ML19093A488

Submit Annual Operating Report 1976, Section 1A

ML19093A488
Person / Time
Site:	Surry
Issue date:	03/25/1977
From:	Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation
References
Download: ML19093A488 (480)

Text

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-~_,_'\ Annual 0-perating Report 1976 Surry Power Station

- ** Virginia Electric and Power?~*

, \ Docket Nos. 50-280 and 50-28.!.. 1 License Nos" DPH-32 and DPR~3** \ ..

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-i RECORDS FACILITY BRANCH

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ANNUAL OPERATING REPORT OF SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COHPANY FOR 1976 DOCKET NOS: 50-280 and 50-281 LICENSE NOS: DPR-32 and DPR-37

• SECTION 1 INTRODUCTION TABLE OF CONTENTS PAGE NO.

1

SUMMARY

OF OPERATING EXPERIENCE 2 PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, 45 AND SAFETY RELATED MAINTENANCE Amendments to Facility License or Technical 46 Specifications Procedure Changes that Change the Operating 51 Mode as Described in the FSAR Facility Changes Requiring NRG Approval 53 Facility Changes Not Requiring NRG Approval 55 Tests and Experiments Requiring NRG Approval 108 Test and Experiments Not Requiring NRG Approval 110 Other Changes, Tests and Experiments 117 Periodic Tests Not Completed Within Time Limits 119 Corrective Maintenance 121 OTHER EVENTS OF INTEREST 271 Chemical Releases to the Cooling Water 272 Instances Where Thermal Discharge Limits Were 285 Exceeded Radiological Environmental Monitoring 287 Fuel Handling 47 8 Fuel Characteristics 515 Effluent Releases (1974 - 1976) 660 Single Release of Radioactivity or Radiation 681 Exposure Associated With Outages

-i-

• TABLE OF CONTENTS (CONTINUED)

PAGE NO.

DATA TABULATIONS 694 Reductions in Power (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or longer 695 and greater than 20%}

Load Reductions Due to Environmental 712 Restrictions Uriit Shutdowns 737 Number of Personnel and Man/Rem Exposure 765 By Work and Job Function Results of Analysis of Non-Radiological 768 Environmental Monitoring Program SECTION 2 Gore Performance and Startup Physics Test

• Reports -

SECTION J Environmental Data

-ii-

SECTION 1

• INTRODUCTION Surry Power Station consists of two pressurized water reactors of 788 Maximum Dependable Capacity each, in MWe Net, owned by Virginia Electric and Power Company and located in Surry County, Virginia. Each unit incorporates a Westinghouse closed - cycle pressurized water nuclear steam supply system.

The Architect/Engineer and Constructor was Stone and Webster Engineering Corporation.

The condenser cooling method is river water and the James River is the condenser cooling water source. Unit One is subject to License Number DPR-32 issued May 25, 1972 pursuant to Docket Number 50-280. Unit Two is subject to License Number DPR-37 issued January 29, 1973 pursuant to Docket Number 50-281.

The date of initial reactor criticality of. Unit One was at 0219, July 1, 1972 and commercial generation of power began at 1201, December 22, 1972. The date of initial reactor criticality of Unit Two was at 0613, March 7, 1973 and commercial generation of power begun at 1201, May 1, 1973.

Major personnel changes during the year included:

Name Previous Position New Position E. M. Sweeney, Jr. Manager-Surry Power Coordinator-Nuclear Station Operations T. L. Baucom Superintendent-Station Manager-Surry Power Operations, Surry Station Power Station.

W. L. Stewart Operating Supervisor Superintendent-Station Operations J. L. Wilson Engineering Supervisor Operating Supervisor

SUMMARY

OF OPERATING EXPERIENCE

-* SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below in a chronological sequence by .unit, are shutdowns, curtailments and occurrences that were experienced during this month that resulted in significant load reductions or non-load related in-

. cidents that may be of interest.

Unit No. 1

.January 1 - This report begins with the unit at 100% power.

January 3 - At 0137 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). The PT-29.1 was satisfactorily comp-leted and the unit returned to 100% at 0240.

January 10 - At 0008 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). At 0100 the PT-29.1 was satisfactorily completed and the unit returned to 100% at 0230.

January 18 - At 0127 load was reduced to 79% power to perform PT-29.1 (Turbine Valve Freedom Test). At 0140 the PT-29.1 was satisfactorily completed and the unit returned to 100% at 0255.

January 25 - At 0250 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). The PT-29.1 was satisfactorily completed and the unit returned to 100% power at 0340.

January 31 - At 0045 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). The PT-29.1 was satisfactorily completed and the unit returned to 100% power at 0245. This report period ends with the unit operating at 100% power.

Unit No. 2 January 1 - This report period begins with the unit at 80%. The reduced power resulting from having a condenser waterbox out of service for main-

• tenance.

Unit No. 2 (continued)

• ~~nuary 2 - At 2340 the unit was returned to 100% with the maintenance on the condenser waterbox having been completed.

January 3 - At 2218 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). At 2345 the PT-29.1 was satisfactorily completed and a load increase commenced.

January 4 - At 0150 the unit was returned to 100%. At 1100 load was reduced to 84% for repairs to a trash screen bas*ket at the high level intake to the main condenser. At,1815 load was returned to 100% with the maintenance having been completed on the screen.

At 2302 a rampdown was commenced to allow for maintenance on one of the half-sized main feed pumps.

January 5 - At 0140 load was stabilized at 50% and the feed pump re-moved from service. At 0515 load was returned to 100% with the main-tenance having been completed on the feed pump.

January 7 - At 1720 a tube leak in "C" Steam Generator was confirmed and appropriate surveillance begun. Evaluation of leak data indicated continued plant operation was allowable.

January lL~ - At 1320 Power Range Nuclear Indicator NI-43 failed re-sulting in a runback of the unit to 70% power. At 1520 the unit was returned to 100% and maintenance was completed on NI-43.

January 16 - At 2127 a rampdown was commenced to remove the unit from service. The primary-to-secondary leakage had reached the point where plant operation was no longer advisable.

January 17 - At 0045 the generator was taken off the line and at 0130 the reactor was manually shutdown. At 0545 a cooldown to cold shut-down conditions was commenced for maintenance in the steam generator

• Unit No. 2 (continued)

• {~nu~ry 24 - The steam generator tube plugging completed and the plimt having been heated and pressurized to normal operating con-ditions, the reactor was taken critical at 2215.

Januar:r 25 - At 0247 an automatic reactor trip occurred. The cause was a failure in the EHC Turbine Control System which resulted in a turbine trip and reactor trip. At 0935 the reactor was taken cri-tical. The problem in the EHC System was corrected and at 1150 the turbine was synchronized to the system. A load ramp-up was commen-ced toward full load. At 1800 the unit was at 100% power. Another primary-to-secondary leak was suspected and appropriate surveillance begun. i~valuation of leak data indicated continued plant operation was allowable.

January 27 - At 0200 load was reduced to 85% to look for condenser tube leaks. At 1005 the load was returned to 100% with the mainten-ance having been completed in the waterboxes.

January 2~ - At 0512 a 30% turbine runback occurred resulting from a dropped control rod. At 0615 load was reduced to 50% as required by T.S. 3.12 regarding the reactor delta flux. At 0715 the control rod was returned to its proper position. However, power reduction to 50% was required for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as indicated in T.S. - 3.12.

__}anuary 30 - At 0620 a power increase toward full power was allow-able. However, at 0857 with the load at 84% an indicated struck rod was observed. Load was reduced to 78% to investigate. At 0943 the problem was found to be only in Individual Rod Position Indication and a power increase was begun. At 1330 the load was increased to

• • 98% power.

in progress.

This being the maximum power due to a Xenon oscillation Unit No. 2 (continued)

January 31 - At 0705 the plant conditions allowed power to be increased to 100%. At 2326 a rampdown was commenced to perform PT-29.1 (Turbine Valve Freedom Te.st). At 2400 this report periods ends with the unit operating at 86% power reducing load to perform PT-29.1 and surveil-lance in progress to monitor the primary-to-secondary leakage in the "C" Steam Generator.

E. FUEL HANDLING There were no new or spent fuel shipments during this month.

However, sixteen (16) partially spent fuel assemblies were examined by binoculars. This examination is part of VEPCO's Nuclear Fuel Service Department Program and was conducted on fuel discharged during Unit l's Cycle II refueling. Also, two BPRA inserts were relocated within the spent fuel pit as part of the forthcoming Unit 2 refueling loading pattern.

LJ.f.~

w. L. Stewart Operating Supervisor

-G-

SHUTDOWNS, CURTAILMENT AND OCCURRENCES

• Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UNIT NO. l February 1 This report period begins with the unit at 100% power.

February 11 - At 2320 load was reduced to 82% to remove "A" condenser waterbox from service to look for tube leaks.

February 12 - At 0753 the waterbox having been returned to service, load was increased. The unit was returned to 100% at 0845.

February 13 - At 0000 load was reduced to 86% to remove condenser water-boxes from service to look for tube leaks. At 0500 the waterboxes having been returned to service, load was in-creased. The unit was returned to 100% at 0555. Again, at 2240 load was reduced to 84% to take a condenser water-box out of service to look for tube leaks. At 2335 the waterbox having been returned to service, load was increased.

February 14 - At 0100 the load increase was stopped at 93% because there were indications a condenser tube leak was still present.

At 0130 load was reduced to 86% to remove the waterbox from service. At 0330 the waterbox was returned to service and a load increase begun. At 0408 the unit was returned to 100%.

February 19 - At 1437 load was reduced to 84% to remove condenser water-boxes from service to look for tube leaks. At 2101 the waterboxes having been returned to service, load was in-

• .creased. The unit was returned to 100% at 2156

• February 22 - At 1145 load was reduced to 88% to remove the condenser

• waterboxes from servic*e to look {or tube leaks.

February 23 - At 0035 the waterboxes having been returned to service, load was increased. The unit was returned to 100% at 0155.

February 28 - At 1440 a 50 }five load reduction was necessitated due to fluctuations in #2 Governor Valve. At 1505 the unit was returned to 100% power. At 1815 load was reduced to 80%

to maintain station 6T less than 15°F. This reduction was necessary due to a low level intake screen malfunction.

At 2223 load was raised to 86% which was commensurate with station 6T limitations.

February 29 - This report period ends with the unit at 86% power.

UNIT NO. 2 February 1 This report period begins with the unit at 100% power.

At 0015 load was reduced to 74% to perform PT-29.1 (Turbine Valve Freedom Test). At 0050 the test was completed and at 0150 the unit was returned to 100%. At 2135 indications of a primary to secondary leak in "C" steam generator were received. Surveillance of steam generator primary to secon-dary leakage was commenced.

February 3 At 1012 a normal unit shutdown was commenced to perform mai_ntenance on "C" steam generator. At 1303 the generator

• output breakers were opened. At 1305 a reactor trip from turbine trip occurred. The trip resulted from a turbine trip during the turbine overspeed test. A plant cooldown

• to cold shutdown condition was commenced. For detail infor-mation about repair work, refer to appropriate section of this report.

