.

1. Revisions 0,2,3,4,5,6,7,8,9,10 and 11 of Station Modification ON-306 were completed. The modification involves changes to the reactor coolant bleed and miscellaneous waste evaporators to improve the operation of the Waste Management System.

2. Revisions 0 and 1 of Station Modification ON-573 were completed. The modification will improve the security system by adding magnetic locks to the doors in the main guard house and in adjacent hallways.

3. Revisions OA, 1 and 3 of Station Modification ON-698 were completed.

The modification involved the replacement of RIA 33 and RIA 34 with a General Atomics radiation monitoring system.

4. Revisions 0 and 1 of Station Modification ON-710 were completed. The modification upgraded the seismic quality of the 230 kV transformers at Keowee by adding restraints to the bases.

5. Revision 0 of Station Modification ON-713 was completed. The modifi-cation upgraded the seismic design of the 230 kV switching station relay house by adding channels and connecting plates across the cable trench adjacent to the columns.

6. Revisions 0 and 1 of Station Modification ON-717 were completed. The modification involves the installation of an annunciator in the Unit 1 Control Room for the waste water treatment system pH strip chart re- ,

corder.

7. Revision 0 of Station Modification ON-774 was completed. The modifi- l cation added a bridge stop bracket on the Unit 1 and 2 spent fuel pool bridge rail.

2.6-2

8. Revision OA of Station Modification ON-820 was completed.. The modifi-cation involved changing the turbine main stop valve test logic to incorporate simultaneous testing of MSV-1 and MSV-3 together and MSV-2 and MSV-4 together.

9. Revision 0 of Station Modification ON-825 was completed. The modifi-cation will connect electrical power to the planning trailer from 1XGB switchgear compartment F2AB.

f f l l l l

                                         > 2. 6-3 .                                 -

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2.6.1.1.3 }fAINTENANCE MONTil OF JUNE 1977 UNIT # 1 OCONdE NUCLEAR STATION ACE of

  ,                                                                                                    MONTIILY DATA SilEET ZFFECT ON                              PRECAUT10:41 Ot'f.RATIOM' S CO WONENT                                          MALFUNCTION         S 'E         CORRECTIVE ACTION           FOR j!SIE     ritir:RElt                        itANUFAClllRER - H0 DEL / SIZE                  W.R. NBR     CAUSE          RESULT OPER. TION                            REACTOR SAFI No safety-related work pt rformed for the morith of June For Unit ll.

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      ?                                                                                                                  .

l

DOCKET NO. 50 - 269 UNIT NAME Oconee Unit 1 2.6.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT NONTH June, 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTFD (HOURS) REASON OCCURRENCE NO. 'DATE The unit tripped from 98 percent 12.16 H Administrative action was taken. 6/6/77 full power due to a turbine shaft oil pump trip caused by technician error. 73 H Investigation showed no reason 6/6/77 Turbine tripped. for the trip. Summary: There was no single release of radioactivity or unusual radiation exposure specift- .i cally associated with any outage which accounted for more than 10 percent of the allowable annual values. .T a- 1 A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING - F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAlH)

2.6.1.2 Unit 2 2.6.1.2.1 Operating Experience Unit 2 was shutdown for annual refueling outage for the entire month of June, 1977. 2.6.1.2.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during June, 1977.

1. Revisions 0,2,3,4,5,6,7,8,9,10 and 11 of Station Modification ON-306 .

were completed. The modification involves changes to the reactor coolant bleed and miscellaneous waste evaporators to improve the operation of the Waste Management System.

2. Revision 0 of Station Modification ON-450 was completed. The modifi-cation installed a deflector plate around the quench tank rupture disc.

3. Revisions 0 and 1 of Station Modification ON-573 were completed. The modification will improve the security system by adding magnetic locks to the doors in the main guard house and in adjacent hallways.

4. Revision 0 of Station Modification ON-626 was completed. The modifi-cation involved rewiring the bridge circuits and adding mechanical bumpers to the fuel transfer bridges.

a 5. Revision 0 of Station Modification ON-646 was completed. The modifi-cation provides a signal from the Electro-Hydraulic Control System to close the moisture separator reheater drain valves to the condenser during the turbine shell warming mode of operation.

6. Revisions OA, 1 and 3 of Station Modification ON-698 were completed.

The modification involved the replacement of RIA 33 and RIA 34 with a General Atomics radiation monitoring system.

7. Revisions 0 and 1 of Station Modification ON-710 were completed. The modification upgraded the seismic quality of the 230 kV transformers at Keowee by adding restraints to the bases.

8. Revision 0 of Station Modification ON-713 was completed. The modifi-cation upgraded the seismic design of the 230 kV switching station relay house by adding chtnnels and connecting plates across the cable trench adjacent to the colamns.

9. Revision 0 of Station Modification ON-721 was completed.. The modifi-cation will establish an interlock between the Reactor Building purge exhaust throttle fan (mini-purge) and the alert alarm on RIA-45.

10. Revision 0 of Station Modification ON-742 was completed. The modifi-cation will replace the '9Dakoron" trace heating on the process line of. the borated water storagt tank level instrumentation with " Nelson" heat tracing.

1 2.6-5 l

11. Revision 0 of Station Nbdification ON-759 was completed. The modifi-cation involves the addition of a fif ty millisecond time delay in the f ast acting intercept valve circuits of the turbine control system to prevent noise spikes.

12. Revision 0 of Stat - t Modification ON-774 was completed. The modifi-cation added a brid, i stop bracket on the Unit 1 and 2 spent fuel pool bridge rail.

13. Revision OA of Station Modification ON-820 was completed. The modifi-cation involved changing the turbine main stop valve test _ logic to incorporate simultaneous testing of MSV-1 and MSV-3 together, and MSV and MSV-4 together.

14. Revision'0 of Station Modification ON-824 was completed. The modifi-cation involved maintenance on the spare'high pressure injection pump motor to return it .to operability.

15. Revision 0 of Station Modification ON-825 was completed. The modifi-cation will connect electrical power to the planning trailer from 1XGB switchgear compartment F2AB.

16. Revision 0 of Station Modification ON-846 was completed. The modifi-j cation involves the replacement of the magrbronze fuel grapple actuator cam with a stainless steel cam.

b

2. 6-6 .

s a 1- r

• 2.6.1.2.3 MAINTENANCE MONTil 0F 19 7 UNITI OCONEE NUCLEAR STATION MONTIILY DATA SilEET PACE 1 of 3 ZFFECT ON PRECAUTIONS OPERATIOM'S CFIPONFNT MALFUNCTION SAFE CORRECTIVE ACTION FOR

 ':M      NIIMBElt     flANUFACTURER - H0 DEL / SIZE                                                                          W.R. NBR        CAUSE        RESULT         OPERATION                               REACTOR SAFE IIP-249           Velan                Globe                                    1 1/2"                                     22971    Bad Packir g         Leakage       None       Repacked                    Unit Down LP'-75            Crane                Gate                                                 8"                             22975      "          "        "               "          =                            "       =
   ~ IIP-10 0                                                                                  6"                              22969      "          "

N-125 Velan Globe 1" 23220 Packing Leakage " " " " HP-259 Velan' Globe 1 1/2" 23223 " " " " FDW-99 Crane

• Check 6" 20616 Bad Gasket " "

Replaced Gasket " " LP-28 Chapman Gate 4" 21917 Bad Packing " " Replaced Packing " "

   !!P-148           Velan                Globe                                               1"                               22965        "       "           "            "

Repacked " " llP-ll4 Velan Globe 3" 22966 " " " " " " " IIP-ll8 Velan Globe 4" 22968 " " " " " " " HP-128 Velan Globe 4" 22970 " " " " " " " HP-250 . 1 1/2" '22972 " " " " " " " LP-34 Crane Gate 10" 23054 " " " " " " " LP-33 Chapman Check 10" 23055 Ilinge Pin " " Replaced flinge Pin " " Gasket Gaskets - , BS-4 Crane Gate 10"' 23057 Packing " " Repacked " " FDH-299 Velan Globe 2" 23074 Broken Ste n " " Replaced Stem RC-38 Volan Globe 1" 23219 Bad Packin g " " Repacked RCS-Root." Velan Globe 23228 Bad Packin g " " " 4 Valve T' e LPI-2B Graham Mfg. 24515 Worn Torque Flanges Letdown , Flange Cooler

                                                                                                                                                                                                                                                  ""                   2 MONTli OF                     UNIT #

2.6.1.2.3 MAINTENANCE OCONi'.E NLICLIMR STATION PACg 2 og 3 MONTill.Y DATA SilElfr PRECAlft1055 ZFFECT ON , CORRECTIVE ACTION FOR MALFUNCTION SAFE i 0TONENT OiT.lu I InX' S REACTOR SAFI W.R. NBR CAUSE RESULT OPERATION p_A'IE i:ll! EEli  !!ANUFAC1LTRER - HODEL/ SIZE Leak' age Hone Repacked Unit Down LP-69 Aloyco Gate 8" 22973 Bad PackinJ HP-98 Crane 6" 22967 Bad PackinJ 22977 '" " " " " LP-7 Gate 14" LPI-Sys " " 23235 Broken Rewelded Piping to LP-ll Weld . Graham Mfg. 16776 Tube Leak Replaced with new

                         ' Letdown                                                                                                                                                                                                       cooler Cooler
                                                                                                                                                                                                          "               "         Replaced Gaskets RC-66                                                         Velan                                 Globe                         1/2"     22953     Worn Seat Bushings
                                                                                                                                                                                                          "                         Replaced Valve HP-35                                                         Velan                                  Globe   -

1" 53135 Worp Thre. ids on Seat PR-7 Grinnell Diaphram 2" 23380 Torque Ino'perable Adjusted Switch Switch out Electricall r af Adjust. Instru " Replaced hand wheel " " Isoloc on Velan Globe 3/4" 23211 Broken Unable to S/G Hd Vent sheel operate

                                                                                                                                                                                         .        manually Pzr. Steari                                                                                                                                                                                                                         "         "*

16784 :orrosion Line Blocke<l " Removed and cleaned Space Vent - Line

                                                                                                                                                                                                                                            ~

Globe 1" 6006 18873 lorn Gaske - Leakage Replaced Gasket MS-143 Velan -

                                                                                                                                                                                                                              "              "       =             "          "

BS-ll Crane 8" 3000 23053 forn Gaske'- . BS-6 "p Crane 10" 3006 23058 Globe 2" 6005 22964 Ba,d Packing Pepacked CS-20 Velan 90818 Worn

                                                                                                                                                                                                             "                 "     Replaced Gasket R.B.                           Emery W. J. Wooley                                                                                                   Gasket Ilatch i       .

2.6.1.2.3 MAINTENANCE MONTII 0F June -1977 UNITp 2 OCONdE NUCLEAR STATION 3 of 3 PAGE

 ~~
                                                                           !!ONTilLY DATA SIIEET 2FFECT ON                              PRECAUTIONS OPERM ION'S                 COMPONENT                                             HALFUNCTION         SAFE           CORRECTIVE ACTION      . FOR UN15      NilMBElt     !!ANUFACTURER - HODEL/ SIZE            W.R. NBR            CAUSE       RESULT   OPERATION                             REACTOR SAFI RC-44              Velan         Globe           1"      23224         Bad Pkg.         Leakage     None    Repacked                    Unit Down IIP-356                             Globe        1"      23214         Bad Pkg.         Leakage     Hone    Repacked RC-24              Velan         Globe 1 1/2' '           23209        Bad Pkg.
  . RC-19              Velan         Globe        1"         23216 N-122              Velan         Globe        1"         23217                                                                 ,

FDW-308 Gate 6" 21583 HP-144 'Velan Stop Ck 1 1/2" 23213 " " " "

                                                                                                                          "                  c       "

LPI Pum15 -Ingersol Rand 23051 Bad Gaske : Plange Replaced Flange Gaskei. LeaRage - LPI Pump . 23056 Th' reads Leaking Tcfloned Threads Vent Line Worn CBAST Pmp Lapp Mfg. Company 23059 Worn Leaki~ng Clean threads. Repl. Stand Pipo Threads with teflon. Cap LPSW Cuno Filter Company Supply 23090 Broken Leakage Replaced Ring Line Filter Retaining . Holder Ring FDW-101 Crane Check 6" 22872 Worn Hinge Replaced Hinge Pin Pin Gasket Nitrogen . Valve on Globe Velan 1" 18874 Packing " " Repacked upper steitm

      ,1,ine .

RCS-Inst. " " Valve 23P Velan Globe 1" 23215 Packing Repacked' T

         ?

DOCKET NO. 50 - 270 UNIT NAME Oconee Unit 2 OUTAGES OR FORCED REDUCTIONS IN POWER 2.6.1.2.4 REPORT MONTH June, 1977 (Over 20 Percent of Design Power Level and Longer Than Four : tours) RADIDACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE Refueling outage continues. 720 C 6/1/71-Summary: There was no single release of radioactivity or unusual radiation exposure specifi-cally associated with the outage which accounted for more than 10 percent oR the allowable annual values.

                  ~

T A-EQUIPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.6.1.3 Unit 3 2.6.1.3.1 Operating Experience Oconee Unit 3 was operating at 97 percent full power at the beginning of the month. Indications of small OTSG 1eaks were noted. On June 2, 1977, power was reduced to 94 percent full power to reroute moisten separator reheater drains to the hotwell to reduce secondary side activity. On June 9,1977, power was reduced to 70 percent full power due to a BTU limit alarm. Power was increased to 95 percent full power on June 10, 1977 , then the unit was shutdown due to a steam generator tube leak. Repairs were also made to the "3B1" reactor coolant pump. Normal power escalation began on June 27, 1977 with the unit reaching 99 percent full power by the end of the month. 2.6.1.3.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during June,1977.

1. Revisions 0,2,3,4,5,6,7,8,9,10 and 11 of Station Modification ON-306 were completed. The modification involves changes to the reactor cool-ant bleed and miscellaneous waste evaporators improve the operation of the Waste Management System. l I

l

2. Revision 0 of Station Modification ON-378 was completed. The modifica- '

tion involved the addition of isolation valves in the impulse lines of the generator core monitor. l

3. Revisions 0 and 1 of Station Modification ON-573 were completed. The I modification will improve the security system by adding magnetic locks I to the doors in the main guard house and in adjacent hallways.

4. Revisions OA,1 and 3 of Station Modification ON-698 were completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomics radiation monitoring system.