• February 7 With the maintenance having been completed a plant recovery was begun this day.

February 9 At 0215 the plant was returned to a hot shutdown condition.

At 0330 the required primary overpressure test was satis-factorily completed. At 1200 it was found that "A" main steam trip valve would not operate. Therefore, a plant cooldown to cold shutdown condition was commenced to allow for maintenance on the valve.

February 11 - The maintenance having been completed, a plant recovery was commenced to 0730. At 1940 the .plant having been returned to hot shutdown conditions, the reactor was taken critical.

At 2140 the generator was synchronized to the system and a load increase was begun. At 2400 the unit was at 54% power.

February 12 - At 0335 the unit was returned to 100% power.

February 14 - At 1840 a cross-under safety valve lifted and load was reduced to 94% to stabilize the plant. With plant conditions normal load was increased to 100% at 1923.

February 15 - At 0150 load was reduced to 74% to perform PT-29.1 (Turbine Valve Freedom Test). At 0330 the test was satisfactorily completed and load returned to 100%. At 1728, a low level intake screen malfunction resulted in exceeding the station 6T limit. A power reduction to 97% returned the 6T to <15°F.

At 1812 the intake screen was returned to service and the load returned to 100%.

February 19 - At 2315 load was reduced to 74% to perform PT-29.1 (Turbine Valve Freedom Test). At 0110 load was increased to 86%

• following satisfactory completion of the test. At 0614 all waterboxes were in service and the unit was returned to 100%.

Fehruary 22 - At 0120 load was reduced to 74% to perform PT-29.1 (Turbine

• February 23 -

Valve Freedom Test). At 0321 the test was satisfactorily completed and the unit returned to 100%.

At 1950 the "B" High Pressure Drain Pump motor tripped, load was reduced to 93% to stabilize the plant. At 2010 load was returned to 100% with the high pressure drain pump out of service.

February 25 - At 0925 the "B" High Pressure.Drain Pump was returned to service.

February 28 - At 0716 load was reduced to 80% due to failure of the 2D Circulating Water Screen at the low level intake. At 0942 load was reduced to 77% to maintain station ~T <15°F and again at 1220 load was reduced to 68% for the same reason.

At 1340 a slow load increase was started as allowed by station ~T. At 1915 the unit was returned to 100%.

February 29 - This report period ends with the unit at 100% power

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES

• Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reductions 0r resulted in significant non-load related incidents.

UNIT NO. l March 1 This report period begins with the unit at 86% power due to an intake screen malfuncti0n. At 0000 a further load reduction to 82% was required to control station 6T.

tlarch 2 At 0230 the unit was returned to 100% power following the completion of maintenance on the intake screen. At 1300, indications of .q primary to secondary leak in "C" Steam Generator were received.

Surveillance of steam generator primary to secondary leakage was com-menced.

March 4 At 2103 load was reduced to 80% to remove a condenser waterbox from service to look for tube leaks.

March 5 At 0210 the unit was returned to 100% with waterbox main-tenance having been completed.

March 10 At 1927 a reactor trip and initiation of safety injection occurred. The signal that initiated the trip and safety injection was from a high.differential pressure between the steam line and steam header. The cause was a bad fus~ holder and fuse clip in the pressure reference circuitry.

March 11 At 0450 the reactor was taken critical and at 1330 the generator synchronized to the system and a load increase commenced.

• At 1800 the unit reached 100% power. At 2130 a normal unit shutdown was commenced to perform maintenance on "A" Steam Generator.

March 12 At 0108 the generator output breakers were opened. At 0139 the reactor was manually shutdown. A plant cooldown to cold shutdown condition was commenced. For detail information concerning repair work, refer to appropriate section of this report.

• UNIT NO. 1 March 15 (continued)

With the maintenance having been completed a plant recovery commenced during the day.

March 18 At 0840 the plant was returned to a hot shutdown condition.

J\t 1000 the primary overpressure test was satisfactorily completed. At 1237 the reactor was taken critical and at 1333 the generator was synch-ronized to the system. At 1348 a turbine trip and resultant reactor trip occurred due to a high level in "B" Steam Generator. At 1413 the reactor was again taken critical and at 1530 the generator was synchronized to the system. At 1942 load was reduced from 76% to 63% to allow for removal of one of the half-sized main feed pumps from service due to a bearing failure.

March 19 At 1607 the "A" Main Feed Pump was returned to service and a load increase commenced. At 1745 the unit was returned to 100% power.

March 22 At 0130 load was reduced to 95% to control station 6T. At 0215 a power increase commenced. At 0800 the unit was returned to 100%.

March 24 At 1753 load was reduced to 96% to control station 6T. At 1935 the unit was returned to 100%.

March 25 At 0100 load was reduced to 99% to control station 6T. At 0130 the unit was returned to 100%. At 1230 load was again reduced to 98%

to control station 6T with a subsequent return to 100%.at 1305.

March 26 At 1615 a load reduction was commenced, the boron injection tank recirc. path had to be taken out of service to allow for maintenance on a valve in the recirculation line. At 1628 repairs were completed and the .tank recirculation restored. At 1637 the unit was returned to 100%.

March 27 At 2328 a rampdown was started to perform PT-29.1 (Turbine

• Valve Freedom Test)

• March 28 At 0053 load was reduced to 74%, the PT-29.1 was satisfactorily completed and the unit returned to 100% at 0425.

UNIT NO. 1 (continuedl

• Harch 29 At 2055 a normal unit shutdown was commenced to perform maintenance on "C" Steam Generator.

March 30 At 0055 the generator output breakers were opened and at 0115 the reactor was manually shutdown. A plant cooldown to cold shut-down condition was commenced. For detail information concerning repair work, refer to appropriate section of this report.

March 31 This report period ends with the unit in a cold shutdown condition with tube plugging operations in progress and other plant maintenance being performed in both the primary and secondary systems.

UNIT NO. 2 March 1 This report period begins with the unit at 100% power.

March 3 At 1630 load was reduced to 97% to reseat a cross-under safety valve which was leaking. At 1652 the valve reseated and load was increased to 100%.

Harcl1 4 At 0056 a normal unit shutdown was cor:unenced to perform maintenance on "C" Steam Generator for a primary to secondary leak. At 0636 the generator output breakers were opened and at 0702 the reactor was manually shutdown. A plant cooldown to cold shutdown condition was commenced. For detail information concerning repair work, refer to ap-propriate section of this report.

March 8 With maintenance having been completed a plant recovery commenced this day.

March 9 At 1445 the primary overpressure.test was satisfactorily conpleted. At 1935 the reactor was taken critical and at 2030 the gen-erator was synchronized* to the system. A load increase was begun.

March 10 At 0410 a reactor and turbine trip occurred from 90% power.

The trip resulted from a spike in loop flow instrumentation in "C" Reactor Coolant Loop although full core flow existed. The flow channels were re-UNIT NO. 2 (continued) calibrated and at 0647 the reactor was taken critical. At 0754 the gen-erator was synchronized to the system. A load increase was begun. At 1139 load was held at 80% power to allow for removal of a condenser waterbox to investigate for tube leaks. At 1403 the waterbox was re-turned to service and load increased to 100~~. The unit reached 100%

at 1430. At 2150 load was reduced to 86% to remove a waterbox to in-vestigate for tube leaks; March 11 At 0200 the waterbox was returned to service and at 0245 the unit was returned to 100% power. Again, at 1344 load was reduced to 89% to remove a waterbox to investigate for tube leaks. At 1812 the unit was returned to 100% following the re1Jurn of the waterbox to service. At 1743 load was reduced to 98% at Westinghouse's recommendation until a accident analysis was completed considering the maximum number of steam generator tubes that could be plugged.

March 13 At 1644 the unit was returned to 100%. The accident analysis indicated the return to maximum load was allowable.

March JA At 0058 load was reduced to 75% to perform PT-29.1 (Turbine Valve Freedom Test). 01Lf5 the PT having been satisfactorily completed the unit was returned to 100% at 0310.

Harch 18 At 2135 load was reduced to 93% to remove the "B" High Pressure Drain Pump from service for maintenance.

March 19 At 1645 the unit was returned to 100% following the return to service of the "B" High Pressure Drain Pump.

Harch 22 At 0017 load was reduced to 95% to control station 6T. At 0150 conditions allowed for the return to 100% power.

Harch 26 A fire drill with simulated injuries was conducted this day.

UNIT NO. 2 (continued) tfarch 27 At 1035 load was reduced to 93% to allow for removing 3B Feedwater Heater due to a tube leak, At 1245 the reactor was returned to 100% which now is 780 MWe with this reduced feedwater heating. At 1545 load was reduced to 98% due to problems with feedwater heater levels.

March 31 This report period ends with the unit at 98% power due to a tube leak in 3B Feedwater Heater

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES

• Listed below in a chronological sequence by unit, are shutdowns,

• curtailments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents:

UNIT NO. 1 April 1 This report period begins with the unit in a cold shutdown condition with tube plugging operations in progress and other plant main-tenance being performed in both the primary and secondary plants.

April 3 With the maintenance having been completed, the reactor was taken critical at 1711. At 2015 the generator was synchronized to the system. At 2034 an automatic reactor* and turbine trip was received from a low steam generator level during manual feedwater control. At 2105 tlle reactor was taken critical and at 2346 the generator was again synch-ronize<l to *the system and a power increase begun.

April 4 At 0505 the unit was returned to 100% power.

April 5 At 2105 the unit was reduced to 97% to control station 6T.

April 6 At 0030 load was returned to 100% power. At 1522 load was again reduced to 97% to control station 6T. At 1555 load was returned to 100%. At 2250 load was reduced to 99% to control station 6T.

April 7 At 0220 load was returned to 100%. At 0955 an emergency plan drill was held. At 1553 load was reduced to 97% to control station 6T.

April 8 At 0215 load was returned to 100% power.

April 11 At 0132 load was reduced to 74% to perform PT-29.1 (Turbine Valve Freedom Test). Mechanical problems prevented satisfactory completion of the test. At 0220 the unit was returned to 100%.

April 12 At 0720 load was reduced to 95% to control station 6T. At

• 1042 the unit was returned to 100,~ .

April 13 At 0330 load was reduced to 97% to control station 6T.

• At 0430 load was further reduced to 94% in order to control station 6T

• At 0947 the unit was returned to 100% power.

April 14 At 0330 load was reduced to 95% to control station 6T. At 0708 the unit was returned to 100% power. Again, at 0825 load was reduced to 97% to control station 6T. At 1028 the unit was returned to 100%. At 1747 load was reduced to 98% to control station 6T.

April 15 At 0230 load was returned to 100% power. At 0917 load was reduced to 98% to control station 6T. At 1205 load was returned to 100%

power. At 1800 load was reduced to 99% to control station 6T.

April 16 At 0230 load was returned to 100%.

April 24 At 0145 load was reduced to 75% power to perform PT-29.1 (Turbine Valve Freedom Test). At 0212 the PT was satisfactorily completed and load increase begun. At 0330 the unit was returned to 100%.