5. Revisions 0 and 1 of Station Modification ON-710 were completed. The modification upgraded the seismic quality of the 230 kV transformers at Keowee by adding restraints to the bases.

6. Revision 0 of Station Modification ON-713 was completed. The modification upgraded the seismic design of the 230 kV switching station relay house by

adding channels and connecting plates across the cable trench adjacent to the columns.

7. Revision 0 of Station hodification 0M-722 was completed. The mainstream radiation monitors, RIA-16 and 17,'were modified to improve check source operation.

2.6-8

8. Revision 1 of Station Modification ON-722 was _ completed. The modifica-tion involved the removal of tubes from service in the "3B" OTSG.

9. Revision 0 of Station Modification ON-825 was completed. The modifica.-

tion will connect electrical power to the planning trailer from IXGB switchgear compartment FZAB.

10. Revision 0 of Station Modification ON-830 was ccmpleted. The modifica-tion involved the installation of General Electric instrumentation in the "3B2" moisture separator reheater to collect data for generic stud-ies on reheater reliability. .

g 2. 6 ..

4 _.

                                         . r                                                                                                . . . .   .

MAINTENANCE HOUTil OF June 1977 UNITF 3 2.6.1.3.3 OCONdE UllCLEAR STATION A L HONTilLY DATA SilEET ZFFECT ON PRECAUTIONS

 'DPERATION'S                  - CO'TONENT                                                                                                              HALFUNCTION           SAFE                 CORRECTIVE ACTION                    FOR A'lE      NilMBER   IIANUFACTURER - MODEL/ SIZE                                                                                 W.R. NBR         CAUSE            RESULT  OPERATION                                            REACTOR SAFE P5rronnel Hatch            W. J. Wooley                                                                                                23475        Broken Not Oper. None       Replaced set screw anc None reg'd agt K s rew   "                                         key in gear geaOE             Proper.ly HP-3 Valve Rockwell                    Globe 2 1/2" 23328                                                                                 Loose             Leakage      None       Replaced Packing packing
    .HP-126          Velan              Stop Ck. 2 1/2 ' 20290                                                                                 Worn              B/B          None       Replaced Gasket &                       Unit off-
  ' Valve                                                                                                                                       Gasket             Leakage                            Repacked'                         line OTSG-           B&W                                                                                                          95892        Unknown           Leakage      None       Tube plugged

• Unit Down l tubes HP-140 Velan Globe 4" 22389 Packing Leakage None Repacked Unit Down FDW-149 Velan Globe *1/2" 20636 B/B Gaske-: Leakage None Repacked Unit Down RCS Root Velan Globe 20457 Packing Leakage Repacked Valves Velves PR-2 Pratt Butterfly 48" 23322 Broken Inoperable "

Replaced Diaphragm Not Reg'd Diaphram ,

                                                                                                                                                                               "                                                 Unit down RC-38           Velan Globe                                                      1"                                          23325        Worn plug         Leakage                 Replaced plug RC-74           Velan Globe                                          1/2"                                                    23327        Packing           Leakage       "

Repacked LPI-PMP .Ingersoll' Rand 23513 Worn Seal Leakage " Replaced Mechanical Seal FDW 23509 Worn Leakage " Replaced Gaskets " " Nozzle. . Gasket 3 1

DOCKET NO. 50-287 2.6.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH June. 1977 RADI0 ACTIVITY SYSTEM CORRECTIVE RELEASE OR CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE Power reduced to 70 percent full A 6/9/77-power to correct BTU limit alarm. The unit was shutdown from 95 per- 212.52 A RO 287/77-8 lubes were plugged. 6/10/77 Investigation of problem and cent full power to repair a leak in possible solutions in progress. the "3B" st.eam generator. Above outage extended to correct 178.61 A Condition corrected. 6/19/77 Iow oil level on reactor coolant pump.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of t'he allow-able annual values.

N A-EQUlPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION p B-MAINTENANCE OR TESTING F-ADMINISTRATIVE r. C C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

r -- J s 2.7 REPORT FOR JULY, 1977 i 2.7-1 ? v ,

b 2.7.1 OPERATIONS

SUMMARY

2.7.1.1 Unit 1 2.7.1.1.1 Operating Experience The month of July began with the unit at 100% Power. On July 5th the unit was taken of f line to repair a leaking coolant storage valve on the bleed transfer pump. The unit was returned to service on the same day. On July 6,1977, the unit reached 55 percent full power and remained at this power level to extend core life. On July 11, 1977, power was in-creased to 80 percent full power due to system load. On July 13, 1977, , power was increased to 86 percent full power due to system load. On July 21, 1977, power was increased to 90 percent full power due to system load. On July 30, 1977, power was decreased to 86 percent full power to extend core life. The unit remained at this power level the remainder of the month. 2.7.1.1.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during July,1977,

1. Revisions 3 and 4 of Station Modification ON-290 were completed. This modification to Warehouse No. 4 will provide for material storage under controlled conditions.

2. Revisions 10 and 11 of Station Modification ON-306 were completed. The modification involves changes to the reactor coolant bleed and miscel-laneous waste evaporators to improve the operation of the Waste Manage- l ment System.

3. Revision 0 of Station Modification ON-307 was completed. The modifi-cation will change the setting range of the SIW relay on Jocassee's black and white static relay panels to a more appropriate range.

4. Revision 0 of Station Modification ON-365 was completed. The modifi-cation involves the addition of flow orifices and differential pressure gauges with integral alarm switches to the component cooling lines to the reactor coolant pumps.

5. Revision 0 of Station Modification ON-648 was completed. The modifi-cation involves the addition of an interlock monitoring circuit to ACB #3 and ACB #4 interlock circuitry at Keovee to allow a pushbutton check of the interlock's operability.

6. Revision 0 of Station Modification ON-683 was completed. The modifi-cation involves changes to Keowee timing circuits to allow the key inhibit switch to be used when breaker maintenance is conducted.

7. Revision 0 of Station Modification ON-731 was completed. The modifi-cation involved the addition of columns inside the 230 kV switching station relay house to brace the concrete block walls. This modifi-cation will improve the seismic loading capability of the walls.

2.7-2.

- 8. Revision 0 of Station Modification ON-775 was completed. The modifi-cation involves the addition of " acknowledge" and " test" pushbuttons on the local statalarm panel in the Unit 1 and 2 electrical equipment room.

9. Revision 0 of Station Modification ON-776 was completed. The modifi-cation involves the removal of a 90' elbow upstream of the particu-late filter of RIA-48, -49, -44 and -45.

t l I l l l i

2. 7-3 /

l l-

     ...  .,--.3_.-.......                    ,. . - . .. . . . _ . .                     .    .          -

2.7.1.1.3 MAINTENANCE HONTl! OF JULY 1977 UNIT #1 OCONdE NUCLEAR STATION P GE M HONTIILY DATA SIIEET ZFFECT ON PRECAUTIONS

   .lP ERATION,' G                CO'!PONENT                                      HALFUNCTION          SAFE          CORRECTIVE ACTION         FOR VIE      Nitt;UEli      !!ANUFACTifRER - HODEL/ SIZE       W.R. NBR        CAUSE         RESULT   OPERATION                            REACTOR SAFE LPSW-18                  Walworth    Globe 8"              23854           Bad         Inoperable  None      Changed and Reset          None Switch                               Torque Switch            Required CCW-101                                                    23740       'Lobse Packing           Leakage     None   Tightened gland nuts        None Gland nut     s                                                  Required 6

e e

Cu .

     "2 DOCKET NO.          50-269 UNIT NAME         Oconee Unit 1 2.7.1.1.4               OUTAGES OR FORCED REDUCTIONS IN POWER g

REPORT MONTH July, 1977 (Over 20 Percent of Design Power Level and Longer Than Four hours) RADIOACTIVITY RELEASE OR CAUSE / SYSTEM OR CORRECTIVE ACTIONS RADIATION COMPONENT DURATION REPORTABLE EXPOSURE (HOURS) REASON OCCURRENCE NO. DATE' AFFECTED 10.22 A Valve repaired. 7/5/77 Unit was taken off line to repair a leaking coolant storage valve on the bleed transfer pump.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values.

A-EQUIPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMlHATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.7.1.2 Unit 2 2.7.1.2.1 Operating Experience Unit 2 was shut down for refueling until July 17, 1977. At that time, the outage was extended for maintenance on the steam generators. 2.7.1.2.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during July,1977.

1. Revisions 3 and 4 of Station Modification ON-290 were completed. This modification to Warehouse No. 4 will provide for material storage under

• controlled conditions.

2. Revision 10 and 11 of Station Modification ON-306 was completed. The modification involves changes to the reactor. coolant bleed and miscel-laneous waste evaporator to improve the operations of the Waste sanage-ment System.

3. Revision 0 of Station Modification ON-307 was evapleted. The modifi-cation will change the setting range of the SIW relay on Jocassee's black and white static relay panels to a more appropriate range.

j 4. Revisions 0, 3 and 5 of Station Modification ON-564 were completed. ' The modification involves the installation of additional orifices on first stage reheat supply piping to moisture separator reheaters.

5. Revision OB of Station Modification ON-530 was completed. The modifi-cation involves the installation of jib cranes above each reactor coolant pump cavity on the fourth level. The jib- cranes will eliminate the need to use the polar crane for reactor coolant pump maintenance.

6. Revision 0 of Station Modification ON-543 was completed. The modifi-cation involves upgrading the seismic design of Reactor Building miscellaneous access platforms MKA-16 and MKA-17.

4

7. Revision 0 of Station Modification ON-545 was completed. The modifi-cation will provide a source of permanent power to the Reactor Building sky climbers and will replace the existing electrical ' components and controls to meet outdoor requirements.

8. Revision 2 of Station Modification ON-605 was completed. The modifi-cation will revise the "D" heater emergency bypass piping to the con-

                                                                                                  ~

denser to' allow the "D" flash tank to properly dump to the condenser.

9. Revision 0 of Station Modification ON-644 was completed. The modifi-cation iuvolves the' replacement of Velan valve 2FDW-ll5 with an Orbit valve.

10. Revision 0 of Station Modification ON-643 was-completed. The modifi-cation involves the addition of an interlock monitoring circuit to ACB #3.and ACB #4 interlock circuitry.at Keowee to allow a pushbutton check of the interlock's operability.

1

                                                                   -2.715
      .                         _                            _ ...       ~   . . ~                  _ _ __ __ ,- . -

11. Revision 4 and 5 of Station Modification ON-681 was completed. The modification revises hydraulic suppressors on the main steam valves by removing fixed bleed orifice plugs from the snubber valve.

12. . Revision 0 of Station Modification ON-683 was completed. The modifi-so tion involves changes.to Keovee timing circuits to allow the key.

inhibit switch to be used when breaker maintenance is conducted.

13. Revisions OB and 1 of Station Modification ON-705 was completed.

The modification involves the installation of instrumentation to provide positive indication that flow exists in at least one boron . dilation drain line. Revision 0 of Station Modification ON-723 was completed. The modifi- - 14. cation involved the installation of a vent line with an isolation valve from the heater drain pump casing to a high point on the side of the heater to assure water to the suction of the pump. l The modifi-

15. Revision 1 of Station Modification ON-726 was completed.

cation will allow proper operation of signals to the "CRD Trouble" annunciator until these power signals can be modified to allow their failure detectors to work properly. i The modifi-

16. Revision 0 of Station Modification dN-727 was completed.

f cation involves the addition of two corrosion resistent bushings to the lever and one to the solenoid of valve RC-66, pressurizer electro-matic relief valve, to ensure free motion 'of the lever pin. i The modifi-

17. Revision 0 of Station Modification ON-731 was completed.

cation involved the addition of columns inside the 230 kV switching station relay house to brace the concrete block walls. This modifi- ! cation will improve the seismic loading capability of the walls.

18. Revisions OA and OB of Station Modification ON-749 were completed.

i The modification involved the replacement of high pressure injection valve 2HP-204, with a Kerotest valve.

19. Revision 0 of Station Modification ON-758 was completed. The modifi-cation involves the replacement of type "HGA" relays in the thrust r

bearing wear detector circuitry of the turbine control system with type "MRD" relays and the addition of a key switch :to disable the

             -thrust bearing wear detector trip during testing.

i

20. Revision 0 and 1 of Station Modification ON-768 was completed.- The modification provides for an increase in capacity and temperature rating of the control-rod drive structure cooling fans.

21. Revision 0 of Station Modification 05-776 was completed. The modifi-cation involves 'the removal. of 90 degree elbows upstream of the particulate filters of RIA -48, -49, -44 and -45. 4

2. 7-6 i

22. Revisions 0-and 1 of Station Modifica. ion ON-794 were completed. The modification will revise the sprocket set screw arrangement on the fuel transfer system drive motor to prevent the sprocket key from working loose.

23. Revisions 0 and 1 of Station Modificat ion ON-814 was completed. The modification changes the Administratitn Building ventilation system by adding a supply duct to the whole tody count room from the canteen area.

24. Revisions OA, 1, 2 and OB of Statica Mcdification ON-845 were completed.

The modification involves the installation of data collection instru- . mentation in the "2B" steam generator.

25. Revision 0 of Station Modification ON-855 was completed. The modifi-cation involved the removal from service of tubes in the "2B" OTSG.

26. Revision OA of Station Modification ON-856 was completed. The modifi-cation will temporarily install thermocouples on the control rod drive service structure for air temperature monitoring and will provide an alarm for high temperature.

27. Revision 0 of Station Modification ON-861 was completed. The modifi-cation will remove a section of SPND #49 in location M-14 and will seal the end of this incore detector tube.

28. Revision 0 of Station Modification ON-871 was completed. The modifi- l cation involves the installation of a steel plate on the bottom of the "2A2" moisture separator reheater first stage tube bundle to prevent tube bundle erosion.

29. Revision OA ?.nd OB of Station Modification ON-872 was completed. The modification involves drilling a hole in the "2B" OTSG to retrieve a dropped instrument. Safety implications were evaluated and the modification was found to have no adverse affect on nuclear safety.

l e 2.7-7

I

  ...Q,..._,.....