April 27 At 0840 a load reduction was begun to remove unit from the system. A primary to secondary S/G tube leak in "B" Steam Generator was the cause of the forced outage. At 1531 the generator was taken off the line. At 1542 the reactor was manually shutdown. A plant cooldown to cold shutdown condition was commenced. For detail information about repair work, refer to appropriate section of this report.

April 30 This report period ends with the unit in a cold shutdown condition, with tube plugging operations in progress and other plant maintenance being performed in both the primary and secondary plants.

UNIT NO. 2 April 1 This report period begins with the unit at 98% due to leak in 3B Feedwater Heater.

• • April 3 At 1712 load was reduced to 85% to allow Primary Drain Transfer System.

cycling of MOV-2585 (Loop Bypass) in an attempt to locate excessive primary leakage into the The MOV-2585 was not the source of leakage however. Contained leakage from 2-RC-24 was the source. The valve was backseated and load returned to 98% at 2245.

April 19 At 2150 load was reduced to 35% power due to gas binding of

• the bearing cooling system from a leak in a generator hydrogen cooler.

April 20 At 0105 load increased to 50% as conditions permitted, at 0800 load was increased to 70% and at 1721 load was increased to 80%

the maximum allowed with one H2 cooler isolated.

April 21 At 2110 a load reduction was commenced to remove the unit from service for refueling.

April 22 At 0040 the unit was removed from the system and at 0128 the reactor was shutdown. A plant cooldown was commenced to place the unit in a refueling shutdown.

April 25 At 0905 PT-16.3 (Containment Pressure Test) was commenced.

April 27 At 2040 commenced depressurizing il2 containment.

April 28 At 1230 the containment was at atmospheric conditions.

Commenced primary maintenance. For detail information refer to other sections of this report.

April 30 This report period ends with the unit in a refueling condition.

RCS drained with the loops isolated and the part length control rods un-latched

• SBUTDOWHS, CURTAILMENTS AND OCCURRENCES

• Listed below in a chronological sequence by unit, are shutdowns, cur-tailments a11d occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UlHT HO. 1 May 1 This report period begins with the unit at a cold shutdown condition with "B" Steam Generator tube plugging operations in progress and other plant maintenance being performed in both the primary and secondary plants. At 0145 maintenance and tube plugging was completed and plant recovery commenced.

May 2 The reactor was taken critical at 1900 and the generator was loaded at 2140.

t-1a_y_L_ - At 0250 a rampdown was commenced because "A" Steam Generator chemistry was continuing with out of spec. pH. At 0446 the generator was taken off the line.

The reactor was manually shutdown at 0613 and a cooldown commenced.

ifay 4 At 1410 "A" Stearn Genera tor was drained and refilled and plant re-covery cornrnenced.

At 1135 the reactor was taken critical and the generator was synch-ronized to the system at 1513. Power level was restricted to 60% due to a failed seal on "B" Main .Feed Pump.

Hay 6 At 0555 "B" Main Feed Pump was returned to service and a load in-crease was started. Load was held at 85% while investigating "D" waterbox for tube leaks. At 1705 the unit was at 100% p0wer. At 2215 load was reduced to

./36% to remove "B" waterbox from service to look for tube leaks.

May 7 At 0530 load was returned to 100% power.

Hay 9 At 0010 load was reduced to 75% to perform PT-29.1 (Turbine Valve

, Freedom Test)*. PT-29 .1 was satisfactorily completed and the unit returned to

-100% at 0300

• May 10 - At 1730 load was reduced to 86% to remove waterboxes and investi-

• gate for tube leaks

• The unit was returned to 100% power at 0525 following the return of the waterboxes to service.

Hay 12 - At 1250 began reducing load to 95% to investigate waterboxes for tube .leaks.

Further reduced load to 87% at 0052 to continue investigation of watcrboxes for tube leaks. At 1015 load was returned to 100%, the waterboxes having been returned to service. At 2207 load was reduced to 92% to again remove waterboxes from service to test for tube leaks.

May 14 - At 0407 the waterboxes were returned to service and at 0440 the

.unit was at 100% power. At 0957 the load was reduced to 92% to again remove waterboxes from service for tube leak investigation.

May 15 - At 0545 load was returned to 100% upon completion of tube plugging

in ;'B" and "D" waterboxes.

[-la v 19 - At lJ.19 generator luad was reduced to 790 MWe at 100% reactor power because of the loss of "Il" Low Pressure Heater Drain Pump. At 1353 the pump was restarted and load returned to 800 MWe. At 2025 commenced reducing load to 780 MWe due to the .loss of "B" Low Pressure Heater Drain Pump. The load was returned to 100% at 2040 after restarting the pump.

At 1324 load was reduced to 790 MWe due to the loss of "B" Low Pressure Heater Drain Pump. At 1500 returned the load to 100% (805 MWe) after restarting the pump.

.Hay 22 - At 2315 commenced reducing load to 75% for PT-29.1 (Turbine Valve Freedom Test).

~~- Returned load to 100% power at 0235 having completed PT-29.1.

May 31 - This report period ends with the unit at 100% power

• UNIT NO. 2

• May TI1is report period begins with the unit in a refueling condition.

Tlie reactor cnolant system is drained with the loops isolnted and the part length control rods unla tche<l.

May 2 At 1440 the reactor vessel head was lifted and at 2332 unlatching of the full length CRDM's was completed.

TI1e upper core internals were removed and at 1700 fuel movement was begun.

Hay 10 - At 0930 core loading was completed.

May ll.__ - At 1211 latching of full length CRDM's was completed.

May 12 - At 1332 latching of part length rods was completed.

May 13 - At 1311 reactor standpipe level was increased to approximately 20 feet and overflow from the reactor head vent and the head flange filled some stud holes and entered the cavity.

May 14 - At 1845 completed tensioning reactor head studs after rec.leaning the stud holes and reactor flange area.

May 21 - At 1300 RCS boron concentration was found to be 1836 ppm during sampling. This constituted an unplanned dilution from 2395 ppm due to a leak from "A" steam generator. Tubes were inadvertently cut while removing a 7th tube support plate section for Westinghouse evaluation.

t1ay 25 * - At 1400 completed filling and venting the RCS and connnenced unit recovery.

~fay 26 - At 0155 satisfactorily completed cold rod drop tests.

May.31 - At 0122 the unit was at hot shutdown and at 0409 the RCS Overpressure test was completed. At 1255 PT-7 (Hot Rod Drop Test) was completed. This report period ends with the unit at hot shutdown preparing for low power physics testing

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UNIT .NO. 1 June 1 This report period begins with the unit at 100% power. At 2040 load was reduced to 99% due to a failure of the normal level control valve bn the lB Feedwater Heater.

June 2 At 0430, by controlling the heater level manually, the unit was returned to 100%.

June 6 At 1400 load was reduced to 96% because of further level control problems with the lB Feedwater Heater. At 2027 the unit was returned to 100%.

The lB Feedwater Heater Level being controlled on the high level divert.

June 19 - At 2018 load was reduced to 74% to perform PT-29.1 (Turbine Valve Freedom Test). At 2350, with the satisfactory completion of the PT, a load increase was begun. At 2400 the load was 82%.

June 20 - At 0100 the unit was returned to 100% power.

June 23 - At 1837 load was reduced to 74% due to high groin temperature.

At 1945 the conditions allowed for a return to 100% power. At 2205 the unit was returned to 100%.

June 24 At 1830 load was reduced to 82% due to high groin temperature.

At 1843 conditions allowed q return to 100% which was accomplished at 2130.

June 30 - This report period ends with the unit at 100%.

UNIT NO. 2 June 1 - This report period begins with the unit at hot shutdown preparing for Low Power Physics Testing following a refueling shutdown. At 0410 the reactor was taken critical. At 0720 Low Power Physics Testing was begun.

UNIT NO. 2 (continued)

• At 1312 the reactor tripped from an automatic signal actuated from a low steam generator level coincident with a steam flow-feedwater flow mismatch.

The reactor was returned critical at 1342.

June 2 - At 1322 the turbine was latched for a normal start-up, however, at 1350 a failure of the #4 bearing required the turbine to be shutdown for maintenance.

June 3 - At 1900 the reactor was manually shutdown awaiting repairs on the turbine bearing.

June 9 - At 1212 the reactor was taken critical with the maintenance on the turbine bearing having been completed. At 2109 the turbine generator was synchronized to the system. At 2115 the reactor and turbine tripped from a steam generator Lo-Lo Level during manual feedwater control. At 2155 the reactor was again taken critical and at 2337 the generator was synchronized to the system. However, at 2345 another reactor and turbine trip was received from a Lo steam generator level coincident with a steam flow - feedwater flow mismatch during manual feedwater control.

June 10 - At 0025 the reactor was taken critical and at 0135 the turbine was synchronized to the system and load increased. At 1440 load was being held at 60% awaiting completion of maintenance on one of the half-sized main feed pumps.

June 11 - At 0140, with maintenance completed on the main feed pump , load was increased toward 100%. At 0730 the unit was at 75% power and holding for physics testing. At 1115 load was reduced to work on the main feed pump.

At 1250 the unit was at 54%. At 1515 the feed pump was returned to service and a load increase begun. At 2400 load was 81% power .

UNIT NO, 2 (continued)

• June 12 - At 0358 load was reduced to 60% to again perform maintenance on the "B" Main Feed Pump.

and load increased to 100%.

At 0609 the main feed pump was returned to service At 1900 the unit was at full load. Physics testing completed.

June 13 - At 0730 load was reduced to 86% to remove waterboxes to investigate for tube leaks. At 2345 the unit was returned to 100% with the maintenance having been completed on the condenser waterboxes.

June 14 - At 1100 load was reduced to 86% to remove waterboxes to investigate for tube leaks. At 2105 the unit was returned to 100% with the maintenance having been completed on the condenser waterboxes.

June 19 - At 0102 the load was reduced to 75%, to perform PT-29 .1 (Turbine Valve Freedom Test). At 0427 the reactor was returned to 100% with the satisfactory completion of the PT.

June 25 - At 01.40 load was reduced to 90% to perform steam generator carry-over testing. At 0350 the unit was returned to 100% power. At 2143 load was reduced to 88% to clean condenser waterboxes.

June 26 - At 0345 the work was completed on the condenser waterboxes. However, when a load increase was begun the #4 Governor Valve on the turbine began to cycle. Load was held at 90% to correct the valve problem. Load was in-

~reased to 96% which was deemed the maximum permitted with this valve problem.

At 1530 an inadvertent boration of the reactor coolant system occurred and load was reduced to 87% to stabilize the reactor coolant temperature. At 1647 load was retuned to 96%. At 1910 load was reduced to 86% to allow maintenance on #4 Governor Valve. At 1931 the repair of the controller for tpe #4 Governor Valve was completed and a load increase begun. At 2008 t,he unit reached 100% .

• June 30 - This report period ends with the unit at 100% power.

SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UNIT NO. l

,July 1 This report period beings with the unit at 100% power.

.I u Ly 7 At 1420 load was reduced to 95% power to remove a waterbox to plug condenser tube leaks. At 1655 load was further reduced to 90% to further cool the waterbox for maintenance.

At 1840 load was reduced to 83% power to further cool the waterbox. At 2010 the waterbox was returned to service and at 2055 load was returned to 100% power.