JULY 1977 UNIT # 2 MONTII 0F MAINTENANCE 1 2 OCONEE NtlCLEAR STATION PAGE d 2.7.1.2.3 MONTilLY DATA SilEET PRECAUTIONS ZFFECT ON CORRECTIVE ACTION FOR MALFUNCTION SAFE OPCIMTION'S _ COWONENT REACTOR SAFE CAUSE RESULT OPERATION

              , Hl4;BER   IIANUFACTliRER - HODEL/ SIZE      W.R. NBR 4A?!E None   Tighten Packing          Unit Down Globe 8"          23885   Loose             Leakage LPSW-18               Walworth                                       Packing CF-2                                                       23222     , ",                 "

12974 Bad Gasket

                                                                                            "         "     Replaced Gasket BS-1 Aloyco              Globe        8" 23808   Flange
                                                                                            "         "     Replaced & Ret rqued LPI "A"                                                                                                            Gasket

• Gasket Wor a Cooler ,

RBCU 52929 Motor Burned Repaired Motor Out Inoperable Motcr 2C 52928 Motor Inoperable Burned Out . Motor 2A Grinnell 3" 24144 Broken Pin Repalced shear pin in CS-67 in Valve Inoperable Handle val'e v handle Not working " Readjusted Leslie 2 1/2" 23203 Out of HP-7 Adjustment Properly T:ndon Cap 90968 Bad Caps Leakage " Replaced plugs Leakage . " " Leakage

                                                                                                         "   Relapped seat MS-92                Lonergan           3"X4"              19806   Worn Seat 23825   Bad Weld
                                                                                            "            "   Rewelded Aloyco             Globe        6" LP-95                                                                                                                                  "          "

Cleaned and restroked

                                                                                                                  ~

6" 18183 Out of Not operating " MS-93 Flowline correctly k Stroke w o, .

MAINTENANCE MONTil 0F July 1977 UNIT # 2 2.7.1.2.3 OCONEE NUCLEAR STATION MONTiiLY DATA SilEET PAGE 2 of 2 ZFFECT ON PRECAUTIONS iPERATION'S COT ONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR VIE NiitlBER MANUFACTURER - MODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION RFACTOR SAFE' FDW-37 Crane Check 24" 20484 Hinge Pir Leakage " Replaced Hinge Unit Down Gasket Pin Gasket

                                                                                                                                                                         "             "                                                   Unit Down LP-95               .Aloyco Globe                                                       6"                              23882         Packing                                                             Tighten Packing Instrument                                                                                                                                                                                                                                 "    "

Valve Velan 20416 " " " Repacked

                                                                                                                                                                                                                                  ~

LP-96 Globe , Velan 2" 23060 Inntru Icol Velan 22677 . . Valve , Iristru Iso 1 Velan 22676 Velve Instru Isc 1 Velan . 23218 Valve S t N O

DOCKET NO. 50-270 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 2.7.1.2.4 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT HONTH Juiv 1977 RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE Continuation of refueling outage 384 C 7/1/77 Instrument inadvertently Extension of outage for maintenance 360 B 7/17/77 dropped into steam generator on the steam generators retrieved.

SUMMARY

there was no single release of radioactivity or unusual radiation exposure specifically associated eith any outage which accounted for more than 10 percent of the allow-ible annual values.

w A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMlHATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN) i e

i 2.7.1.3 Unit 3 2 . 7 .1.3 .1 Operating Experience The unit operated at 99 percent full power until July 7,1977, when a high chloride concentration in the reactor coolant system resulted in a power decrease to 48 percent full power. The condition was corrected and power l was escalated to 88 percent full power due to waste bleed volume. Power I was increased as waste problem was corrected and by July 14, 1977, the unit reached 97 percent full power.  ; On July 14, 1977, the unit was shut down to repair a t 'a leak in the "3B" OTSG. The unit was brought back on line on July 27,197. , and reached 60 .l percent full power that same day. Power was held at this level to allow waste processing. On July 30, 1977, power was increased and 89 percent full power was reached by the end of the month.  ; 2.7.1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during July, 1977.

1. Revisions 3 and 4 of Station Modification ON-290 were completed. This modification to Warehouse No. 4 will provide for material storage under controlled conditions.

2. Revision 10 and 11 of Station Modification ON-306 was completed. The modification involves changes to the reactor coolant bleed and miscel-laneous waste evaporators to improve the operation of the Waste Management System.

3. Revision 0 of Station Modification ON-307 was completed. The modifi-cation will change the setting range of the SIW relay on Jocassee's  ;

black and white static relay panels to a more appropriate range.  !

4. Revision 0 of Station Modification ON-545 was completed. The modifi-cation will provide a source of permanent power to the Reactor Building sky climbers and will replace the existing electrical components and controls to meet outdoor requirements.

l S. Revision 0 of Station Modific ition ON-648 was completed. The modifi-  ; cation involves the addition of an interlock monitoring circuit to ACB #3 and ACB #4 interlock circuits.

6. Revision 0 of Station Modification ON-663 was completed. The modifi-cation added ductwork to the ventilation system to provide fresh air to operating personnel in the Interim Waste Building.

i

7. Revision 0 of Station Modification ON-683 was completed. The modifi- '

cation involves changes to Keowee timing circuits to allow the key inhibit switch to be used when breaker maintenance is conducted. 1

                                        - 2. 7-9 j

T

8. Revision 1 of Station Modification ON-726 was completed. The modifi-cation will allow proper operation cf signals to the "CRD Trouble" annunciator until these power signals can be modified to allow their failure detectors to work properly.

9. Revision 0 of Station Modification ON-731 was completed. The modifi-cation involved the addition of columns inside the 230 kV switching sta ton relay house to brace the concrete block walls. This modifi-cation will improve the seismic loading capability of the walls.

10. Revision 0 of Station Modification ON-776 was completed. The modifi-cation involves the removal of 90 degree elbows upstream of the particulate filter of RIA -48, -49, -44 and -45.

11. Revision OA of Station Modification ON-820 was completed. The modifi-cation involved changing the turbine main stop valve test logic to incor;. orate sinrtitaneous testing of MSV-1 and MSV-3 together, and MSV-2 and MSV-4 together.

l l i i l I 2.7-10

2.7.1.3.3 itAINTENANCE MONTil 0F Uti1T# OCONdK NUCt.EAll STATION PACE of 110NTill.Y DATA SilEET dFFECT ON PRECAlTTIONS OPERATION'S, COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR lA'IS HigyH tlANUFACTURER - MODEL/ SIZE W.R. NBR CAUSE RESIILT OPERATION REACTOR SAFE EPI Seal Supply Fluid Dynamics 23794 Worn Leakage None Replaced Gasket None Reg.

     ' Filter                                                 Gasket Nitrogen                                                                                                      .

4 Valve-233 22053 Bad Packirg and gaske t Leakage None Replaced Gasket and None Req. packing. . OTSG Tube BLW

• 95937 Unknown Leakage None

        #1 & 42                                                                                          Welded stabilizer Row 77                                                                                            plugs in tubes # 1&2      Unit Down OTSG    .
                   .B&W Main Fdw                                 24019     Worn             Leakage       None            Replaced gaskets        Unit Down Nozzle                         .                   Gaskets e

S e Y

        ~

o t,a w.

s DOCKET NO. 50-287 UNIT NAME Oconce Unit 3 2.7.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT MONTH July 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours)

                        ~

RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE ___ Forced reduction in power from D Condition corrected 7/7/77 99 percent full power to 48 percent full power to correct high chloride concentration in reactor coolant system Unit was shut down from 97 per- 292.28 A RO 287/77-10 Tube leak repaired. Investi- -

~7/14/77                                                                               gation of-cause and solutions cent full power due to a tube                                             in progress.

leak on the "3B" steam generator Unit held at 60 percent full 11 Power was increased as waste , 7/27/77 situation permitted. I power due to waste processing volume. A-EQUlPMENT FAILURE (EXPLAIN) E-OPERATOR TRAlHING Ahl LICENSi EXAMitlAllCN B-MAINTENAtlCE OR TESTING F-ADMINISTRATIVE

 'f C-REFUELING                      G-0PERATIONAL ERROR (EXPLAlH)

C D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

i V h 2.8 REPORT FOR AUGUST, 1977 l l 1 l l 2.8-1 1 1 I ~ . - - _ .

2.8.1 OPERATIONS

SUMMARY

2.8.1.1 Unit 1 2.8.1.1.1 Operating Experience The unit.was at approximately 85 percent full power at the beginning of the month. On August 2, 1977, power was reduced to approximately 83 percent full power until August 5, 1977. On August 5, 1977, the unit was shut down for refueling and remained shut down for the remainder of the month. 2.8.1.1.2 Changes, Tests and Experiments not Requiring Prior NRC Approval ~ The following changes, tes* and experiments were carried out without prior NRC approval pursuan_ to 1GCFR50.59 during August, 1977.

1. Revision 2C of Station Modification ON-370 was completed. The modifi-cation deleted the auto-start creep function on the reactor coolant ,

pumps oil lift AC circuits and added a three minute time out on the DC lift pumps. This change will facilitate the control and monitoring  ! of the oil lift pump operaticn. 1

2. Revision 0 of Station Modification ON-537 was completed. The modifi-cation involves the installation of thermocouple wells in each pipe carrying low pressure service water to and from the Reactor Building j cooling unit.

3. Revision 2 of Station Modification ON-559 was completed. The modifi-cation will effectively disable the by-pass dampers on the Reactor -

Building purge filters and seal the exit of the bypass to prevent leakage.

4. Revision 0 of Station Modification ON-622 was completed. The Auxiliary Building wall was modified to allow access to the change room of the hot machine shop from outside of the Auxiliary Building.

5. Revision 0 of Station Modification ON-626 was completed. The modifi-cation involved rewiring the bridge circuits and adding mechanf cal bumpers' to the fuel transfer bridge.

6. Revision 0 of Station Modification ON-646 was completed. The modifi-cetion provides a signal from the Electro-Hydraulic Control System to close the moisture separator reheater drain valves to the condenser during the turbine shell warming mode of operation.

7. Revision 0 of Station Modification ON-661 was completed. The modifi-cation involved the installation of a climbing safety device on both of the spent fuel pool decontamination pit ladders.

8. Revisions 2 and 3 of Station Modification ON-681 were completed. The modification revises hydraulic suppressors on the main steam valves by removing fixed bleed orifice plugs from the snubber valve.

2. 8-2 1

9. Revision 0 of Station Modification ON-695 was completed. The modifi-cation will add flush connections to various locations in the low pressure service water system.

10. Revision 2 of Station Modification ON-717 was completed. The modifi-cation involves the installation of separate control room alarms for pH control at the oil retention pond and waste water collection basins.

The alarms will have reflash capability,

11. Revision 0 of Station Modification ON-742 was completed. The modifi-cation will delete the "Dekoron" trace heating on tha process lite of the borated water storage tank lesel instrumentation. " Nelson" trace heaters will be installed to improve the reliability of the ,

equipment .

12. Revision OD of Station Modification ON-751 was completed. The modifi-cation replaces valves SD-19, SD-20 and SD-70, steam drain ' alves, with Kerotest valves.

i

13. Revision 0 of Station Modification ON-759 was completed. The modifi-cation involves the addition of a fif ty millisecond time delay in the fast acting intercept valve circuits of the turbine control system to prevent noise spikes.

l

14. Revision 0 of Station Modification ON-796 was completed. The modifi-cation removed a section from the inside corner wall of the entrance to the letdown storage tank to provide easier access to :he area.

15. Revision 0 of Station Modification ON-836 was completed. The modifi-cation involved the rerouting of drains to the condenser instead of l

• - the blowdown tank.

16. Revision 0 of Station Modification ON-854 was completed. The modifi-cation involved the replacement of the existing drain plug on the hydraulic tanks of the fuel handling equipment with a quick disconnect plug.

l 17. Revision OB of Station Modification ON-858 was completed. The modifi-I cation provided water, electricity, public address and telephone services to the security and canteen trailers.

18. Revistor O of Station Modification ON-864 was completed. The modifi-cation involved changes to the feedwater temperature circuits of the Integrated Control System, c

l 2.8-3

          ..             ___ _       -- - -- ~                                       .mm.as m z a ~. .. .. ..  . . - . w 4   w - - w--     ---      - -

w -- --. -.g MAINTENANCE MONTil 0F August 197% NIT # 1 2.C.1.1.3 OCONEE' NUCLEAR STATION MONTIILY DATA SilEET PACE 1 of 3 5FFdCT ON PRECAUTIONS (;PERATION' S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR AME NUMBER MANUFACTURER - MODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFETY MS-92 Lonergan Relief 6" 19351 Worn Seat Leakage None Relapped Seat Ref. Outage MS-103 Turb. Stop Valve 2" 23008 Loose Pkc Leakage None Adjusted Packing Ref. Outage HP-71 Lonergan f 24107 Worn Leakage ,None Replaced Gasket " " Gasket ea ag N ne Repacked " " HP-65 Globc Velan 1/2 25112 Worn Packing LP-2 Walwo'rth Gate 12" ' 17835 Loose Leakage None Repacked " " Packing LP-1-' Walworth Gate 12" 17834 Bad Leakage None Repacked " " Packing RB Pers. W. J. Wooley 24696 Out of Not closing None Adjusted Cable and " " Hitch Doon Adjustment properly Ratch Paws Intarlock, i . Ralief V. Lonergan Relief Valve 22681 Worn Gaske t Leakage None Replaced Gasket & " " on HPI Sys & Stem Stem CS-- 6 9 Grinnell 3/4" 24129 Worn Piapl' " " Replaced Gasket " " } , Gasket P LPI-18 Welworth

• Gate 10" 24996 Bad Pkg. Leakage "

Repacked " " LP-94 Aloyco Gate 6" 18795 Bad .-kg. Leakage " " " " RC-43 Velan Globe 1 1/2 '24952 Bad Pkg. Leakage

• CC-24 Crane Swing Check 6" 91065 B/B Gasket " "

Replaced Gasket " " RC-36 Velan Globe 1" 24951 Bad Pkg. " " Repacked " " RC-16 i Velan Gate 1" 24957 Bad Pkg. " " Repacked " " E

• HP-120 Ieelie Globe 2 1/2 '24673 Worn Seat " "

Lapped Seat " " 4

 %--               -m   u__    m  ____a_m _ . m       - - - _ _ _ -         .-

                                                                                                     " ~ - -
, ,.4 v e6me.eS hddSea 6m sp 40 m wu asess amansh. .. .                                                                                August 197i UNIT #                1 HOLTil OF 2.8.1.1.3                              MAINTENANCE OCONEE NUCLEAR STATION                                               PAGE 2       of 3 MONT!!LY DATA SilEET                                                            PRECAUTIONS EFFECT ON CORRECTIVE ACTION             FOR HALFUNCTION                   SAFE COMPONENT                                                                                                                    REACTOR SAFETY

'OPFRATION'S CAUSE RESULT OPERATION MANUFACTURER - MODEL/ SIZE W.R. NBR IAME NUMBER Lapped Seat Re f. Outage Leakage None Nitrogen Globe ' 1" 24470 Worn Seat

   #130 Valv(

None Lapped Seat Ref. Outage Globe 1" 23901. Worn Seat Leakage GWD-58 Velan ,

                                 'Che             6"      24198!           Worn              B/B                                                          "             "

FDW-101 Crane Gasket Leakage None Replaced Gasket 23182 Worn Seat Leakage None Replaced Gasket MS-140 .Lonergan Relief Worn Part s Running None Replaced Motor RBCU Mtr  !