July 14 At 2205 an orderly shutdown was commenced on the unit due to increased primary to secondary leakage in A,B & C steam generators. At 2400 load was 55% power.

July 15 At 0022 an automatic reactor trip was received from Lo-Lo S/G Level while on manual feed control. At 0330 a unit cooldown to Cold Shutdown was commenced to allow maintenance on the S/G tube leaks.

. ,!July 20 At 0135 the maintenance having been completed, the RCS was filled and venting operations begun.

July 21 The system was brought to a Hot Shutdown Condition and at 0725 a successful overpressure test was conducted on the RCS.

During the walkdown of the containment a leak was found on the RHR isolation, MOV-1700. This tequired returning the plant to the Intermediate Shutdown condition to allow for maintenance *

• July 22 With the maintenance having been completed, the unit was returned to a Hot Shutdown Condition. At 0650 the reactor was taken critical and at 0955 the turbine generator was synchronized to the system *and power increase begun.

At 2400 load was 97% power.

July 23 At 0122 load reached 100% power. At 1400 a load reduction was begun toward 50% due to delta flux being out of the target hand. At 1715 the reactor power reached 50% power.

July 24 At 1804 a ramp-up toward 100% power was begun. At 2103 power was held at 92% for delta flux control.

July 25 The unit reached 100% at 1115.

July 26 At 0915 a reactor trip occurred during reactor protection logic testing with the reactor trip by-pass breaker not fully racked in. At 1005 the reactor was taken critical and at 1039 the unit was synchronized to the system.

At 1450 the unit was at 100% power.

July 31 This report period ends with the unit at 100% power.

UNIT NO. 2 July 1 This report period begins with the unit at 100% power.

July 2 At 2254 load was reduced to 89% power to remove condenser waterboxes from service to look for tube leaks.

July J At 0515 load was returned to 100% following completion of maintenance on the condenser waterboxes.

July 9 At 2237 load was reduced to 88% power to clean waterboxes.

UNIT NO. 2

• July 10 July 30 At 0400 load was returned to 100% following waterbox cleaning.

At 0023 load was reduced to 90% to perform PT-29.1 (Turbine Valve Freedom Test). However, due to an indicated increased primary leakage, load was returned to 100% at 0125 to perform a more accurate leak rate measurement. At 0315 a load re-duction was begun due to the excessive primary leak rate"'

At 0843 the turbine generator output breaker was opened and at 0912 the reactor was manually shutdown. The unit was cooled down to an Intermediate Shutdown Condition to allow maintenance to be performed.

July 31 This report period ends with the unit in an Intermediate Shut-Jown condition awaiting repairs to RV-2203 (Low Pressure Letdown Relief) *

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UNIT NO. 1 August 1 This report period begins with unit operating at 100% power.

August 3 At 2353 load was reduced to 80% to allow removal of one waterbox to repair condenser tube leaks.

A'ugust 4 At 0200 the waterbox was returned to service and load in-creased toward 100%. The unit was returned to 100% at 0323.

At 2320 load was again reduced to 82% to remove a condenser waterbox from service for repair of tube leaks.

August 5 At 0030 load was further reduced to 80% to work in waterbox.

At 0040 the waterbox was returned to service and load in-creased toward 100%. The unit was returned to 100% at 0215.

August 13 At 1800 a rampdown was begun due to increased primary to secondary leakage in the steam generators. At 2244 the output circuit breakers were opened and at 2248 the reactor was manually shutdown. A cooldown was begun toward cold shutdown.

August 18 At 0250 the maintenance having been completed, the Reactor Coolant System was filled and venting operation begun.

August 19 The system was brought to a Hot Shutdown Condition and at 0140 a successful overpressure test was conducted on the Reactor Coolant System. At 1320 the reactor was taken critical and at 1440 the turbine generator was synchronized to the system. However, at 1445 a turbine trip occurred due UNIT NO. 1 August 19 (continued) to a Hi Level in "B" Steam Generator. During the re-latching of the turbine a first stage impulse pressure spike resulted in a reactor trip at 1452. At 1515 the reactor was again taken critical and at 1550 the generator was synchro-nized to the system and a power increase begun. At 2400 the load was held at 38% power to allow steam generator activity to decrease with blowdown.

August 20 At 1927 load was increased to 50%. At 2237 load was increased to 75% and at 2400 load was at 80% awaiting decreased activity in the steam generator.

• August 21 At 0400 conditions allowed the return to 100% operation.

August 22 At 0820 load was reduced to 55% due to loss of vacuum in the turbine. The rupture discs on the low pressure turbine were found to be leaking. At 1905 a unit shutdown to hot standby was begun to allow maintenance on the turbine rupture discs.

At 2112 the turbine generator output breakers were opened and the reactor maintained critical.

At 0238 the generator was synchronzied to the system.

However, at 0252 a reactor trip occurred from Lo Steam Gener-ator Level in coincidence with steam flow/feed flow mismatch during startup. The level was restored and at 0327 the reactor taken critical and the generator synchronized to the system at 0426. However, again at 0446 another Lo Steam Generator in coincidence with steam flow/feed flow mismatch reactor

• trip occurred during startup feedwater control. The level was again restored and the reactor taken critical at 0520.

• UNIT NO. 1 August 23 (continued)

The generator was synchronized to the system at 0606 and a power increase begun. At 0955 a reactor trip occurred when the static breaker failure relay failed on the GIT-240 breaker.

This resulted in tripping the G-102 and GIT-240 breakers pro-ducing a reactor trip. At 1030 the reactor was taken critical and at 1125 the generator was synchronized to the system and load increased. At 1717 the unit was returned to 100%.

August 30 At 2056 power was reduced to 60% to allow for maintenance on half-sized main feed pumps.

August 31 At 0210 maintenance was completed on the main feed pumps and a load increase begun. The unit was returned to 100% at 0533.

This report period ends with the unit at 100% power.

UtHT NO. 2 August 1 This report period begins with the unit in an Intermediate Shutdown Condition awaiting repairs to the RV-2203 (Low Pressure Letdown Relief).

August 2 At 1530 maintenance was completed on the RV-2203 and unit recovery begun.

August 3 At 0408 the reactor was taken critical and at 0535 the gen-erator was synchronized to the system and a load increase begun. At 0910 load was held at 75% due to a sheared shear pin in the "D" Hi-Level Travelling Screen requiring the "D" waterbox outlet valve to be closed. At 1008 the screen was returned to normal and a load increase begun. The unit was 100% at 1125. At 2005 load was reduced to 90% to control

• UNIT NO. 2 August 3 (continued) waterbox delta-T's during repairs to the travelling screen.

At 2150 the unit was returned to 100%.

August 14 At 2305 load was reduced to 67% power to perform PT-29.1 (Turbine Valve Freedom Test) and remove waterboxes from service for repair of tube leaks.

August 15 At 0030 load was further reduced to 63% to allow work in the waterbox. At 0130 the PT-29.1 (Turbine Valve Freedom Test) was satisfactorily completed. At 1015 a load increase was possible to 79% power while continuing maintenance on

.1 I

waterboxes. At 1455 maintenance was completed and load increased. At 1618 the unit was returned to 100%.

_August 22 At 0115 the i/2 Governor Valve cycled to 20% open,this re-sulted in 16% load reduction. The unit was stabilized and at 0122 load was returned to 100%.

At 1435 commenced load reduction at 150MWe/hr. to repair l-CH-125. The repair required stopping recirculation through the boron injection tank. At 1510 the repairs were complete, flow verified through the boron injection tank, and load in-creased to 100% at 1540.

August 24 At 1427 load was reduced on the unit due to two (2) screen failures at the river. At 1615 the load was 72% and holding to maintain waterbox delta-Tin specifications. At 1745 load could be raised to 83%~ At 2400 load was at 90%.

August 25 At 0643 the unit was returned to 100% following repair to one

• of the broken screens and being able to control waterbox and station delta-T's in specifications.

-31

• UNIT NO. 2 August 29 (continued)

At 0522 a spike in the EHC System caused the #2 Governor Valve to again close to 20% open, resulting in a 4% loss in load. The unit was stabilized at 0550 returned to 100%

power.

August 31 At 221b power was reduced to allow for taking out a condenser water hox to look for tube leaks. At 2257 load was at 76%

power. This report period ends with the unit at 76% power uith the waterbox out of service

• SliUTllO\lNS

---

- ..:.:..:.:.:.:.: CUln'AILMENTS AND OCCURRENCES Listed below in a chronological sequence by unit, are shutdowns, curt.1ilments and occurrences experienced during this month which required load reductions or resulted in significant non-load related incidents.

UNIT NO. 1 Sept. 1 This report period begins with the unit operating at 100% power.

Sept. 5 At 0145 load was reduced to 80% power to perform PT-29.1 (Turbine Valve Freedom Test). At 0200 PT-29.1 was completed and at 0345 the unit was returned to 100%.

At 1120 load was reduced to 86% to allow removal of a con-denser waterbox to look for tube leaks. At 1355 the waterbox was returned to service and a load increase begun. At 1445 the unit was returned to 100% power.

At 0830 a ramp down was commenced due to the "C" SI Accumulator pressure being be low specification. This was the result of a nitrogen gas leak in the containment on the accumulator pressurization line. At 0903 the pressure was returned to the specified valve and a load increase begun. At 0920 the unit was returned to 100% power.

Sep_t~ - At 1348 a ramp down was commenced due to a plugged line in the Iloric Acid System that required securing the recirculation of the IlIT. At 1353 recirculation of the BIT was restored. A load, increase was begun and at 1357 the unit was returned to 100% power. At 1625 the normal level control valve (LCV-SD-103A) failed on the first point feedwater heater. The reactor remained at 100%, however, turbine output was reduced by about 15 l~Je/Hr

• UNIT NO. 1 (CONTINUED)

S<>J_J_i~ 17 - At 0926 a ramp down was commenced when BIT recirculation was aga.in secured wh.i le returning a portion of the Boric Acid ~

System to service after repairs. At 0929 the BIT recirculation was restored and a load increase begun. At 0923 the unit was returned to 100%. At 1530 the LCV-SD-l03A was repaired and retur1~d to service. The turbine generator output was in-creased 15MWe/Hr. At 2246 the load was reduced to 87% power to allow removal of a condenser waterbox to look for tube leaks.

~ept.__J.~'?_ - At 0143 the waterbox was returned to service and a load increase was begun. At 0400 the unit was returned to 100% power.

At 1642 the routine FQ survey results were uns~tisfactory due to a faulty computer component. Therefore load was reduced to "P" threshold power of 96% at 1750. At 2345 after repair of the computer a power increase was possible and at 2400 the unit was at 98% power with Fq surveillance in operation.

Sep_~..!._11_ - At 0045 the unit returned to 100% and the Fq survey was satis-factory.

Sept. 24 - At 1045 a unit ramp down was commenced due to increased primary to secondary leakage in the steam generators. At 1520 an auto-matic reactor trip and generator trip occurred due to feedwater control system sensitivity while in manual feed control during the shutdown. A cooldown was commenced to a cold shutdown con-dition to allow for maintenance.