                                                      '   17967 high amps l                                                                                                              "             "

90856 Bad Leakage None Replaced Washers

• i T5ndon Washers Caps. . ,

Ilinge Pin Leakage None Install New flinge Pin FDW-48 . Crane Check f" 22206, Gasket Gasket ,

                 .' G:E. . Supplied Valve t

16993- Seal Leakage None Replaced Seal Gasket

• MS ,

Gaskets i Lapped Seat HP-71 Relief Valve , 22161; Worn Seat Leakage None Worn Leakage None uoose Packing RC-46 Velan Globe " 25953 , Packing i " " 25669 Worn Leakage None Lapped Seat GWD-153 . Velan Globe 1" . Seat Gate 8" 25128 Worn

                                                                                                   "             "        Replaced Packing LPI-l            Crane Packing
                                                                                                                 "             =           a                a             a LPI-ll           Crane          Gatelh"                  25121 a
              ."                                 i                     ,
                                                                              "                    "             a              a          a                a BS-13     T      Crane          Gate        8"           25117
                                                                                                                                                            =             =

U " " " " = MS-79 Crane Gate 12" 23946

idad MMhaeMlaChassaatanadsata4u.w.. ... . -

                                                                                                                                                                                             ..u.t..aa,wm                            m & - -- -      - - --
                                                                                                                                                                                                                                                                            ._ . . L. . .
                                                                                                                                                                                                                                                                                           .g 2.8.1.1.3                                                                                              MAINTENANCE                                                 MONTH OF August 1977       UNIT #1 1 OCONEE NUCLEAR STATION MONTi!LY DATA SIIEET PACE 3 of    3 EFFECT ON                                  PRECAUTIONS OPERATION'S                     COMPONENT                                                                                                                                             MALFUNCTION                               SAFE             CORRECTIVE ACTION               FOR AME   NUMBER         NNUFACTURER - HDDEL/ SIZE                                                                                                                 W.R. NBR            CAUSE                     RESULT ~        OPERATION                                 REALTOR SAFETY i

CS-65 Grinnell 2" 23285 Diaphragm Leakage None Replaced Diaphragm Ref. Outage

                    .                                                                                                                                                            Leak MS-24          Crhne                          Gate                                                                             6".                           .

23015; B/B Leak " " Lapped Seat " " I i HP-27 hobkwell/EdwardGlobeI4" 24994 Bad Pkg " " Repacked " " s 3 HP-26 Rockwell/ Edward Glopei4" 24993 Bad Pkg. " " " " " t i RCP

• s Root Valve " "

24959. Bad " " "

                                                                                                                                                                                . Packing

> i . i i j . t t s i I .! W 4

DOCKET NO. 50-269 UNIT NAME Oconee Unit 1 2.8.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT NONTH August 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE. OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE 8/5/77 Refueling Shutdown 633.92 C Summary: There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allowable annual values. T 4- A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTlHG F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAlH) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

4 g 4++$> ,

                                      ,    h
               . eE Ev <e 1,em TEST TARGET (MT-3)
                                       $<s' 1.0   lg m an y ((3 IH4 1.1   i "3 Ea
                                  .8 1.25 ' l.4    1.6 4                     6" MICROCOPY RESOLUTION TEST CHART
  %                                      ++//p 4%

• $f'%

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I.8 1.25 1.4 1.6 l-m. MICROCOPY RESOLUTION TEST CHART 4% '4

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                             ,; E3 H==a =

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                     --              1.8 1.25     1.4    1.6 l
   <                        6"               >

MICROCOPY RESOLUTION TEST CHART

#%                                            sp f                                  #$+h[

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     ?

9. Revision OC of Station Modification ON-749 was completed. The modifi-cation involved the replacement of liquid waste disposal valve 2 LWD-230 with a Kerotest valve.

Revisions 0 and 1 of Station Modification ON-765 were completed. The 10. modification involved the installation of target rock solenoid operated valves in place of existing pressurizer spray valve 2RC-1,

11. Revision 0 of Station Modification ON-770 was completed. The modifi-cation revised the pneumatic control system to the second s,tage moisture separator and reheater.

                                                                                                  ~

The modifi-

12. Revision 0 of Station Modification ON-779 was completed.

c,ation extended the existing reactor vessel lifting cable storage platform to enhance personnel safety. The modifi-

13. Revision 0 of Station Modification ON-796 was completed.

cation removed a section from the inside corner of the entrance to the letdown storage tank to provide easier access to the area.

14. Revision 0 of Station Modification ON-801 was completed. The modifi-cation involves the installation of viscosity type upper bearing thrust runner pumps to replace the present centrifugal type pumps.

15. Revision 0 of Station Modificati;a ON-837 was completed. The modifi-cation involved the installation of a resistor in the output of feed-water pump turbine vibration monitor to cut the maximum current seen by the monitor.

16. Revision OB of Station Modification ON-858 was completed. The modifi-cation provided water, electricity, public address and telephone services to the security and canteen trailers.

17. Revision 0 of Station Modification ON-896 was completed. The modifi-cation revised the position of 2HP-66, the reactor coolant pump "2Bl" seal injection throttle valve, and the piping around the valve.

18. Revision 0 of Station Modification ON-897 was completed. The modifi-cation will 12 move the center control rod drive vent and line to vent tank and install a regular control rod drive cap. .

4 m 9 9 2.8-6 i

MAINTENANCE MONTil 0F AUGUST 1977 UNIT # 2 2.8.1.2.3 OCONdE NUCLEAR STATION PAGE 1 of 2 MONTill.Y DATA SilEET 2FFECT ON PRECALTIONS OPERATION'S, Cf4PONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR lA'E THIMEElt PIANUFACTURER - MODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFE LP-39 Velan Globe 3/4" 24526 Worn Leakage None Tightened Packing Unit Down Gasket CF-1 Walworth Gate 14" 24936 Worn Leakage None Adjusted Packing Packing HP-285 Kerotest Globe' 1 1/2" 24785 Cracked Leakage None Replaced Stem Assembl /

                                          .                                 Seat                                    and lapped seat MS-33               Crane          , Gate          6"           24799     Loose           Leakage   None      Repacked
                                                                .           Packing LP-73             Crane           Gate            8"           24525     Loose           Leakage   None      Tightened Packing Packing MS-102             Crane           Stop Va]ve                   24557     Bad                "

Repacked Packing " " Packing , MS-105 . Crane Stop Valve 24558 MS-104 Crane Stop Valve 24559 MS-103 24560 MS-83 Crane Check 6" 24521 ." R.B. Pers. IIatch ' W. J. Wooley 90961 Str'etchec " " Installed shim under " '" Gasket gasket NI-l Detcctor Westinghouse 24135 Detector Failed low Replaced detector HP-66 Velan Globe 24940 Inoperable " Replaced Valve GWD-59 Velan Globe 24618 Worn Seat Leakage Replaced diaphram

            ."                                                                                                 & Lapped Seat GWD-581          Velan                  Globe           1"      24647                          "

Lapped Seat

            ?

August M UNIT # MONTil OF 2.8.1.2.3 Malt 1TFilANCE OCOtidE tilICLEAR STATION PAGE 1, of 2 MONTill.Y DATA SilEET PRECALTs10NS

              ~

IFFECT ON CORRECTIVE ACTION FOR MALFUt!CTION SAFE OPERATION'S COIPONENT REACTOR SAFE W.R. NBR CAUSE RESULT OPERATION IMIF. Till!;BEli IIANUFACIIIRER - MODEQSIZE 24801 Broken Inoperable None Replaced Stem Unit Down LWD-230 Velan Globe Stem 24619 Broken Inoperable None Replaced stem & whee l LWD-229 Velan Globe 1" 11andwheel ,

                                                   "               "                        1" 24644    Worn            Leakage       None   Lapped      Seat GWD-54 Seat 23379                     Smoking              Replaced Motor LP-21                    Rockwell                   Gate                        14"            Motor Burned out 20487    Worn            Leakage              Replaced Valve RC-68                Velan                        Globe Seat
                                                     "                          "               20486    Worn            Leakage              Replaced Velve RC-67                                                                     -                    Seat HP-66                                                                                24765     Weld Leak Leakage                   Repaired Weld Piping 16751     Broken         Leakage CBAST Tank Weld o

y 8*

                 ?

DOCKET NO. 50-270 2.8.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME O conee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH August 1977 SYSTEM RADIDACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 4 8/1/77 Outage continued due to steam 663.58 A generator maintenance, control rod drive stator failures and

         'other maintenance.

Sununary: There was no single release of radioactivity or unusual radiation exposure , specifically associated with any outage which accounted for more than 10 percent of the allowable annual values. [ A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION 0-MAINTENANCE OR TESTING F-#DMINISTRATIVE C-REFUELING G-0PERATIONAL ERROR (EXPLAlH) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.8.1.3 Unit 3 2.8.1.3.1 Operating Experience The month of August began with the unit holding for Xenon equilibrium at 91 percent full power. On August 2, 1977, 100 percent full power was reached and the unit remained at this power level until August 20, 1977. At this time while performing a control rod movement test rod 2 group 3 dropped inte Power was reduced to 50 percent full power.

 'the core due to a shorted stator.

The unit was shut down the same day to repair the stator. On August 22, 1977 Power was increased to 57 percent full the unit was returned to service. power. At this point the "3B" feedwater pump turbine tripped. Power remained - at approximately 57 percent until August 24, 1977 when power escalation was commenced. On August 25, 1977, 100 percent power ess reached but on the same day the "3B" feedwater pump turbine tripped again and the unit ran back to 60 percent full power. On August 26, 1977 power was increased to 100 percent full power and remained at this power level the remainder of the month. 2.8.1.3.2 Changes, Tests and Experiments not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NBC approval pursuant to 10CFR50.59 during August, 1977.

1. Revision 2 of Station Modification ON-559 was completed. , The modifi-cation will effectively disable the bypass dampers on the Reactor Building purge filters and seal the exit of the bypass to prevent leakage.

2. Revision 0 of Station Modification ON-622 was completed. The Auxiliary Building wall was modified to allow access to the change room of the hot machine shop from outside of the Auxiliary Building.

3. Revision 0 of Station Modification ON-695 was completed. The modifi-cation will add flush connections to various locations in the low pressure service water system.

4. Revision 0 of Station Modification ON-742 was completed. The modifi-cation will delete the "Dekoron" trace heating on the process line of l

the borated water storage tank level instrumentation. " Nelson" trace heaters will be installed to improve the reliability of the equipment.

5. Revision 2 of Station Modification ON-772 was completed. The modifi-cation will remove tubes 1 and 2 of row 77 of the "3B" steam generator l

l by stabilizing the upper ends and explosively plugging the lower ends. The

t. Revisions 0 and 1 of Station Modification ON-791 were completed.

modification involved the replacement of all concentrated boric acid storage tank batch counters with a newer model.

7. Revision 0 of Station Modification ON-796 was completed. The modifi-cation removed a sectinn from the inside corner of the entrance to the letdown storage tank to provide easier access to the area.

8. Revision OB of Station Modification ON-858 was completed. The modifi-cation provided water, electricity, public address and telephone ser-vices to the security and canteen trailers.

2.8-8

2.8.1.3.3  ?!AINTENANCE }iONTil OF

• AUGUST 1977 tRJITil 3 OCONdE NilCl. EAR STATION 1 MONTilLY DATA SilEFT PACE 1 of

[FFECT ON PRECAUTIONS-OPERATION'S, CO'iPONENT MALFIR1CTION SAFE CORRECTIVE ACTION FOR '91'IE UllfiEER IIANUFAC'llfRER - liODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFE Trt;ns forme c Worn Leakage 3 X 10 24358 Bushings of Freon None Added Freon Gas None Reg'd CS-65 Grinnell Diaph 2" 24325 Bad Diaph. Leakage None Replaced Diaphragm " " CBAST Pmp Accumulat 3r Sharp Control 20774 Bad Seal Leakage None Installed new accumulator None Req'd CBAST Lapp 24718 Bad Coup- Excessive Pmp 3A ling noise None Replace bad coupling None reg'd HP-64 Velan. Globe 1/2" 24857 Loose Packing Packing Leak None Adjusted packing None reg'd RC-43 Velan Globe 1 1/2" 23969 Cracked LeaRage " Repacked valve. To be Unit down Seat Replaced during refuel . RC-45 Velan Globe 1 1/2" 23970 Cracked Leakage " Repacked valve. Valve Unit down Seat to be replaced during refueling. CBAST Lapp 11940 Worn parts Inoperable " Replaced pump parts " " Pmp. ' 4 w

  'h r

DOCKET NO. 50-287 UNIT NAME nenng, unt, 1 2.8.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT NONTH Anguar 1977 RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DyRATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE Stator was repaired Unit was shut down from 100 percent 35.59 A 8/20/77 full power due to a failed stator in control rod 2 group 3. Summary: There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allowable annual values. A-EQUIPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMINATION Y

• B-MAINTENANCE OR TESTlHG F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

s a 2.9 REPORT FOR SEPTEMBER, 1977 1 1 1 o G 9 2.9-1 i

2.9.1 OPERATIONS

SUMMARY

2.9.1.1 Unit 1 2.9.1.1.1 Operating Experience The unit was in refueling shutdown at the beginning of the month. -Required maintenance and periodic testing were in progress. Refueling was completed on September 17, 1977. The outage was extended for maintenance on the steam generators until September 27, 1977. Preparations for unit startup, includ-ing completion of maintenance and periodic testing, were in progress for the remainder of the month. . 2.9.1.1.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during September 1977.

1. Revisions lA, 4, and 5 of Station Modification ON-246 were completed. The modification involved the replacemi nt of low pressure injection ILP-14 ,

with Fisher Vee-Ball valves.