Sept. 29 - The maintenance was completed on the primary and a recovery was begun to fill and vent the primary system *

• UNIT NO. 1 Sept. JO (CONTINUED)

At 1530 with the unit in hot shutdown condition, a satisfactory overpressure test was conducted. At 2230 the reactor was taken critical. This report period ends with the reactor critical and a turbine start-up in progress.

UNIT NO. 2 Sept. 1 This report period begins with the unit at 76% with a condenser waterbox out of service to look for tube leaks. At 0035 load was reduced to fi8% to limit l\.T across the unaffected waterboxes.

At 051~ the waterbox was returned to service and a power increase begun. At 0720 the unit was returned to 100% power.

At 2345 a load reduction was commenced to remove a waterbox from sPrvice due to tube leaks. At 2400 load was at 98%.

Sept. 2 At 0125 load was at 76% power. At 0715 the waterbox was returned to service and a load increase begun. At 0915 the unit was re-turned to 100%.

At 2241 a ramp down was started to clean waterboxes. At 2400 load was at 80%.

At 0055 load was at 68% to allow waterbox cleaning. At 0406 load could be increased to 85%. At 0530 all waterboxes were back in service and load was returned to 100% power.

At 1345 the turbine and reactor were manually tripped and safety injection was ITTanually initiated due to high reactor coolant leakage from a steam generator tube. A unit cooldown and depressurization was commenced to prevent any atmospheric

• leakage. There was no release to the atmosphere.

steam generator (2A) WiJS The affected identified and a cooldown to cold shutdown conditions was commenced to allow for repairs and evaluation

• UNIT NO. 2 (CONTINUED) of the leak.

This report period ends with the unit in a cold shutdown condition with major maintenance being performed on the "A" S/G to evaluate the S/G tube leak .

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below in a chronological sequence by unit, are shutdowns, curtailments and occurrences experienced during this month which required load reduction or resulted in significant non-load related incidents.

UNIT NO. 1 October 1 This report period begins with the reactor critical and a turbine start-up in pro3ress. At 0417 the generanor was synchronized to the system and a load increase begun.

At 0750 load was held at 70% due to broken shear pins on two of the traveling screens. At 0836 a slight power increase was possible, however, load had to be held at 86% to clean waterboxes. At 2400 load was 86%.

October 2 At 0125 a load increase was begun, and at 0351 the unit was at 100%.

October 3 At 0412 load was reduced to 84% due to a broken shear pin in one of the traveling screens which required reducing flow through the condenser. At 0710 load was increased commensurate with waterbox delta-T lunts.

At 0840 the unit was returned to 100%. At 1620 load was reduced to <P-threshold due to failure of the computer and FQ Surveillance required. At 1635 the power was at 96%.

At.1907 power could be increased above P-threshold and at 1930 the unit was returned to 100%.

October 5 At 0047 load was reduced to 86% to allow removins of a water-

• box from service to inspect for tube leaks. At 0332 load was returned to 100% after,:. the waterbox was returned to service.

At 0840 load had to be reduced due to decreasing vacuum in I..'

UNIT NO. 1 (continued)

• October 17 the condenser. At 1055 power was at 96%.

was returned to 100%.

At 1120 power At 0940 a unit shutdown was commenced for scheduled re-fueling outage. At 1411 the turbine was taken off the line and at 1525 the reactor was manually shutdown. After which a normal cooldown was commenced to place the unit in a refueling condition.

October 23 At 1805 the part-length control rod unlatching was completed as part of the refueling sequence.

Octnlwr 27 At 1535 the reactor vessel head was removed as part of the refueling sequence.

October 28 At 0052 full-length control rod unlatching was completed.

October 29 At 2223 fuel movement was commenced as scheduled.

October 31 This report period ends with the plant in a refueling condition with fuel movement in progress. Major maintenance in the primary and secondary systems was in progress; consult other sections of this report for more detailed information.

UNIT NO. 2 Oetober 1 This report period begins with the unit in a cold shutdown condition with major maintenance being performed in the "A" Steam Generator to determine the cause of the October tube failure *

• UNIT NO. 2 (continued)

October 20 Completed plugging 402 tubes in 2A, 2B & 2C Steam Generators as a result of the evaluation of recent primary to secondary leaks.

October 31 The report period ends with the unit still :i:.n a cold shut-down condition with major maintenance in progress and evaluation still being done on steam generator tube material.

For detailed information about maintenance items refer to other sections of this report

• SHUTDOWNS, CURTAILMENTS AND OCCURRENCES Listed below jn a chronological sequence by unit are shutdowns, curtailments and occurrences e~perienced during this month which required

. load reductions or resulted in significant non-load related incidents.

UNIT 1 Nov. 1 This report period begins with the unit in a refueling condition with fuel movement in progress. Also, major maintenance is in progress in the primary and secondary systems; other sections of this report provide detailed maintenance information.

Nov. 15 At 1720 fuel movement for loading Unit 1- Cycle 4 Core was completed.

Nov. 20 The full length control rods were latched at 2200.

Nov. 22 The reactor vessel head was set in place at 1915 and remained unbolted.

Nov. 23 At 1720 the latching of the part length control rods was completed.

• Nov.30 This report ends with the plant in a refueling condition with major maintenance still in progress in the primary and secondary systems.

UNIT 2 Nov. 1 This report period begins wilh the plant in a cold shutdown condition, with major maintenance in progess. Also, evaluation of the steam generator tube stress cracking in progress.

Nov. 30 This report period begins with the plant still in a cold shutdown condition with major maintenance in progress in the primary and secondary systems.

SHUTDmms' CURTAILMENTS AND OCCURRENCES

• Listed below in a chronological sequence by unit are shutdowns, curtail-nK:nts and occurrences experienced during this month which required load n.~duc.tt.ons or resulted in significant non-load related incidents.

UNIT NO. 1 December 1 This report period begins with the plant in a refueling condition with major maintenance still in progress in the primary and secondary systems.

December 3 Reactor Vessel Head bolted in place.

December 31 This report period ends with the plant in a refueling shut-down condition with major maintenance still in progress in the primary and secondary systems.

UNIT NO. 2 December 1 This report period begins with the plant in a cold shutdown condition with major maintenance in progress in the primary and secondary systems.

December 11 - At 0510 the plant went above 350°F, heatup continued. At 1220 the plant was in a hot shutdown condition and a satis-factory overpressure test was completed at 1411.

December 12 Full Length Control Rod at position D-6 would not move while conducting rod withdrawal for criticality. Several attempts were made to move the rod and plant cooldown to various temperatures proved unsuccessful. At 1800 the plant was cooled below 3500F.

December 13 Several more attempts were made at various plant temperatures to move the rod. Results were still unsuccessful

• UNIT NO. 2 (CONTINUED)

• December 14 The decision was made to replace the CRDH and the unit was cooled down to a cold shutdown condition at 1305 and drained to allow maintenance.

December 15 Replacement was completed on CRDM Rod D~6, the RCS was filled, vented and the rod tested satisfactory and plant heat-up begun.

December 16 The unit was returned >350°F at 1015 and heat-up was in progress when a plant cooldown was begun to await the results of the Unit 1 S/G Eddy Current data evaluation. The unit was reduced to <350°F at 2000.

December 18 At 1642 a plant heat-up was begun; preliminary results of the evaluation of the eddy current data were received. At 1715 the plant was >350°F. At 2341 the unit was returned to a hot shutdown status and a satisfactory overpressure test was performed.

December 19 At 0030 a satisfactory rod drop test was performed on Rod D-6. At 0914 the reactor was taken critical. At 1035 the reactor was manually shutdown pending further Unit 1 S/G eddy current results. The unit was borated to cold shut-down concentration. After further eddy current evaluation a dil~tion to critical concentration was performed at 1711 and at 1727 the reactor was taken critical. At 1915 the generator was paralled to the system. At 2400 the unit was at 50% power

• UNIT NO. 2 ( CONTINUED_)

• December 20 December 22 At 0237 the unit was at 100%.

At 1414 an orderly shutdown was commenced to correct a steam generator tube leak~ At 1744 the tuubine was taken off the line and at 1757 the reactor was manually shutdown.

0 At 2300 the plant was< 350 F.

December 24 At 1440 the maintenance was completed and recovery begun.

December 25 At 1740 the unit went above 350°F.

December 26 At 0400 a overpressure test was satisfactorily completed.

At 1020 the reictor ~as taken critical. At 1239 the generator was paralleled to the system. At 1241 an automatic reactor trip was received from Rx Power Lo Setpoint - operator failed to block as per procedure. The reactor was returned critical at 1301, however, a reactor trip occurred at 1335 from a spike in first stage pressure during turbine latch resulting in a reactor trip from turbine trip. At 1350 the reactor was again taken critical and the turbine paralleled to the system at 1511.

However, at 1524 a reactor trip occurred from a Low Steam Generator Level with flow mismatch due to feed control sensitivity.

during manual feed control. At 1550 the reactor was taken critical. At 1643 the genera-tor was paralleled to the system.

However, at 1650 another reactor and turbine trip resulted from a failure of the speed channel in the turbine EHC System.

At 1710 the reactor was taken critical again and the turbine paralleE~d to the line at 1828. At 2325 the unit was at.

100% .

UNIT NO. 2 (CONTINUED)

• Decemblir 28 At 0510 both high pressure drain tank pumps were inoperable and load was reduced to 98%. At 0300 load was reduced to 90%

to nllow waterbox to be removed from service. At 0719 load irns returned to 99% (High Pressure Drain Pump's still out of service).

December 10 At 1200 sampling indicated boron injection tank boron con-centration was lower than the limiting condition of operation in Technical Specifications and a load reduction begun ..

At 1513 lo*ad was at 5:2% and the sampling results indicated the tank had been restored to specification, ~rampup was started. At 65% 3 load reduction was again begun due to high condenser waterbox temperature, this started at 1645.

Load was reduced as required to maintain 6T's in specification.

At 2400 load was at 40%.

Dl!cember 31 At 0430 a load increase was begun and at 0900 the unit was returned to 100%. This report period ends with the unit at 100% .

PLANT OR PROCEDURE CHANGES, TESTS,

• EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

')

'- . Procedure Changes that Change to Operating Mode As Described in The FSAR

3. Facility Changes Requiring NRC Approval

4. Facility Changes Not Requiring NRC Approval

5. Tests and Experiments Requiring NRC Approval

6. Tests and Experiments Not Requiring NRC Approval

7. Other Changes, Tests and Experiments

8. Periodic Tests Not Completed Within Limits

9. Corrective Haintenance of Safety Related Equipment During Outages and Reductions in Power AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS

~1ENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS

• On January 7, 1976, the Nuclear Regulatory Commission issued Amendment No. 14 to the Technical Specifications for the Surry Power Station, Unit Nos.

1 and 2. The changes are of major significance relative to Station reporting re~~rements.

On January 26, 1976, the Nuclear Regulatory Commission issued Amendment No. 15 to the Technical Specifications for the Surry Power Station, Unit Nos.

1 and 2, which is designated Change No. 30. Of significance are the following changes:

1. A reorganization of system management relative to the Station Manager.

2. An updating of experience and training requirements to meet the latest ANSI Standard.

3. A major reorganization of the System Committee.

4. Additional approvals required to make procedure changes.

On March 31, 1976, the Nuclear Regulatory Commission issued Amendment No. 17 to the Operating License for the Surry Power Station, Unit Nos. 1 and 2, which is designated as Technical Specification Change No. 31. The change is the result of our request to make a change to the gaseous release rate specification.

Of significance is the following change: '

1. An increase in the gaseous release rate from 8% to 10% when averaged over any 12 consecutive months.

On April 16, 1976, the Nuclear Regulatory Commission issued Amendment No.

18* to the Operating License for the Surry Power Station, Unit Nos. 1 and 2, which is designated as Technical Specification Change No. 32. The change is the result of our request to increase the allowable river water 6T during periods of circulating water pump repairs. Of significance are the following changes:

• 1.

2.

An increase in the permitted 6T limit to 23°F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• An increase in the permitted 6T limit to 17.S°F for 14 days.

• On May 13, 1976, the Nuclear Regulatory Commission issued Amendment No. 19 to the Operating License for the Surry Power Station, Unit Nos. 1 and 2, which is designated as Technical Specification Change No. 33. The change is the result of our request to operate with a slightly positive moderator coefficient in the power range. Of significance are the following changes:

1. An increase in the moderator coefficient to 3 pcm/°F at power levels less than 50% power.

2. An increase in the moderator coefficient to 3 pcm/°F at 50% power and decreasing to O pcm/°F at 100% power.

On May 25, 1976, the Nuclear Regulatory Commission issued changes to the Technical Specification for the Surry Power Station, Unit Nos. 1 and 2.

Of ~ajar significance are the following changes:

1.. An updated allowable fuel residence time for Unit 2.

2. An increase in F ~H to 1.55.

J. The deletion of the Fxy monitoring requirement.

On June 25, 1976, the Nuclear Regulatory Commission issued Amendment No. 21 to the Operating License for the Surry Power Station, Unit Nos. 1 and 2, which is designated as Technical Specification Change No. 35. The change is the result of our request to increase the allowable condenser cooling water discharge temperature because of higher than expected river water temperatures.

Of significance are the following changes:

1. An increase, during the normal operations, in the permitted discharge temperature to lQJOF.

2. An increase, during circulating pump maintenance, in the permitted discharge temperature to 105.5°F.

On July 12, 1976, the Nuclear Regulatory Commission issued Amendment No.

22 to the Operating License for the Surry Power Station, Unit Nos. 1 & 2, which is designated as Technical Specification Change No. 36. The changes are the result of our request to reorganize the Chemistry and Health Physics Group. Of significance are ti1e following changes:

• 1.

2.

The creation of a new supervisory position.

The division of responsibility between the Chemistry Supervisor.

and the Hea.lth Physics Supervisor.

On July 27, 1976, the Nuclear Regulatory Commission issued Amendment No.

23 to the Operating License for the Surry Power Station, Unit Nos. 1 & 2, which is designated as Technical Specification Change No. 37. The changes are the result of our request to clarify the "monitoring requirements" for certain' radiation monitors. In addition, our request to modify T.S.-3.llA 4,5, and 9 to allow continuous discharge was found unacceptable by the NRC Staff. Of significance are the following changes:

1. The clarification of the component cooling radiation monitor "monitoring requirements" .

. 2. The clarification of the air ejector radiation monitor "monitoring req ui remen ts"

• On September 13, 1976, the Nuclear Regulatory Commission issued Amendment No. 24 to the Operating License for the Surry Power Station, Unit Nos. 1 & 2, which is designated as Technical Specification Change No. 38. The changes are the result of our request to provide a more realistic reduction of the maximum permissible concentration (MPC) to account for doses to personnel in unrestricted areas through the terrestrial food chain. Of significance are the following changes:

'1. Deletion of the 700 reduction factor for any radioisotope except halogens and l)articulates with half-lives greater than eight days.

2. Redefinition.of the release rate for radioiodine and radioactive materials in particulate form with half-lives greater than eight days.

', 3. Addition of new surveillance requirements to monitor the location of nearest milk produciri.g animals,

• Included in this distribution is the correction of a typographical error

• on Page 6.4-2 which was made in Change No. 36.

On September 14, 1976, the Nuclear Regulatory Commission issued

• Arnendment No. 25 to the Operating License for the Surry Power Station, Unit Nos. 1 & 2, which is designated as Technical Specification Change No. 39.

The change is the result of an NRG requirement to modify the license to include shnck suppressor specifications. Of significance are the following changes:

1. The addition of limiting conditions for operation of shock suppressors.

2. The addition of surveillance requirements for shock suppressors.

On November 26, 1976, the Nuclear Regulatory Commission issued Amendment No. 26 to the Operating License for the Surry Power Station, Unit Nos. 1 & 2, which is designated as Technical Specification Change No. 40. The change is primarily the result of a NRG requirement to submit a reevaluation of the LOCA-ECCS analysis and accompanying Technical Specifications in accordance with the Order For Modifications of License (August 27, 1976). In addition to in-cluding the effect of the higher upper head temperature, the analysis includes the effect of steam generator tube plugging up to a maximum of 12%. Of signi-ficance are the following changes:

l. An increase in accumulator level to 1089 cubic foot maximum and 1075 cubic foot minimum.

2. An increase in the total peaking factor (FQ) to 2.00.

3. The addition of APDM type surveillance.

In addition to the Technical Specifications, the NRG has stipulated the following license amendment:

Steam Generator Inspection: In order to perform an inspection of the steam generators, the plant shall be brought to cold shutdown condition with 61 equiva-lent days of operation from the effective date of issuance of this amenment.

For the purpose of this requirement, equivalent operation is defined as operation with a primary coolant temperature greater than 350°F. Nuclear Regulatory appro-val .shall be obtained before resuming power operation following this inspection.

PROCEDURE REVlSIONS THAT CHANGE THE OPERATING MODE AS DESCRIBED IN THE FSAR LIST OF PROCEDURE REVISIONS THAT

• CHANGE THE OPERATING MODE AS DESCRIBED IN THE FSAR There were no procedure revisions that change the operating mode as described in the FSAR .

FACILITY CHANGES REQUIRING NRC APPROVAL

• FACILITY CHANGES REQUIRING NRC APPROVAL There were, no facility changes which required NRC approval.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Design Change_ Unit

1. DC 73 Accumulator Level Transmitters 1,2 Description - This change replaced the Masoneilon 12500 level transmitters with Rosemount Model 1152 DP liquid level transmitters.on the Safety Injection Accumulators.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report is not increased since the Rosemount transmit-ters has a higher degree of accuracy and a greater dependability.

b. The possibility for an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report has not been created. Normal operation of this system is unchanged. Only the re-liability an~ accuracy of the instrumentation has been improved.

c. The margin of safety as defined in the basis for any technical specification i!:l not reduced. The replace-ment of the level transmitters only enables the accum-ulator volumes to be monitored more accurately.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit 2* DC 73 Boric Acid Transfer Pumps Non-Auto Control 1,2 Annunciator Modification Description - This change revised the logic of the Annunciator "Boric Acid Transfer Pumps Non-Auto Control" from an alarm when any pump is in the off to an alarm when neither pump is in automatic. New pump control switches were also added to provide contacts for the auto position.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report is not increased by this change. The Boric Acid Pumps and control circuits are unaffected.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This modification will help prevent accidents by having the subject annunciator alarm only when a real alarm condition exists.

c. The marein of safety as defined in the basis for any technical specification is not reduced. The Boric Acid Pumps and their control circuits are unaffected by this change.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of

• any technical specification.

1 Design Change Unit

3. DC 73-111 - The Removal of Control and Indication Circuitry 1 For S0V-MS-l03A through D and S0V-MS-203A through D Description - This change was to disconnect and remove electrical components of the containment spray pump steam turbine drive. The turbine drive steam piping and control has been previously removed in accordance with Design Change 73-102.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment important to the safety previously evaluated in the Safety Analysis Report is not increased; since the steam turbines drives have been disabled, this modification will not increase the probability of occurrence.

b. The possiblity for an accident or malfunction cif a different type than any evaluated previously in the Safety Analysis Report is not created. Since the subject components are a part of a previously dis-abled safety system, their removal will not create a possibility for an accident.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The removal of this equipment will only affect the Containment Spray Pump Turbine Drives, which have been previously reP.loved.

Conclusion - This design change does not constitute an

• unreviewed safety question or change the basis of any technical specification.

Design Change Unit

4. DC 73-127 - Containment Escape Hatch 2

• • Description - The existing 18" diameter manway locking device was modified to prevent inadvertent opening.

locking pin and plate assembly, a pressure equalizing A

assembly and an instruction plate were installed.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The manway lock-ing device is not evaluated in the Safety Analysis Report.

b. The possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The manway o.peration was not affected. The locking device was improved without disturbing manway integrity.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The manway locking device is not the basis for any Technical Specification. Additionally, the man-way leakage was not affected.

Conclusion This design change does not constitute an unreviewed safety question or change the basis of any Technical Specification

• Design Change Unit

5. DC 74 Reroute Oil Drains 1,2

• Description - This change involved rerouting of the various lube oil drains so that all oil leakage could be captured, reprocessed in the lube oil conditioner, and reused thereby significantly reducing the oil consumption of the station.

Summary of Safety Evaluation

a. The probability of an occurrence important to safety is not increased since this modification only provides a means of collecting waste oil.

b. There is no possibility of a malfunction of a different type occurring due to the change because the basic function of the system in-volved remains unchanged.

c. The margin of safety has not been decreased since no safety related equipment is involved.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis for any technical specification

• l Design Change Unit i

6. DC 74 Containmerit Instrument Air - Redundant Piping 2 Description - The modification consists of installing four (4) check valves - two (2) in the discharge lines of the compressors and two (2) in the inlet lines of the receivers. In the event that one compressor de-*

velops a leak to atmosphere, the discharge line check valves prevent the other compressor from discharging through this leak instead of into the receivers. The check valves in the receiver inlet lines, in conjunc-tion with the discharge line check valves, protect system pressure in the event of a receiver leak to atmosphere.*

Summary of *safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The modification improved perfortnance of the systern.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The design of t;he system was improved by this change.

Normal-operation of this system is unaffected by this modification.

c. The margin of safety as defined in the basis for any technical 'specification is not reduced. The Design Change

6. DC 74 Containment Instrument Air - Redundant Piping Summary of Safety Evaluation (continued) containment instrument air compressors are not contained in the basis of any Technical Speci-fication.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any Technical Specification

• Design Change Unit DC 74 Emergency Diesel Generator 1,2 3 Audio Alarm 1,2 7* &

Monitoring EFI-TX Relay Description - This change involved adding an audio alarm to the Emergency Diesel Generator Protection to monitor the EGI-TX relay which trips J3 or H3 breakers.