2. Revision 2 of Station Modification ON-379 was completed. The modification recessed the radial retainer clips on the thrust runner air seal in the reactor coolant pump motor oil system into the thrust runner seal housing to prevent the fretting of the seal ring and the loss of oil from the upper oil pot.

3. Revisions 0A, 1, 8 and 9 of Station Modification ON-502 were completedd. The modification replaced and relocated , valves RC-4 and RC-66 to increase the reliability of these valves.

4. Revision 0 of Station Modification ON-529 was completed. The modification.

changed the 1900 and 2000 ohm resisters on GE ET-16 indicating lamps to 2550 ohm resisters.

5. Revision 0 of Station Modification ON-545 was completed. The modification provided a source of permanent power to service the Reactor Building sky climbers by replacing the existing electrical components with weatherproof electrical components.

6. Revision 0 of Station Modification ON-594 was completed. The modification l involved the inspection of all General Electric type HFA and HGA relays '

at Oconee Nuclear Station including those at Keowee Hydro Station and replacement of defective relay coils.

7. Revisions 0,1 and 2 of Station Modification ON-605 were completed. The '

     "D" heater emergency bypass piping to the condenser was modified to allow the "D" flash tank to properly dump to the condenser.

l

2. 9-2

 . S. Revision 9 of Station Modification ON-635 was completed. The modification involved the installation of a feedback mechanism which will assure that the setpoint for the flowrate of liquid waste discharged from the station is not exceeded.

9. Revision 0 of Sta, tion Modification ON-659 was completed. The modification involved the installation of ground level pressure gauges to indicate SFThismodifica! io gas pressure inside electrical penetrations EMB-1 and -2.

will assure personnel safety when reading the gauges. Revision 1 of Station Modification ON-665 was completed. The modification 10. involved the installation of thermocouples on turbine bearings to indicate - the temperatures of the bearings. The

11. Revisions OB, 2 and 4 of Station Modification ON-698 were completed.

modification involved the replacement of RIA-33 and RIA-34 with a General t Atomics radiation monitoring system.

12. Revisions OA, OB, 2 and 3 of Station Modification ON-705 were completed.

The modification involves the installation of instrumentation to provide positive indication that flow exists in at least one boron dilution drain line.

13. Revision 0 of Station Modification ON-706 was completed. The modification involved the installation of an acrylic collimator on the face of the scintillation crystals of RIA-47 and RIA-49, the Reactor Building airborne activity monitors.

14. Revision 0 of Station Modification ON-735 was completed. The modification involved the addition of fuses to protect the 0.5 KVA transformer which supplies power to the cooling fans for the pressurizer heater control cir-

' cuits.

15. Revision 0 of Station Modification ON-740 was completed. The modification involved the installation of a locking device on the Keowee governor sole-noid cap screw to prevent the cap screw nut from backing off. The modifi-cation was done at the manufacturer's recommendation.

Revisions OC and OB of Station Modification ON-748 were completed. The 16. modification involved the replachment of valves NI-116, nitrogen 1HP-285, supply to quench tank, NI-128, nitrogen supply to core flood tank "A", seal supply to RCP "Bl" outside stop check valve and 1HP-147, seal supply to RCP "B1" stop check valve with Kerotest valves.

17. Revision 0 of Station Modification ON-758 was completed. The modification involved the replacement of all General Electric type HGA relays in the thrust bearing wear detector test circuit and the addition of a key switch to disable the thrust bearing wear detector trip during the turbine trip test.

2.9-3

18 c m.1-fon a of Station Modification ON-770 was completed. The modification _aviset the pneumatic control system to the second stage moisture separator and rehe.ter.

19. Revision 0 of Station Modification ON-801 was completed. The modification involves the installation of viscosity type upper bearing thrust runner pumps to replace the present centrifugal type pumps.

20. Revision 0 of Station Modification ON-808 was completed. The modification involved the replacement of the bronze control rod guide cage assembly on the fuel handling bridges with a new stainless steel design. ,

21. Revisions 0 and 1 of Station Modification ON-817 were completed. The modification revised the trips related to the turbine electro-hydraulic control to enhance operation of the unit and prevent spurious trips.

22. Revision 0 of Station Modification ON-833 was completed. The modification involved the replacement of one standard axial power shaping control rod (APSR) containing sixteen silver - indium - cadmium absorbers with an APSR j containing fif teen silver - indium - cadmium absorbers and one Inconel absorber. *

23. Revision 0 of Station Modification ON-839 was completed. The modification  ;

involves the installation of a pump, piping and valves to transfer reactor l coolant bleed evaporator bottoms and miscellaneous waste evaporator bottoms to the Interim Waste Building bottom storage tank.

24. Revision 0 of Station Modification ON-851 was completed. The fuel elevator's control circuiting was modified to require manual switch holddown for contind-  ;

dus operation.

25. Revisions 0 and 1 of Station Modification ON-852 were completed. The modifi-cation revised valve CCW-8 motor, open torque switch bypass contact to allow for an extended bypass interval as the valve disc travels of f the seat.

26. Revisions OA and OB of Station Modification ON-891 were completed. The modi-fication added a door to the temporary material areas offices in Warehouse #2.

27. Revision 0A of Station Modification ON-892 was completed. The modification involved the replacement of General Electric CD-31 coupling capacitors on g the main set-up transformers.

28. Revision 0 of Station Modification ON-897 was completed. The modification will remove the center control rod drive vent and line to vent tank and install a regular control rod drive cap. ,

t

29. Revision 0 of Station Modification ON-911 was completed. The modification supplied power to the General Electric tool trailer temporarily located east of the Turbine Building.

2. 9-4

30. Revision 0 of Station Modification ON-912 was completed. The modification relocates EDW99, emergency feedwater line "A" check valve, to provide for easier operation of the valve.

The modification

31. Revision 0 of Station Modification ON-919 was completed.

involves the replacement of valve IRC-1, pressurizer spray control valve, with an approved valve and operator. P e

        ^                                 2.9-5

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2.9.1.1.3 MAINTENANCE MONTil 0F Sept 77 UNIT 1 1 OCONEE NUCLEAR STATION PAGE 1 of 2

                                                                                                                                        !!ONTilLY DATA SilEET ZFFECT ON                                                                                           FRECAUTIONS OPERATION'S                                                                                            COMPONENT                                         MALFUNCTION                                         SAFE              CORRECTIVE ACTION                                                                    FOR AME       NUMBER                                            MANUFACTURER - HDDEL/ SIZE                                          W.R. NBR       CAUSE                      RESULT                          OPERATION                                                                                          REACTOR SAFETY RC-66                                             Dresser                                                  Relief 2 li/2"     26298       Worn Seat.                  Leakage                            None          Lapped Seat with                                                                   Refueling Diamond Compound DW-87                                            Grinnell                                                          1"         26406       Worn Dia[               .

Leakage None Replaced Diaphram "

 .RC-5                                              Rockwell                                                 Globe   1"         24473       Motor                     Inoperable                          .None          Replaced Motor                                                                          "

from Cont. Room RC-66 Dresser Relief 2 1/2" 24208 Bad'Gask. Leakage None Replaced Gasket " CC-7 Walworth Gate 8" 90862 Gasket Leakage None Replaced Gasket "

 .RC-68                                           Dresser                                                    Relief 2 1/2"      25860       Worn out                   Leakage                             None         Replaced with New V.                                                                     "

Valve RC-67 Dresser Relief 2 1/2" 25861 " " -" " " " " " " CC-76 Crane Swing Ck 3" 25041 Worn' " " Replace Gasket " Gasket CC-8 William Powell Gate 8" 90861 " " " " " " CS-173 24283 Bad Diap! " " Replaced Diaphragm " IIP-217 .Velan_ Globe 1" 24119 Bad Diapt " " Repacked " -MS-94 244,17 Worn Seat Leakage " Relapped Seat " HP-43 Lonergan Relief 2X2 " 24455 Bad Ping " " " Replaced P,lange MS-79 Crane Gate 12" 10825 Worn Seat Leakage " Dressed Wedge & Seat " OTSG Tube B&W 53688 Unknown Leakage " Tubes Plugged " PDW-108 Rockwell 53778 Packing Leakage " Repacked " PDN-106 Rockwell 52602 Packing Leakage " Repacked " LP-105 Gate 53489 Out of Not Workinc.; " Adjusted Switch "

   ,N                                                                                                                                      Adjustm.                   Properly T'     -
   ?

s .

                                                                                                               , , _ , _ , , , ,       ,,,__.m.,

M0!rril OF Sept 1977 UNIT # 1 2.9.1.1.3 MAINTENANCE OCONEE NUCLEAR STATION. PAGE 2 og 2 MONTHLY DATA SilEET EFFECT ON PRECAUTIONS HALFUNCTION SAFE CORRECTIVE ACTION FOR OPERATION'S COMPONENT RESULT OPERATION REACTOR SAFETY AM NUMBER MANUFACTURER - HDDEL/ SIZE W.R. NBR CAUSE Leakage None Repacked Refueling LPI-13 Crane Gate 10" 24123 Packing CC-7 Walworth Gate '8" 25685 Switch Will no't None Adjusted Torque Swit h Refueling

                                                                                            '                                      Open Elect                         and cleaned contacts Globe           1/2*    25956              Packing      Leakage                   "        Repacked & Replaced HP-126         Velan                                 '

Gaskets j , - ; l " " " " HP-127* Velan ' Globe 2 l'/2* 24954 Packing Leakage i ,  ! ', " " HP-246 Velan Globe 1 24955

                                         ~                                                                                              "                     "

HP-126 Velan Globe 2 1/2 25922 Worn Seat ,

                                                               .                    l                                            "      "                   '"                "                      "                                       "

i " HP-127 Velan Globe 25923 ." 1 l , 25924 Diaphragm Inoperable Replaced diaphragm CS-70 grinnell 1" ' I " Adjusted Guide Ring 24416 Not Operat Lng Lon*ergan Relief ! Incorrect MS-140 " Setting Settings Correctly l

                                                                                     'l of Guide Rings Letdown        Fluid Dynamics                 ,         ,   26228          Loose            Leakage                   "

Tightened Bolts ," Filter - Bolts A

                                                         .                           l                     [              .

24968 B/B Leak- Leakage Replaced B/B. Gasket SF-61 Crane Gate  ! 8 "i

                                                                                                                                                                         & Repached l

I age Gasket SD-2 25182 Worn Gasket Leakage " Replaced Packing & Gasket t . Tendon l 90859 Worn Leakage Replaced Washers Caps j i Washers Letdown 10819 IIole in Leakage- Replaced Cooler Cooler Tubes , "A" ,N i Bad Pkg Replaced Packing " RC-3 y Rockwell Globe.2 1/2" 24958 Packing Leak

4.3M.m 04M baHbaEMJiMeal 45 ave.swaamies.ssm.m.. ........-2 > - ~ ' - - - - - - -- -- - - - - - - - - - - e s. 2.9.1.1.3 MAINTENANCE MONTil 0F Sept. 1977 UNIT # 1 OCONEE NUCLEAR STATION Additional Items to September's Report MONTitLY DATA SIIEET EFFECT ON FRECAUTIONS OPERATION'S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR IAME NUMBER MANUFACTURER - MODEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFETY R.B. Spra: r Out of II. .perable None iteplaced the Pump Unit Down Pump 53591 alignment I i l l l 4 g I i i l I I , 1 f

                                        +                                                                                                          .

g 6 h l r I l  !

     ~                                                                                                                                                        ,

v. O

DOCKET NO. 50-269 2.9.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UtilT NAME ocnnen Unit 1 REPORT MONTH September, 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE Refueling continued. 408.00 C 9/1/77 9/18/77 Outage continued for steam Maintenance conducted. generator maintenance. 312 B

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values. -

."                                                                                                                        E-0PERATOR TRAINING AND LICENSE EXAMINATION
?                                                                                         A-EQUIPMENT FAILURE (EXPLAIN)

• B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) ,

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

I 2.9.1.2 Unit 2 I 2.9.1.2.1 Operating Experience The unit was at 75 percent full power at the beginning of September. Power escalation testing was in prn;ress. On September 3, 1977, power was increased to 96 percent full power and a main steam stop valve (MSSU) test was conduc-ted. On September 4,1977, power was decreased to 75 percent full power for transient testing on the "2B" steam generator. On the same day, power was reduced to approximately 15 percent full power to implement an EHC modifica-tion to decrease the closure time on the MSSV's. Normal power escalation began later that day and the unit reached 96 percent on September 6,1977. . On September 9,1977,, the reactor was shutdown due to indications of a reactor coolant system leak. On September 17, 1977, the leak was determined to originate from SOAK instrument line penetrations of the "2B" steam generator. Also, a stator was replaced on control rod 1, group 2 during the outage. On September 20, 1977, heatup was commenced. During reactor startup it was determined that the "AA" phase of a control rod in group 5 was burned out. The stator was replaced and heatup was commenced on September 22, 1977. On September 23, 1977, while at hot shutdown, a leak developed in the EHC system on the line to the MSSV's. The leak was repaired and startup commenced the same day. At approximately 27 percent full power control rod 3 group 6 dropped into the core due to a stator failure. The reactor was shutdown to r2 place the stator. On September 24, 1977, normal power escalation resumed and 96 percent full power was reached on September 26, 1977. On September 27, 1977, power was reduced to approximately 63 percent due to a suspec* d OTSG tube leak. The leak was too small to determine the location and powe; was increased to 68 percent by September 28, 1977 and remained at this level for the rest of the month. 2.9.1.2.2 Changes, Test and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during September, 1977.

1. Revision 2 of Station Modification ON-559 was completed. The modification will ef fectively disable the bypass dampers on the Reactor Building purge filters and seal the exit of the bypass oil cooler.

2. Revision 0 of Station Modification ON-594 was completed. The modification involved the inspection of all General Electric type HFA and HGA relays at Oconee Nuclear Station including those at Keowee Hydro Station and replace-ment of defective relay coils,

3. Revision 0 of Station Modification ON-635 was completed. The modification involved the installation of a feedback mechanism which will assure that the setpoint for the flowrate of liquid waste discharged from the station is not exceeded.

2. 9-7

4 l 1 I 4 Revisions OB, 2 and 4 of Station Modification ON-698 were completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomics radiation monitoring system.

5. Revision 0 of Station Modification ON-706 was completed. The modification involved the installation of an acrylic collimator on the face of the scin-tillation crystals of RIA-47 and RIA-49, the Reactor Building airborne activity monitors.

6. Revision 0 of Station Modification ON-735 was completed. The modification involved the addition of fuses to protect the 0.5 KVA transformer which supplies power to the cooling fans for the pressurizer heater control cir- .

cuits.

7. Revision 0 of Station Modification ON-740 was completed. The modification involved the installation of a locking device on the Keowee governor sole-noid cap screw to prevent cap screw nut from backing off. The modification was initiated at the manufacturer's recommendation.

8. Revision 0 of Station Modification ON-839 was completed. The modification involves the installation of a pump, piping and valves to transfer reactor l coolant bleed evaporator bottoms and miscellaneous waste evaporator bottoms to the Interim Waste Building bottom storage tank.

9. Revision 0 of Station Modification ON-851 was completed. The fuel elevator's control circuiting was modified to require continuous manual switch holddown for operation.

10. Revision 2 of Station Modification ON-875 was completed. The modification involved the addition of orificies in the main turbine stop valves to

' decrease closure time.

11. Revision 0A of Station Modification ON-891 was completed. The modification added a door to the temporary materials area offices in Warehouse #2.

12. Revision 0A of Station Modification ON-892 was completed. The modification involved the replacement of General Electric CD-31 coupling capacitors on the main step-up transformers.

l l

2. 9-8

2.9.1.2.3 IMINTENANCE MONTil 0F Sept. 1977 untyp 2 OCONdE NUCLEAR STATION 1 PAGE of I HONTiiLY D_'.YA S!1EET ZFFECT ON PRECAUTIONS OPERATION'S, CO'!PONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR NIE F,id .u c a stANUFAC'IURER - MOuEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFE FDW-101 Crane Check 6" 25667 B/B Gasket Leakage None Replace B/B. Gasket Unit Down CA -10 Grinnell 3" 25451 Worn

                                                                    *Diaphras m Leakage                                                           "    "

None Replaced Diaphragm CS-66' Grinnell 3" 25664 Bad Diaphragm Inoperabl( None Replaced Diaphragm " " CRD Stator B&W 25970 Bad Stator Inoperabl( None Replaced Stator' " " CS-67 Grinnell 3" 25670 B/B Gasket Leakage None Replaced Bonnet Assy. " " OTSG 2B B&W 25674 Worn Gaskc t Leakage None Replaced Gasket " " Primary Handhole . FDW-104 Crane Gate 4" 25302 Loose Pkg Leakage None Adjusted Packing " " SD-152 25705 Bad Packir g Leakage None Repacked Valv.s " " SD-146 " " " " Velan Gate 1" 25185 " " " " 4=- 25986 " R.B. Pers. W. J. Wooley " Slipped Adjusted Linkage " " Hatch Shaft Mech Seal 24571 Orfice " " Replaced Orfice Line on 2B HPI Pmp ' SD-13 Viv 25703 Packing " " Repacked Hyd Supp. Grinnell 53614 Loose " " Replaced eyebolt " " Eyebolt flyd Supp Grinnell 53543 Rod out " " Adjusted Rod " " of Adjust-w ment i 2*

Page 1 of 2 DOCKET NO. 50-270 UNIT HAME Oconee Unit 2 2.9.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT MONTH September. 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hcurs) RADIOACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RAD 1ATION DURATION REPORTABLE ACT10NS COMPONENT EXPOSURE

                                                     /   AFFECTED                        (HOURS) REASON   OCCURRENCL NO.

DATE Unit taken of f - line to modify Modification to slow closure 9/04/77 of MSSV completed. the turbine main' stream stop valve 6.00 B (MSSV) Leak around OTSG "2E" vibra-9/11/77 Unit shutdown f rom approximately tion testing instrumentation 94 percent full power to investi- A R0 270/77-11 seal repaired. gate indications of a primary leak. 196.24 Stator replaced 9/19/77 Outage extended to replace failed stator on control rod 1 group 2. 47.60 A 9 A-EQUIPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING Ain LICENSE EXAMINATION , y ' B-MAINTENANCE OR TESTING F-ADMINISTRATIVE e C-REFUELING G-0PERATIONAL ERROR (EXPLAIN) D-REGULATORY RE'TRICTION H-0THER (EXPLAltl)

Page 2 of 2 t DOCKET NO. sn_97n 2.9.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH September, 1977 SYSTEM RADIOACTIVITY CAUSE OR

                                                                                 ,                       CORRECTIVE                RELEASE OR COMPONENT                  DURATION           REPORTABLE                ACTIONS                   RADIATION DATE                     AFFECTED                              REASON (HOURS)           OCCURRENCE NO.                                       EXPOSURE 9/21/77     Gutage extended to replace failed        33.92        A                      Replaced stator.

stator on control rod 6 group 5. 9/23/77 Outage extended to repair leaking 7.88 A Repaired leaking pipe fitting pipe fitting on EHC system. on EllC system. 9/23/77 Unit shutdown from 27 percent full 31.86 A Replaced stator, power to replace failed stator on control rod 3 group 6. 9/27/77 Power reduced from approximately A RO 270/77-12 Investigation in pregress. 96 percent to 63 percent fuel power to investigate suspected OTSG 1eak.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values.

[ o

                                                       .A-EQUIPMENT FAILURE (EXPLAIN)    E-0PERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING         F-ADMINISTRATIVE C-REFUELING                      G-OPERATIONAL ERROR (EXPLAIN) 3-REGULATORY RESTRICTION         H-0THER (EXPLAIN) 4

__,m a. ...

f 2.9.1.3 Unit 3 2.9.1.3.1 Operating Experience At Oconee Unit 3 operated at 100 percent full power until September 2, 1977. i this time, the 24 time limit allowed by technical specifications for return of an inoperable Reactor Building Spray Pump (RBSP) ended. Unit shutdown was commenced as required by the specification. The pump which had a turned out motor was repaired and returned to service on September 3,1977 and unit startup was commenced. The unit reached 97 percent fell power by On September 5,1977 and approximately 100 percent by September 7,1977. September 8,1977, power was reduced to 26 percent full power to correct a stator coolant problem. The unit returned to approximately 100 percent full . power on September 8,1977 and remained at this level for the rest of the month.

2. 9.1. 3. 2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuar.t to 10CFR50.59 during September,1977.

1. Revision 1 of Station Modification ON-453 was completed. The modification involved the installation of check valves in the reheat stop intercept valve steam leakoff lines from the high pressure turbine to the low pres-sure turbine to prevent air leakage to condenser steam leakoff line.

2. Revision 0 of Station Modification ON-594 was completed. The modification involved the inspection of all General Electric type HEA and HGA relays at Oconee Nuclear Station including those at Keowee Hydro Station and replace-ment of defective relay coils.

3. Revision 0 of Station Modification ON-635 was completed. The modification involved the installation of a feedback mechanism which will assure that the setpoint for the flowrate of liquid waste discharged from the station is not exceeded.

4. Revisions OB, 2 and 4 of Station Modification ON-698 were completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomic radiation monitoring system.

5. Revision 0 of Station Modification ON-735 was completed. The modification involved the addition of fuses to protect the 0.5 KVA transformer which l

supplies power to the cooling fans for the pressurizer heater control cir-cuits.

6. Revision 0 of Station Modification ON-740 was completed. The modification involved the installation of locking device on the Keowee governor solenoid cap screw to prevent the cap screw nut from backing off. The modification l

was done at the manufacturer's recommendation. 2.9-11

7. Revision 0 of Station Modification ON-785 was completed. The modification replaced the existing center s'ections of the spent fuel pool personnel safety barrier with two removable chains.

8. Revision 0 of Station Modification ON-839 was completed. The modification involves the installation of a pump, piping and valves to transfer reactor coolant bleed evaporator bottoms and miccellaneous waste evaporator bottoms to the Interim Waste Building bottom storage tank.

9. Revision 0 of Station Modification ON-851 was completed. The fuel elevator's control circuiting was modified.

10. Revision OA of Station Modification ON-891 was completed. The modification added a door to the temporary materials area offices in Warehouse #2.

4 1 J 2.9-12

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DOCKET NO. 50-287 2.9.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH September, 1977 SYSTEM RADI0 ACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 11/2/77* Unit shutdown from 100 p'ercent 7.29 A R0 287/77-11 The RB Spray Pump was repaired full power per Oconee Technical and returned to service. Specification 3.3 due to Reactor Building spray pump out of service more than 24 hours. 11/8/77 Unit power reduced to 26 percent A Problem corrected. due to stator coolant problem.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which acccunted for more than 10 percent of the allow-able annual values.

N y A-EQUIPMENT FAILURE (EXPLAIN) E-0PERATOR TRAINING AND LICENSE EXAMlHATION

 -.                                          B-MAINTENANCE OR TESTING         F-ADMINISTRATIVE C-REFUELING                      G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.10 REPORT FOR OCTOBER, 1977 l 1 l l i l l 1 2.10-1

                                     .i

2.10.1 OPERATIONS

SUMMARY

2.10.1.1 Unit 1 2.10.1.1.1 Operating Experience Preparations for startup from an outage for steam generator maintenance were in progress at the beginning of October,1977. On October 4, 1977, startup was terminated to correct excessive Reactor Coolant Pump (RCP) seal leakage on the "1B1" RCP. Repairs were completed on October 10, 1977 and unit start-up resumed. Zero Power Physics Testing was conducted on October 14, 1977 and - approximately 16 percent full power was reached by October 18, 1977. At this level, the unit tripped due to the loss of the "1A" feedwater pump. The pump was returned to service and the unit was brought back on line the same day. , Power was escalated to 40 percent full power by October 19, 1977 for testing Problems with quadrant tilt caused a power reduction to 30 percent full power on October 21, 1977 for further testing. On October 25, 1977, power was again escalated to 40 percent tuli power and on October 30, 1977, powe; reached approximately 75 percent full power and remained at this level for the rest of the month. Tests to determine the cause of the tilt problem were still in progress. 2.10.1.1.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during October,1977.

1. Revision 0 of Station Modification ON-513 was completed. The modification replaced various seismic monitoring equipment with more modern equipment.

2. Revision 0 of Station Modification ON-543 was completed. The modification upgraded access platforms in the Reactor Building to meet present seismic  !

design criteria.

3. Revisions 2 and 4 of Station Modification ON-650 were completed. ' Die modi- I fication will move the power service of Reactor Building cooling unit (RBCU) l "A" from XSL MCC to X8 Load Center and RBCU "C" from XS2 MCC to X9 Load i

Center.

4. Revision 0 of Station Modification ON-662 was completed. The codification involved zhe replacement of Keowee emergency start pushbuttons with switches similar to those used for electric valves.

5. Revision 5 of Station Modification ON-698 was completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomics radia-tion monitoring system.

6. Revision 0 of Station Modification ON-746 was completed. The modification involved the installation of a 6 foot fer.:e around the area where the full -

waste solidification casks are stored. 2.10-2 __

7. Levision 0 and 1 of Station Modification Oh-768 was completed. The moditication provides for an increase in capacity and temperature ratirg of the control rod drive structure cooling .?ans.

8. Revision 0 of Station Modification ON-822 was completed. The modifica-tion involved the removal of the controlled access function from the main, northwest and south gates and disabled the east personnel gate by movement of the restricted area fence.

9. Revision 0 of Station Modification ON-849 was completed. The modifica-tion provided a regulated power supply to the Health Physics counting room. .

Revision OA of Station Modification ON-858 was completed. The modification 10. provided electrical, water, public address and telephone services to the interim security trailer and canteen trailer. Revision 0 of Station Modification ON-875 was completed. The modification 11. involved the addition of orifices to the main turbine stop valves to increase closure time. The modification

12. Revi;sion 0 of Station Modification ON-893 was completed.

involved the movement of the hydrogen gas analyzer moisture separator, filter and float trap upstream of the gas pump.

13. Revision 0 cf Station Modification ON-894 was completed. The modification involved changer to the reactor coolant pump seal housing to accommodate a replaceable seal insert.

14. Revision 0 of Station Modification ON-933 was completed. The modification involved the replacement of valve RC-5, the pressurizer steam space sample valve with an approved valve and operator.

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2.10.1.1.3 MAINTENANCE . MONTH OF October 1977 UNIT # 1 OCONEE NUCLEAR STATION . PAGE of MONTHLY DATA SHEET EFFECT ON PRECAUTIONS OPERATION'S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR AME NUMBER MANUFACTURER - HDDEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFETY No safety related work performed , 1 . 9 e , e e *

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                                                                                                                    -       _.           ^

DOCKET NO. 50-269 UNIT NAME Oconee Unit I 2.10.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT MONTH October. 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RADICACTIVITY SYSTEM COP.PICT IVE RELEASE OR CAUSE OR ACTIONS RADIATION DURATION REPORTABLE COMPONENT EXPOSURE (HOURS) REASON OCCURRENCE NO. DATE AFFECTED Maintenance completed. Outage for steam generator main- 87.40 B 10/01/77 tenance continued. Reactor coolant pump seal Outage continued to correct reac' tor 236.60 B leakage corrected. 10/04/77 coolant pump seal leakage. 85.05 B N/A 10/14/77 Zero Power Physics testing. Problem was corrected and pump Unit tripped from approximately 8.91 A 10/18/77 placed back in service, 16 percent full power due to loss

• of "A" feedwater pump.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values.

I A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION w F-ADMINISTRATIVE B-MAINTENANCE OR TESTING

 'r.                                                                              G-OPERATIONAL ERROR (EXPLAlH)
 '9                                              C-REFUEllHG D-REGULATORY RESTRICTION         H-0THER (EXPLAIN)

2.10.1.2 Unit 2 2.10.1.2.1 Operating Experience Oconee Unit 2 was held at approximately 68 percent full power at the beginning of the month to investigate a small OTSG tube leak. Due to its size, the loca-tion of the leak could not be determined. On October 6,1977, power was increas-ed to 80 percent full power. On October 7, 1977, the reactor was shutdown. The leak was determined to be in "2B" 0TSG, but leak tests and other efforts failed to pinpoint the location. On October 28, 1977, power was increased to 30 percent full power and held due to - quadrant tilt problems. Power was then increased to 50 percent and on October 29, 1977 to 70 percent, to determine if the leakage was increasing. Power was held at 70 percent full power the remainder of the month. 2.10.1.2.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during October, 1977.

1. Revisions IA, 2, 3 and 5 of Station Modification ON-246 were completed. The modification involved the replacement of low pressure injection valves 2LP-12 and 2LP-14 with Fisher Vee-Ball valves.

2. Revisions 0 and 1 of Station Modification ON-605 were completed. The "D" heater emergency bypass piping to the condenser was modified to allow the "D" flash tank to properly dump to the condenser.