Summary of Safety Evaluation

a. The p~obability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report would not be increased. The EG (1,2,3)-TX relays have spare mechanical type contacts which open when the relay is energized. This alarm will remind the operator that the "H3" breaker is being held open because the EG(l,2,3)-TX relay is energized.

b. A possibility for an accident or malfunction of a different type than any evaluation previously in the Safety Analysts *Report would not be created. The alarm would be a redundant indication of relay coil status (energized or deenergized),

c. The margin of Safety as defined in the basis for technical specifications would not be reduced.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any Technical Specification

• Design Change Unit

8. DC 74 Addition of High-Low Level Alarm to 2 Emergency Diesel Generator Auxiliary Fuel Oil Tank Descriptio~ - The change added a level switch to the auxiliary fuel oil tank. This switch activates an alarr.1 which alerts the operator to the. fact that the tank level is abnormal. A low level alarm helps pre-vent a violation of Technical Specifications; a high level alarm helps prevent tank overflow and environ-mental pollution.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The alarm sw-itch action is independent of any control function.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The alarm switch does not affect the operation of the fuel oil supply system.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The addition of the alarm helps to ensure an adequate fuel oil supply.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of

• any technical specification.

Design ChangE:_ Unit

9. DC 75 Modification to Component Cooling Heat 1,2

~~{c~1ng~1.:_ Radiation Mon itorit_!_g_ ~ tern Dcseriptior1_ - Replace existing radiation sampling pump RM-SW-107 with four (4) positive displacement type pumps, one sampling each component cooling heat exchanger.

_Summa~ Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety and previously evaluated in the Safety Analysis Report is decreased.

The continuous monitoring of the service water fro~ each of the component cooling water heat exchange.rs will be more reliable and more re-p.resentative with the one pump per cooler arrange-ment.

b. The possibility for an accident or r.1alfunction of a**different type than any previously evaluated in the FSAR is not created. The change to the method of obtaining the flow through the radiation moni-tor (RM-SW-107) will only improve the reliability of this system and not affect any other system.

c. The margin of safety as defined in the basis for any technical specification is not reduced. This change does not affect the basis for any technical specification

• Unit 9* DC 75 Modificatio~ to Component Cooling Heat 1,2 Exehang~r Radiation Monitoring System (continued)

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

10. DC 75 Removal of Turbine "Fast Valving" Feature 2 Description - The "Fast Valving" feature (CIV) was disabled during start-up. This change provided for the disabling using the method recommended by West-inghouse, thus utilizing the most effective method and allowing for the units to be identical in this respect.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The "Fast Valving" feature was not evaluated in the Safety Analysis Report.

b. The possiblity for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This change did not affect the safety of the unit since dis-abling the feature will not prevent the operation of any turbine protection functions.

c. The margin of safety as defined in the basis f.or any technical specification is not reduced. The turbine "Fast Valving" feature is not the basis of any tech-nical specification.

Conclusion - This design cha~e does not constitute an unreviewed safety question or change the basis of any

• Technical Specification.

_Design Chan~ Unit

11. DC 75 Steam Generator Blowdown Trip Valves 1,2 Interlock Modifications Q_escriptio~_ - In order to sample the Stearn Generators in wet layup or cold shutdown, the use of jumpers was necessary to bypass certain interlocking features to open the trip valves. This has led to a Reportable Occurrence in the past for one reason or another.

To prevent this from happening three (3) administra-tively contr6lied key switches were installed to by-pass the interlocks and allow the operation of the three trip valves. The use of a key switch would also light a permissive light on the bypass status board.

Sumrna_£Y._ of Safe SY_ Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The key switches are administratively controlled to be used only at cold shutdown or wet layup.

b. The possiblity for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The contain-ment integrity is not required at cold shutdown.

c. The margin of safety is not reduced because con-tainment integrity is not required at cold shutdown.

Conclusion - This design change does not constitute an

• unreviewed safety question or change the basis of any technical specification.

l Design Change Unit

12. DC 75 Emergency Turbine Oil Pump Auto Start 1,2 Modification Description - This change added a relay to the Emergency Turbine Oil Pump (ETOP) start circuit. It will initiate an ETOP start if the Turning Gear Oil Pump (TGOP) suffers a loss of A.C. power or a thermal overload. In addition, a pressure switch was installed to sense decreasing oil pressure. This switch will prevent false starts of the ETOP whenever the TGOP is removed from service for main-tenance.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of the equipment important to safety previously evaluated in the Safety Analysis lleport is not increased. The new start function is independent of any previously installed start function.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This change does not introduce any function not prev-iously discussed in the Safety Analysis Report.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The additional start function increases the margin of

• safety.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification.

Design Chang1:

Unit

13. DC 75 Condensate Water Truck Station 1,2 Description - This change installed a concrete pad, two electric driven pumps, and associated piping and valves. The system permits pump-ing of condensate water from two trucks to either condensate tank or from either condensate tank to the trucks *

.summ~ of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The condensate tanks are not evaluated'in the Safety Analysis Report~*

b. The possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The truck station does not affect any system involved in the Safety Analysis Report.

c, The margin of safety as defined in the basis for any technical specification is not reduced. The truck station is not the basis for any technical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis

• of any technical specification.

Design Change Unit

• 14. DC 75 Reactor Coolant Pump Underfreguency Relay Circuit Modification Description - This design change implemented a wiring 1,2 modification so as to deter an underfrequency relay trip to ICS coil failure by excessive ambient temp-erature. The underfrequency relay is designed for momentary-*energization only and this modification will remove power from the ICS coil after if operates thus eliminating the possibility of overheating and the need for a timely manual reset of the circuit at the Reactor Coolant Pump cubicles.

Summary of Safety Evaluation

a. The probability is not increased because the modification does not alter the actual tripping function of the underfrequency relay.

b. The possibility is not created because the mod-ification only affects the circuit operation after the pump has been tripped.

c. The margin of safety is not reduced because the modification does not alter the actual tripping function of the underfrequency relay.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 15. DC 75 Lube Oil Vapor Extractor Separator Description - This change installed a Peetless separator in the discharge line from the vapor 2

extractor. This was necessary because the present collector does not adequately remove all oil vapors.

Sul'lillary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. This equipment was not evaluated in the Safety Analysis Report.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This change did not affect the safety of the unit.

c. The margin of safety as defined in the basis of any technical specification is not reduced. This equipment is not the basis of any Technical Speci-fication.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any Technical Specification

• Design Change Unit

• 16. DC 75 Main Steam Trip Valve Modification (Schutte & Koerting=)

Description - This design change improved the opera-1,2 tional reliability of the Main Steam Trip Valves by installing positive stops for the discs to bear against in the open position. The actuating cylinders were also replaced with lal'.'.ger ones to provide the necessary force to keep the disc firmly seated against the stop.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction or equipment impor-tant to safety and previously evaluated in the Safety Analysis Report will not be increased.

By performing the Schutte & Koerting modification on the main steam trip valves their operational reliability will be greatly improved. The posi-tive stop and larger air operating cylinders will eliminate the possibility of the valve sticking in the open position. In addition, the possibility of rock shaft failure will be greatly reduced by the elimination of the cyclical torsion load which the valves now experience.

b. A possibility for an accident or malfunction or a different type than previously evaluated in the Safety Analysis Report has not been created since basic system design has remained unchanged. The purpose of the Schutte & Koerting modification is to improve the existing components operation and r,73-

16. DC 75 Main Stearn Trip Valve Modification 1,2 (Schutte & Koerting)(continued)

• SUI:1mary of Safety Evaluation b.

c.

reliability.

The margin of safety is not reduced. Any steam lin*e rupture will involve a high flow of steam which will cause the main steam valves to close considerably faster than the cold shut-down rate of closure due to the force exerted on the disc by the steam flow. This force has been increased since the disc projects down into the line of flow more than before due to the positive stop (79° open versus 80° open before modification) which will result in improved closure time.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• r Design Change Unit rt

• 17. DC 75 Charging Pump Miniflow Orifice Replacement Description - The installed miniflow orifices and orifice bypasses were replaced with Westinghouse furnished Pacific 2

eleven stage orifices. The replacement was necessary due to a severe erosion problem which had been attributed to the miniflow orifice performance characteristics.

Sur:unary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report is not increased. The system basic design remains unchanged and all material used in the mod-ification was equal to or superior to that used in original construction.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The basic system design remains unchanged. System operating parameters (temperature and pressure) are the same as before the modification.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The elimination of the orifice bypass improved system reliability because of the elimination of welds and mechanical joints.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification.

Design Change Unit

• 18. DC 75 Replacement of Recirc. Spray Valves (MOV-RS-155(255) A & B)

Descrip_ti~ - The modification accomplished by this 1,2 design change removed existing solid wedge, 12", weld end, gate valves and replaced them with 12" flanged end plug valves. Remote operators were also replaced with larger operators with reduction gear drives to accomodate the greater break-away torque and the 90 degree actuation required by the new plug valves.

Summa~ Safety Evaluation

a. The probability is not increased since the new valves will be designed and installed according to present system limitations and requirements and no safety system function will be changed.

b. The possibility is not increased since no new system function is created and present system safety functions remain unchanged.

c. The margin of safety is not reduced since the functions of the system remain unchange<l.

Conclusion - This design change does not constitute an unreviewed safety question ,or change the basis of any technical specification

• Design Change Unit

• 19, DC 75 High Pressure Drain Pump Cavity Dewatering Systel_!!

Description - This modification eliminated sources of 1,2 water in leakage to the H.P. Heater Drain Pump cavity by increasing the length of a vent pipe, capping off a 2" standpipe, and completely sealing the pump casing to the cavity to eliminate ground water.

Summary of Safety Evaluation

a. The probability of an occurreRce important to safety is not increased due to the fact that the cavity will now remain dry as originally intended.

b. There is no possibility of a malfunction of a dif-ferent type occuring due to the modification since no change in system design is involved.

c. The margin of safety is not decreased since no system boundaries are involved.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 20, DC 75 Low Head Safety injection Description - The suction header from the Refueling Water Storage Tank to the Low Head Safety Injection 1,2 pumps was split with a suction valve and check valve in each line thus providing redundant suction supply.

Iri addition, the recirc. lines from each pump were made independent. The above action insures that a spurious single component faiiure will not render the entire Low Head Safety Injection System inoperable.

This action was initiated to comply with the. Nuclear Regulatory Commission Document, BTP EICSB18 (Single Failure Criteria).

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased. The "undesirable function" failure mode as stipulated in the new requirements of 10 CFR 50.46; 10 CFR 50 Appendix K, and BTP EICSB18 was not previ-ously evaluated. Renee, this failure mode was analy-zed and.the proposed modifications will provide re-dundancy for the Low Head Safety Injection System and the previous evaluation will not be affected, except that the scope is increased as required by NRC directives

• Design Change Unit

• 20. DC 75 Low Head Safety Injection (continued)

Summary of Safety Evaluation (continued)

b. The possibility for an accident or malfunction of 1,2 a different type than ay previously evaluated in the FSAR is not created. The accident analyses as stated in Section 14 will not be affected.

Meeting the new sing.le failure requirements of 10 CFR 50.46 by performing the modifications will insure redundancy of Low Head Safety Injection System and provide added assurance that the system can perform its intended function.

c. The margin of safety as defined in the basis for any technical specification is not reduced since the modifications provide increased assurance that the Low Head Safety Injection System will perform its intended function.