3. Revision 4 of Station Modification ON-650 was completed. The modification involves the movement of the power source of Reactor Building cooling units "A" and "C" from XS1 and XS2 motor control centers to X8 and X9 load centers respectively.

4. Revision 0 of Station Modification ON-659 was completed. The modification involved the installation of ground level pressure gauges to indicate SF gas pressure inside electrical penetrations EMV-1 and -Z. This modifica6 tion will assure personnel safety when reading the gauges.

5. Revision 0 of Station Modification ON-662 was completed. The modification I involved the replacement of Keowee emergency start pushbuttons with switches similar to those used for electric valves.

6. Revision 5 of Station Modification ON-698 was completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomics radia-tion monitoring system.

7. Revision 0 of Station Modification ON-746 was completed. The modification involved the installation of a 6 foot fence around the area where the full waste solidification casks are stored.

2.10-5

8. Revision OA of Station Modification ON-752 was completed. The modification involved the replacement of valve 2FDW-296, 2FDW-298 and 2FDW-302 with Keotest valves.

9. Revision 0 and 1 of Station Modification ON-783 was completed. The modifi-cation blanks the auxiliary feedwater nozzles that empty into the OTSG open tube lanes to help eliminate vibration in the lane.

10. Revision 0 of Station Modification ON-822 was completed. The modification involved the removal of the controlled access function from the main, north-east and south gates and disabled the east personnel gate by movement of the restricted area fence. .

The modification

11. Revision 3 of Station Modification ON-845 was completed.

involved the removal of the auxiliary feedwater camera probe and the blind flanges on the auxiliary feedwater header and replaced the original auxiliary feedwater nozzle and riser.

12. Revision 0 of Station Modification ON-849 was completed. The modification provided a regulated power supply to the Health Physics counting room.

13. Revision OA of Station Modification ON-858 was completed. The modification provided electrical, water, public address and telephone services to the interim security trailer and canteen trailer.

14. Revision 0 of Station Modification ON-864 was completed. The modification involves the deletion of signal limiters on the feedwater temperature input to the BTU limit circuit.

6 { l l - I l l 2.10-6

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i 2.10.1.2.3 MAINTENANCE H0!mi 0F October 1977 trNITf 2 OCONEE C' CLEAR STATION PACE of M0!mlLY DATA SilEET EFFECT ON PRECAUTIONS OPERATION'S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR AME NUMBER MANUFACTURER - HDDEL/ SIZE W.R. NBR CAUSE RESULT OPERATION REACTOR SAFETY No safety related work pc rformed i

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• DOCKET NO. 50-270 UNIT NAME Oconee Unit 2 2.10.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH October. 1977 1 RADIDACTIVITY SYSTEM CORRECTIVE RELEASE OR CAUSE OR ACTIONS RADIATION DURATION REPORTABLE COMPONENT EXPOSU,RE (HOURS) REASON OCCURRENCE NO.

DATE AFFECTED A RO 270/77-12 Investigation continued. 10/01/77 Power held at 68 percent full power to investigate tube leak in "2B" OTSG 497.00 A R0 270/77-12 Investigation did not reveal 10/07/77 Unit shutdown to investigate location of leak. indicated tube leak in "2B" OTSG A RO 270/77-12 Investigation continued. 10/28/77 Power held in steps of 30 percent. 50 percent and 70 percent full power to determine if leak was increasing.

SUMMARY

There was no single release of radioactivity or unusual radiation '

exposure specifically associated ' with any outage which accounted for more than 100 percent of the allow-able annual values. A-EQUIPhENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION

 "                                             B-MAINTENANCE OR TESTING        F-ADMIN I ST RAT IVE C-REFUELING                     G-OPERATIONAL ERROR (EXPLAIN)

{ u D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.10.1.3 Unit 3 2.10.1.3.1 Operating Experience Oconee Unit 3 was at 98 percent full power at the beginning of October, 1977. On October 13, 1977, the unit tripped due to the loss of DC power to the tur-bine controls. The unit was placed back on line the same day and reached 85 percent full power by October 14, 1977. Power was decreased.to 70 percent on October 20, 1977 due to a low oil level in the upper oil pot of the "3B1" reactor coolant pump. On October 21, 1977, the unit was shutdown for refueling. 2.10.1.3.2 Changes, Tests and Experiments not requiring prior NRC approval. , The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during October, 1977.

1. Revision 0 of Starfan Modification ON-538 was completed. The modification involved wiring changes to the annunciator panels in the control room.

2. Revision 0 of Station Modification ON-662 was completed. The modification involved the replacement of Keowee emergency start pushbuttons with switches similar to those used for electric valves.

3. Revision 5 of Station Modification ON-698 was completed. The modification involved the replacement of RIA-33 and RIA-34 with a General Atomics radia-tion monitoring system.

4. Revision OA of Station Modification ON-719 was completed. The modification changed electrolytic capacitors acroas the "A" relay of all trace heat alarm panels from 250 microforad to 1000 microforad and revised individual heat trace field wiring.

5. Revision 0 of Station Hodification ON-746 was completed. The modification involved the installation of a 6 foot fence around the area where the full waste solidification casks are stored.

6. Revision 0 of Station Modification ON-759 was completed. The modification involves the addition of a fifty millisecond time delay in the fast acting intercept valve circuits of the turbine control system to prevent noise spikes.

7. Revisions 1 and 2 of Station Modification ON-762 were completed. The modi-fication involved the application of Furmanite to stop leaks in 3FDW-46, the OTSG "B" normal header check valve, until permanent repair can be made.

8. Revision 0 of Station Modification ON-808 was completed. The modification involved replacement of the bronze control rod guide cage assembly on the fuel handling bridge with a new stainless steel design.

l 1 I 2.10-8 l

9. Revision o of Station Modification ON-822 was completed. The modification involved the removal of the controlled access function from the main, northeast and south gates and disabled the east personnel gate by movement of the restricted area fence.

10. Revision 0 of Station Mootfication ON-846 was completed. The modification involves the replacement of the Mag-bronze fuel grapple actuator cam with a stainless steel cam.

11. Revision 0 of Station Modification ON-849 was completed. The modification provided a regulated power supply to the Health Physics counting room.

                                                                                         ~

12. Revision OA of Station Modification ON-858 was completed. The modification provided electrical, water, public address and telephone services to the interim security trailer and canteen trailer.

13. Revision 0 and 1 of Station Modification ON-893 were completed. The modifi-cation involved the movement of the hydrogen gas analyzer moisture separator, filter and float , trap upstream of the gas pump.

O 2.10-9

6 N W IS N M N 86 % u emd464& 4 4 d..... - . . , . . ... . - . = ma u . w w --

                                                                                                                                                               --.m   pump tripped on overspeed causing the generator to come.off line.

was made critical again on the same day and power was increased to 25 percent full power by November 14, 1977. Power was increased and held in steps to allow monitoring of the leak until November 29, 1977 when the unit began decreasing power to 27 percent in order to replace a gasket on the stator cooling system. Repairs were made and the unit reached 70 percent full power by the end of the month. 2.11.1.2.2 Changes, Tests and Experiments not requiring prior NRC approval. The follwing changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during November,1977.

1. Revision 0 of Station Modification ON-SPR-190 was completed. The modification connected the RIA process and area monitors to control room alarms such that alarms can be received, acknowledged and reset for another alarm.

2. Revision 1 of Station Modification ON-530 was completed. The modification j

involved the installation of jib cranes to facilitate reactor coolant pump motor maintenance. ! 3. Revision 0 of Station Modification ON-881 was completed. The modification provided electrical service, high pressure service water and service air to the Chem-Nuclear Mini-Mobile Waste Solidification unit.

4. -Revision 1 of Station Modification ON-938 was completed. The modification involved the removal of a wall between a file room and the canteen storage area in the Administration Building.

2.11 -

MAJOR SAFETY RELATED " MAINTEllANCE M0ffrH OF llovember. 1977 UNIT # 2 2.11.1.2.3 OCONEE NUCLEAR STATION MONTilLY DATA SilEET PACE 1 of 1 ZFFECT ON PRECAtTTIONS OPERATION'S COMPONENT MALFUNCTION SAFE CORRECTIVE ACTION FOR NA!!E NUEEElt HANUFACTURER - MODEL/ SIZE W.2. NBR CAUSE i RESULT OPERATION REALTOR SAFETY _ No safety related work performed. e i if . G

DOCKET NO. srL 9 7n UNIT NAME Oconee Unit 2 2.11.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT MONTH November, 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) . RADICACTIVITY SY5 TEM CORRECTIVE RELEASE OR CAUSE OR ACTIONS RADIATION DURATION REPORTABLE COMPONENT EXPOSURE (HOURS) REASON OCCURRENCE NO. DATE AFFECTED A RO 270/77-12 Investigation continued. 11/1/77 Power held at 70 percent full power to investigate possible OTSC tube Icak. 201.84 A RO 270/77-12 Location of leak could not be 11/3/77 Unit was shutdown to repair OTSG determined. A leak on the tube leak. powdex system was repaired. 7.97 B Pump was returned to operable 11/13/77 Unit tripped from 25 percent full status, power during test on emergency feedwater pump. A Gasket replaced. 11/29/77 Power decreased to 27 percent to replace a gasket on the stator cooling system.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able values.

A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION O B-MAINTENANCE OR TESTING F-ADMINISTRATIVE

       &                                                                                                                                                    C-REFUELING                     G-OPERATIONAL ERROR (EXPLAIN)

D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.11.1.3 Unit 3 2.11.1.3.1 Operating Experience Oconee Unit 3 was shutdown for refueling the entire month of November, 1977. Startup procedures were in progress at the end of the month. 2.11.1.3.2 Changes, Tests and Experiments not requiring prior NRC approval. The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during November, 1977. .

1. Revision 0 of Station Modification O'N-SPR-190 was completed. The modification connected the RIA process and area monitors to control room alarms such that alarms can be received, acknowledged and reset for another alarm.

2. Revision 0 of Station Modification ON-646 was completed. The modification provides a signal from the Electro-Hydraulic Control System to close the moisture separator reheater drain valves to the condenser during the turbine shell warming mode of operation.

3. Revision OA of Station Modification ON-705 was completed. The modification involves the installation of instrumentation to provide positive indication that flow exists in at least one boron dilution drain line.

4. Revision OC of Station Modification ON-750 was completed. The modification involves the replacement of valve 3HP-223, the "3B1" RCP and supply vent valve, with a Kerotest valve.

5. Revision OA of Station Modification ON-753 was completed. The modification involved the replacement of steam drain system valves 3SD-8, 3SD-115, 3SD-161, 3SD-163, 3SD-168, 3SD-215, 3SD-283, 3SD-373 and 3SD-410 with Kerotest valves.

6. Revision 0 of Station Modification ON-767 was completed. The modification involved the replacement of existing control rod gate drives with improved gate drives ao proposed by Diamond Power Company.

7. Revision 0 of Station Modification ON-792 was completed. The modification involved the installation of valve N-137, core flood tank nitrogen supply valve, such that valve is more accessible.

8. Revision 1 of Station Modification ON-830 was. completed. The modification involved the restoration of the 3B2 moisture separator reheater to its original configuration after testing by General Electric.

9. Revision 0 of Station Modification ON-854 was completed. The modification involved the removal of the existing hydraulic tank drain plug on the fuel handling equipment and replacement of the plug by a ball valve and quick disconnects.

Y 2.11-6

10. Revision 0 of Station Modification ON-881 was completed. The modification provided elsctrical service, high pressure service water and service air to the Chem-Nuclear Mini-Mobile Waste Solidification Unit.

11. Revision 1 of Station Modification ON-938 was completed. The modification involved the removal of a wall between a file room and the canteen storage area in the Administration Buildings

12. Revision 0 of Station Modification ON-944 was completed. The modification increases the moisture separator reheater first and second stage non-conden-sing vent line orifice size to prevent moisture separator reheater tube .

bundle steam erosion.

13. Revision 0 of Station Modification ON-945 was completed. The modification converts the tube bundles in the moisture separator reheaters to a floating U-bend design to prevent moisture separator reheater tube support plate buckling.

14. Revision 0 of Station !!odification ON-954' was completed. The modification involves the installation of acoustic leak detection herdware in the mois-ture separator reheaters.

I 1 i s

                                           -2.11-7

MAJOR SAFETY RELATED MAINTEllANCE MONTII 0F November, 1977 UNITI 3 2.11.1.3.3 OCONEE NIICLEAR STATION

                                                                                                                                        ^     '          '

HONTilLY DATA SHEET ZFFECT ON PRECAttrIONS OPERATION'S COMPONENT _ MALFUNCTION SAFE CORRECTIVE ACTION FOR NA*E NijEEElt flANIIFACTURER - 110 DEL /SI2.E _ W.R. NBR CAUSE RESIILT OPERATION REACTOR SAFET1 Pcnetration Viking Industries Type J 90836 Worn gasket None New penetration installe L. None  : WA-1 required. 27EYClX Cutler llammer - D/26MRD 91072 Magnetic None New relay installed. None carrier required. . failure RPS power Westinghouse WL236 36-B 54192 Signal None Cable replaced. Redun-range cable ant indica-detection failure tion avail-able. t l l I I I i M I e b i .

DOCKET NO. 50-287 UNIT NAME Oconee Unit 3 2.11.1.3.4 OUTAGES OR FORCED REDUCTION 5 IN POWER REPORT HONTH November, 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RAD 10ACTIVl1 SYSTEM RELEASE OR-CORRECTIVE CAUSE OR RADIATION REPORTABLE ACTIONS COMPONENT DURATION EXPOSURE AFFECTED (HOURS) REASON OCCURRENCE NO. DATE 720.00 C N/A 11/1/77 Refueling outage.

SUMMARY

There wac no single release of tadioactivity or unusual radiation exposure specificall. associated with any outage which accounted for more than 10 percent of the allow-able values.

s-o O E-OPERATOR TRAINING AND LICENSE EXAMlHATION o3 A-EQUIPMENT FAILURE (EXPLAIN) B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN) s 6 J

I 2.12 REPORT FOR DECEMBER, 1977 l l

                                                                               /

2.12-1 y , , ,.--.-- y

1 2.12.1 OPERATIONS

SUMMARY

2.12.1.1 Unit 1 2.12.1.1.1 Operating Experience Oconee 1 began the month of December at 100 percent full power. On December 9, 1977, a ground developed on the generator. The generator was taken off line and the ground problem was found in the diode cabinet. Dust was blown from the cabinet and the problem cleared. The reactor remained at approximately 13 perc9nt power during this time. The generator was returned to service on December 12, 1977. - The unit returned to approximately 100 percent full power on the 12th of the month and ran smoothly until December 16, 1977. While decreasing Tave for a test, the reactor ran back to 82 percent full power due to feedwater limits. The reactor was returned to the power level cut off. The test was canceled. Equilibrium xenon was established and reactor power was increased to 100 per-cent on December 16, 1977. Reactor shutdown was commenced on December 20, 1977 due to a Reactor Coolant System leak. Entry was made into the Reactor Building to look for primary leaks. The leak was determined to be on the pressurizer, but due to heat and poor visibility the exact location could not be determined. Shutdown was commenced. On December 21, 1977, a cooldown was complete and visual inspection revealed that the leak was from RC-2 and RC-17. The two valves were repacked and heatup commenced on December 22, 1977. Heatup continued and on December 24th, the reactor was critical. The generator was placed on line the same day. The unit reached 100 percent full power on December 28, 1977. Another reactor coolant leak developed on December 29, 1977. The reactor was reduced to 40 percent power and the leak was determined to be at the "A" narrow range pressure transmitter. The leak was isolated and reactor power was increased. The unit reached 100 percent full power on December 29, 1977. On December 30, 1977, OTSG "A" main block valve was closed instead of the Unit 2 valve, which resulted in an ICS runback due to feedback limit. The reactor tripped on high pressure. The unit was returned to service the same day and 100 percent full power was reached on December 31, 1977. 2.12.1.1.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during December,1977.

1. Revision 0 of Station Modification ON-721 was completed. The modification established an interlock between the RB purge exhaust throttle mini purge fan with a alert alarm en RIA-45.

2.12-2

2. Revision 0 of Station Modification ON-784 was completed. The modification involved the installation of a support member to the hotwell pump suction piping to prevent the suction header from moving laterally.

3. Revision 0 of Station Modification ON-892 was completed. The modification involved the replacement of General Electric type CD-31 coupling capacitors on Keowee, the red and yellow buses and transformers CT-1 and CT-2.

4. Revision 0 of Station Modification ON-968 was completed. The modification involved the installation of an additional alarm reflash unit for the fire detection system. .

0 2.12-3

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DOCKET NO. 50-269 OUTAGES OR FORCED REDUCTIONS IN POWER UtilT NAME Oconee Unit 1 2.12.1.1.4 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT MONTH December. 1977 RADIDACTIVITY SYSTEM RELEASE OR CORRECTIVE CAUSE OR RADIATION DURATION REPORTABLE ACTIONS COMPONENT EXPOSURE AFFECTED (HOURS) REASON OCCUR.ENCE NO. DATE N/A Dust cleared from cabinet, The generator was taken off line 13.13 A 12/0P/77 due to a ground problem in a diode cabinet. Ground postulated to have resulted from dust in the cabinet. A R0 269/77-30 The valves were repacked. The unit was shutdocu due to leaks 92.40 12/20/77 pass the packing on RC-2, spray control bypass valve and RC-17, surge line drain valve. A Transmitter was repaired, 12/28/77 Power reduced to 40 percent full - power. Leak on the "A" narrow range pressure transmitter was isolated. A-EOUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE P G-OPERATIONAL ERROR (EXPLAIN) { e-C-REFUELING D-REGULATORY RESTRICTION H-0THER (EXPLAIN) t

DOCKET NO. 50-269 2.12.1.1.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit I (Over 20 Percent of Des'gn Power level and Longer Than Four Hours) REPORT MONTH December. 1977 SYSTEM RADI0 ACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSUhE 12/30/77 FDW'31, OTSG "A" main bidck valve 5.43 G Condition cirrected, was closed instead of 2FDW' 31 resulting in a reactor trip.

SUMMARY

There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values. .

w L A-EQUIPMENT FAllllRE (EXPLAIN) E-OPERATOR TRAINlftG AND LICENSE EXAMINATION Y B-MAINTENANCE OF. TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

1 2.12.1.2 Unit 2 2.12.1.2.1 Operating Experience Due Oconec Unit 2 was operating at 78 percent full power on December 1, 1977. to maneuvering limitations, ti; m:in steam lines, RIA-40 and Turbine Building sump were being monitored in order to detect any increase in radiation that A shut-could be coming through the suspected tube leak ia the "2B" OTSG. doPn was initiated the same day to repair the leak. On December 2,1977, "the primary leak was determined to beWork a packing leak on was completed

                                                                                       ~

2RC-16, the water space sample valve on the pressurizer. on 2RC-16 the same day. At this time, Chemistry samples showed activity in .0TSG; therefore, heatup was delayed until further samplin3 showed that the activity was within pro-scribed limits. On December 3,1977 a 2CC-8 f ailed to close. A work order was issued and the valve was repaired and retested. On December 6, 1977, heatup was commenced. Chemistry problems still existed On December 7, 1977, and heatup was held at 300*F due to chemistry in 2B OTSG. heatup was continued, but a problem with the mechanical trip solenoid on the Turbine delayed unit startup. On December 8,1977, the generator was placed on line and power was increased to 50 percent full power. Af ter a five hour hold, power was increased at approxi-mately 1 percent per 8 hours to allow monitoring primary to secondary leak. On Decenber 15, 1977, power was increased to 80 percent full power and held due to station procedure limit on primary to secondary side leakage. During the 80 percent power hold, the mainstream lines RIA-40, Turbine Building sumo, hotwell sump, yard drainage, powdex cell, and Reactor Coolant System average gross gas activity were monitored closely to detect any increase in radiation due to the suspected tube ieak. On December 21, 1977, core power distribution measurements were performed using the calibrated incore detectors. It was then decided to decrease power at i percent every two hours until leak was less than .5 gpm. This was determined by RIA-40 and. RCS gross gas activity. At 75 percent full power, leakage was approximately .35 gpm. A program to monitor activity and to watch for an increase in leakage was established. 2.12-6

i I Power level remained at 75 percent until December 29, 1977. At this time,  ! Rod 4 Croup 6 dropped into the core and the reactor ran back to 48 percent full power. It was determined that pl ase AA fuse had failed; therefore, the fuse was replaced and the control rod engaged. The fuse failed again. Power was reduced to ce ttrol quadrant tilt. Shutdown was (nitiated later in the day to repair the problem. During the outage, the stator on control rod 4, group 6 was replaced, S.O.A.K. instrumentation was removed, 2 RC-16 was repacked, and an evaluation of the suspected OTSG tube leak continued. 2.12.1.2.2 Changes, Tests and Experiments Not Requiring Prior NRC Approval

                                                                                          ~ ~

The following changes, tests and experiments were carried out without prior NRC , approval pursuant to 10CFR50.59 during December, 1977.

1. Revision 0 of Station Modification ON-784 was completed. The modification involved the installation of a suppert mecder to the hotwell pump suction piping to prevent the suction header from moving laterally.

2. Revision OB of Station Modification ON-892 was completed. The modification involved the replacement of General Electric type CD-31 coupling capacitors on Keovee, the red and yellow Fases and transformers CT-1 and CT-2.

3. Revision 0 of Station Modification ON-968 was completed. The modification involved the installation of an additional alarm raflash unit for the fire detection system.

2.12-7

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DOCKET NO. 50-270

        -2.12.1.2.4               OUTAGES OR FORCED REDUCTIONS IN POWER                          UNIT NAME Oconee Unit 2 (Over 20 Percent of Design Power Level and Longer Than Four Hours)     REPORT MONTH    Decomher. 1977 SYSTEM                                                                                            RADI0 ACTIVITY CAUSE         OR                                                                   CORRECTIVE                RELEASE OR COMPONENT                  DURATION           REPORTABLE                ACTIONS                   RADIATION DATE         ,          AFFECTED                    (HOURS)  REASON   OCCURRENCE NO.                                        EXPOSURE 12/01/77     Unit shutdown to repair a packing         19.52     A       N/A              Valve was repacked.

leak on 2RC-16 pressurizer water space sample valve. 12/02/77 Unit shutdown continued due to 119.48 D N/A Chemistry problem corrected. chemistry. 12/07/77 Unit shutdown continued to correct 12.81 A N/A Problem corrected. turbine trip solenoid problem. 12/29/77 Control rod 4 group 6 dropped into - B N/A Unit shutdown was initiated a core causing power reduction to 48 subsequently. percent full power. A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION 7* B-MAINTENANCE OR TESTING F-ADMINISTRATIVE C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

DOCKET NO. 50-270 , UNIT NAME Oconee Unit 2 2.12.1.2.4 OUTAGES OR FORCED REDUCTIONS IN POWER REPORT MONTH December. 1977 (Over 20 Percent of Design Power Level and Longer Than Four Hours) RADIDACTIVITY SYST EM CORRECTIVE RELEASE OR CAUSE OR ACTIONS RADIATION DURATION REPORTABLE COMPONENT EXPOSURE (HOURS) REASON OCCURRENCE NO. DATE AFFECTED R0 270/77-17 Stator replaced. Unit shutdown f rom 48 percent full 49.28 A 12/29/77 power to repair dropped control rod.

SUMMARY

There was no single release of radioactivity or unusual radiation ,

exposure specifically associated with any outage which accounted for more than 10 percent of the allow-able annual values. A-EQUIPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION B-MAINTENANCE OR TESTING F-ADMINISTRATIVE 4 C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN)

2.12 1.3 Unit 3 2.12.1.3.1 Operating Experience Unit 3 began the month of December with zero power physics tests in progress. On December 4,1977, the generator was placed on line. During power escala-tion testing, a tilt problem was noted and power level was held at 25 percent full power. On December 5, 1977, the control rods in group 8 were checked for couplings. Control rod 3 was found to be uncoupled. Later that day, Unit 3 initiated shutdown. The generator went off line at 2046 and was placed back on line at 0138 on December 6,1977 for a manual turbine trip test. The turbine tripped at 0150. Maintenance work to recouple control rod 3 in - group 8 was completed by December 8,1977. On December 9, 1977, Unit 3 s tarted heating up. On the same day, a control rod patch verification test was performed. It was determined that control rod 9 group 1 had a shorted stator. The stator was replaced on December 10, 1977 and Unit 3 resumed heatup. On December 12, 1977, the generator was placed on line. On December 13, 1977, the power level reached 40 percent full power where it was held for power escala-tion testing. On December 15, 1977, power was increased to 75 percent full power. Unit 3 reached 100 percent full power on December 20, 1977 and remained at this power level for the rest of the month. 2.12.1.3.2 ?anges, Tests and Experiments Not Requiring Prior NRC Approval The following changes, tests and experiments were carried out without prior NRC approval pursuant to 10CFR50.59 during December,1977.

1. Revision 0 of Station Modification ON-661 was completed. The modification involved the installation of a ladder climbing safety device on the spent fuel pool decontamination pit ladders.

2. Revision 0 of Station Modification ON-673 was completed. The modification will change the area radiation monitor circuitry so the operator can read the "high" alarm setpoint on the module meter.

3. Revision 0 of Station Modification ON-784 was completed. The modification involved the installation of a support member to the hotwell pump suction .

piping to prevent the suction header from moving laterally.. j

4. Revision 0 of Station Modification ON-968 was completed. The modification involved the installation of an additional alarm reflash unit for*the fire detection system.

l 1 l 2.12-10

M MAJOR SAFETY RELATED H0tTTil 0F Decetbor. 1977 UNITi 1 MAINTEllANCE PAGE of ^ 2.12.1.3.3 OCONEE NilCLEAR STATION 1 l HONTitLY DATA SilEET PRECAlTIl0NS 2FFECT ON CORRECTIVE ACTION FOR HALFUNCTION SAFE COMPONENT REACTOR SAFET1 OPERATION'S CAUSE RESULT OPERATION HANUFACTURER - HDDEL/ SIZE W.R. NBR N A.tE  !!UEEElt 0' ring Unit O' ring replaced. Unit shut- , 27594 Rod recoupled. down. Control rod Diamond Power fallure shutdown 3 group 6 for re- 1 pairs. I Detector replaced. Redundant Signal None Westinghouse WL 23636-B 27523 indication RI'S Channel cable available. A power failure range de-tector h i n C 4 4

DOCKET NO. 50-287 2.12.1.3.4 OUTAGES OR FORCED REDUCTIONS IN POWER UNIT NAME Oconee Unit 3 (Over 20 Percent of Design Power Level and Longer Than Four Hours) REPORT NONTH Decembe r, 1977 SYSTEM RADIDACTIVITY CAUSE OR CORRECTIVE RELEASE OR COMPONENT DURATION REPORTABLE ACTIONS RADIATION DATE AFFECTED (HOURS) REASON OCCURRENCE NO. EXPOSURE 12/1/77 Refueling outage continued. 76.81 ,C N/A. 12/5/77 Unit was shutdown to recouple a 4.87 B Test conducted. control rod. During the outage, a manual turbine trip test was conducted. 12/6/77 Control rod 3 of group 8 was 151.63 A Control rod recoupled and sta-recoupled as outage continued and tor replaced. a stator replaced on control rod 9 group 1. SUHMARY: There was no single release of radioactivity or unusual radiation exposure specifically associated with any outage which accounted for more than 10 percent of the allowl , able annual values. O C A-EQUlPMENT FAILURE (EXPLAIN) E-OPERATOR TRAINING AND LICENSE EXAMINATION

d. B-MAINTENANCE OR TESTIFG F-ADMINISTRATIVE -

C-REFUELING G-OPERATIONAL ERROR (EXPLAIN) D-REGULATORY RESTRICTION H-0THER (EXPLAIN) i

2.13 ENVIRONMENTAL MONITORING This information will be provided in a separate submittal. h I 1 l

                           . 2.13-1

2.14 PERSONNEL EXPOSURE AND MONITORING I 1 Table 2.14-1 contains a tabulation (supplementing the requirements of 10 CFR 20.407) of the number of personnel receiving exposures greater than 100 mrem - in the reporting period and their associated man-rem exposure, according to duty function, e.g., routine plant surveillance and inspection, routine plant maintenance, special plant maintenance, routine fueling operation, special  ; refueling operation, and other job-related exposures for the period January 1, 1977 through December 31, 1977. e 4 1 e i i 2.14-1

                                                                                                                                                                                                                                                                                                                                       'e TABLE 2.14-1 c_               _                 . _ . _ -                                                                                                                                                                                 _ _.             _ _ .              _

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