Conclusio~ - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 21. DC 75 Containment Instrument Air Compressor Interstage Cooling Description - This change installed water cooled 2

interstage cooling on the compressors as an interim solution to the compressor failure problem.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. A failure in the component cooling water system or the instru-ment air system is not considered in the accident analysis in FSAR Section 14.5.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The addition of the cooler and components will be de-signed and installed to present system requirements, thus assuring that component cooling capabilities are not disturbed.

c. The margin of safety as defined in the basis for any technical specification is not reduced. Since no safety function is change<l.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification .

Design Change Unit

• 22. DC 75 Steam Generator 2.0 Inch Inspection Openings Description - This change installed inspection ports 2

in the secondary shell of the steam generators, near the tube sheets. These openings also permit a more thorough sludge removal procedure.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The probability of failure of the 2.0 inch inspection port is less than that of the already installed 6.0 inch diameter handholes. This is discussed thoroughly in Westing-house Safety Review NS-MFSE-379.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The steam generator shell is the only component affected by this change. The only accident that could possi-bly result from this change is a steam or feedline break. The Westinghouse safety review shows that inspection port failure is well within the boundaries of existing analysis presented in the FSAR.

c. The margin of safety as defined in the basis for any technical specification is not reduced. Steam gener-ator pressure/temperature requirements addressed in Design Change Unit

22. DC 75 Steam Generator 2,0 Inch Inspection 2 Openings (continued)

Summary of Safety Evaluation (continued)

c. the Technical Specifications are not affected by this modification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 23. DC 76 Secondary Drains - Flow Transmitter Flexible Hose Connections Description - Piping connecting isolation valves 1,2 l-SD-51 and 1-SD-52 to line 10" WID-4-301 failed at point approximately 2" from the 10" pipe. The cause of the problem was due to extreme stress con-ditions due to the cyclical translation of the 10" pipe and the torsional and control lever loading imposed by the 1" globe valve and its associated piping. This change eliminated the problem by changing the 1" globe valve to 1/2" Whitey valve and installing a length of flexible metal hose between the iJhitey valve and the existing 1/2" O.D. tubing.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. This portion of the Secondary Drain System is not addressed in the Safety Analysis Report.

b. The possibility for ,an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This change is only to the piping of the flow trans-

• mitters which will not adversely affect the per-formance of the system. A piping failure possi-bility is not increased by this modification. As Design Chang~ Unit

• 23. DC 76 Secondary Drains - Flow Transmitter Flexible Hose Connection3 (continued)

Sunmary of Safety Evaluation (continued) 1,2

b. no other changes will be made to the system, no other possibilities for a different accident exist.

c. The margin of safety as defined in the basis for any technical specification is not reduced. Flow transmitter piping for this system is not the basis of any technical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

24. DC 76 Westinghouse Independent Fuel Evaluation 1,2 System Design Package Description - This change provided for the installation of the Westinghouse Independent Fuel Evalaution System.

The system is composed of the following: Fuel Assembly Exanination System, Fuel Rod Examination System, Fuel Rod Handling System, and a Fuel Examination Bridge System. This system was incorporated to provide a capability for fuel examination which would be inde-pendent as possible of the fuel building bridge and assembly handling tool.

Summary of Safety Evaluation

a. The probability of occurrence of an accident analy-zed in the safety analysis report will not be in-creased since fuel asseI!lblies will be handled with the fuel bridge. The design of the IFE bridge and rod handling tool is such that the probability of a rod handling accident has not been increased.

The consequences of such an accident are not in-creased since the amount of radioactivity released by the rupture of a single rod would be normal when compared with a fuel assenbly handling acci-dent as previously analyzed in the Safety Analysis Report.

b. The possibility for an accident or malfunction of

• a different type than any previously evaluated in the Safety Analysis Report has not been created.

Design Change Unit

• 24. DC 76 Westinghouse Independent Fuel Evaluation System Design Package Summary of Safety Evaluation (continued) 1,2

b. A fuel handling accident is analyzed in section 14.4 of the FSAR.

c. The margin of safety as defined in the basis of the technical specifications is not reduced since all applicable technical specification requirements have been met.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification.*

Design Change Unit

• 25. DC 76 Steam Generator J-Tube Modification Description - The scope of this change was to install vents (J-Tubes) on the steam generator feed ring and 2

plug existing holes on the bottom of the feed ring.

This change was designed to eliminate the possibility of secondary system fluid flow instability (water hammer) under certain operating conditions.

Stmunary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to the safety previously evaluated in the Safety Analysis Report is not increased. The modifications made to the steam generator further decreased the probability of an undesirable occur-rence.

b. The possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. This change will further decrease the possibility of a malfunction.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The design change does not affect the basis of any technical specification.

Conclusion - This design change does not constitute an

• unreviewed safety question or change the basis of any technical specification.

Design Change Unit

26. DC 76 Pump Overhead Clearance for "A" High Pressure 1,2 Feedwater Heater Drain Pump Description - The modification was made to eliminate having to remove "B" H.P. Feedwater Heater Drain Pump each time the "A" H.P. Feedwater Heater Drain Pump was removed for maintenance. The change consisted of re-locating the feedwater heater drain pump recirculation line.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-,

tant to safety previously evaluated in the Safety Analysis Report is not increased. The additional material required to relocate the pipe will not provide any additional stresses or flow restric-tions to the system.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The rerouting of this pipe does not alter the functions of the system.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The routing of the pipe is not a basis for any tech-nical specification.

• Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification.

Design Change Unit

• 27. DC 76 Fuel Tool Examination Hoist Description - This change installed a one ton electric chain hoist on the rear of the fuel 1,2 building 125 ton crane. The purpose of the hoist is to lift fuel handling tools clear of the fuel for inspection prior to use during refueling.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The spent fuel crane operation is not evaluated in the Safety Analysis Report.

b. The possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The fuel tool hoist does not affect any system in-volved in the Safety Analysis Repo~t.

c. The margin of safety as defined in the basis for any technical specification is not reducerl. The spent fuel crane is not the basis for any tech-nical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 28. DC 76 Emergency Escape Hatch in Equipment Hatch Description - The purpose of this design change was to install a secondary means of egress from the con-1,2 tainment. The modifications included the installation of 5 1 -6 11 diameter personnel air lock in the existing machinery hatch. The 12' length of the new personnel air lock is designed to accomodate a stretcher.

Summary of Safety Evaluation

a. The probability of occurrence or consequences of an accident or malfunction of equipment important to safety and previously evaluated in the Safety Analysts Report has not increased. The emergency escape hatch is similar in construction to the existing personnel hatch and is designed to main-tain containment integrity equal to the existing hatch requirements.

b. The modification does not create the possibility for an accident or malfunction of a different type than any evalauted previously in the Safety Analy-sis Report. The emergency escape hatch is under administrative control and is only to be used under emergency conditions when escape through the per-sonnel hatch cannot be accomplished. Any release of airborne contamination resulting from the use of the emergency escape hatch is not considered to

• be significant because of the small volume of the hatch.

1. 6 x 10 The emergency escape hatch represents

-2

% of the containment, volume. Therefore, Design Change Unit

• 28. DC 76 Emergency Escape Hatch in Equipment Hatch Summary of Safety Evaluation (continued) the amount of airborne contamination that could 1,2 be trapped in the emergency air lock is not con-sidered to be significant.

c. The margin of safety as defined in the basis for any Technical Specification is not reduced.

This change does not affect the basis of any technical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

• 29. DC 76 Steam Generator Tube Support Plate Removal Description - This change involved removing a small portion of the tube support plate with some tubes 2

still intact. The purpose of this evolution Yas to obtain a speciman for the investigation of the tube denting phenomenon. In addition to the support plate ,removal the following work was also performed:

crud collecting, neasurements of annulus width between secondary shell, and wrapper and eddy current testing.

Summary of Safety Evaluation This work was determined not to provide an unreviewed safety question therefore:

a. The probability of occurrence or the consequences of an accident or malfunction of equ:iipment impor-tant to safety and previously evaluated in the Safety Analysis Report is not increased.

b. A possibility for anaccident or malfunction of a different*type than any previously evaluated in Safety Analysis Report is not increased.

c. The margin of safety as defined in the basis of the technical specification is not increased.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• l Design Change Unit I

I

30. DC 76 Control Room Air Conditioning Modification 1,2  !

I

_Description - This change modified the ductwork to computer rooms 1 & 2 to supply air directly to the computer cabinets in order to reduce the temperature of the computers and improve their availability.

Summary of Safety Evaluation This design change does not constitute an unreviewed safety question because:

a. The probability of occurrence or the consequences of an a_ccident or malfunction of equipment impor-tant to safety and previously evaluated in the Safety Analysis Report is not increased because the failure of ducting in the _Control Room ven-tilation is not evaluated.

b. A possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created because the only modification is to ducting which will not adversely affect the performance of the system.

A ducting failure possibility is not increased by this modification. As no other changes will be made to the system, no other possibilities for a different accident exist.

c. The margin of safety as defined in the basis for any technical specification is not reduced because no margin of safety for the control room ventila-tion system is addressed in Technical Specifications.

Design Change Unit

• 30. DC 76 Control Room Air Conditioning Modification Conclusion - This design change does not constitute an unreviewed safety question or change the 1,2 basis of any technical specification

• Design Change Unit

• 31. DC 76 Turbine Load Rate Modification Description - In order to prevent raising the temp-erature of the water at the discharge control struc-1,2 ture the turbine load rates of 6% per minute arid 8%

per minute were changed to 0.3% per minute and 0.5% per minute. This change was accomplished by changing the value of two resistors on the "Clock Rate Driver 2" card of the EHC SysteN.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety previously evaluated in the Safety Analysis Report is not increased. The circuitry being changed is not required to perform a pro-tective function.

b. The possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created. The proposed design change does not change the role of the circuit being modified, only the output signal in the designed role.

c. The margin of safety as defined in the basis for any technical specification is not reduced. The circuitry involved is riot the basis of any tech-nical specification.

• Conclusion - This design change does not constitute unreviewed safety question or change the basis of any technical specification.

an Design Change Unit

• 32. DC 76 M.G. Set Varmeters & Modifications Description - This change installed a varmeter on each of the control rod drive motor generators (4).

1,2 In addition, neoprene vibration absorbers were in-stalled to reduce the amount of vibration previously transmitted to the directional overcurrent trip relays.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety that was previously evaluated in the Safety Analysis Report is not increased be-cause the varmeters and vibration modification do not affect present control levels, and are only for more clarification of reactive loads and isolating _vibrations.

b. A possibility for an accident or malfunction of a different type than one evaluated previously in the Safety Analysis Report isn't created be-cause the modification does not affect the control rod generators, but only monitors reactive loads which does not adversely affect the performance of the system.

c. The margin of safety as defined in the basis for any technical specifications is not reduced be-cause no margin of safety for control rod MG

• varmeters and vibration modification is add-ressed in technical specifications.

Design Change Unit 32, DC 76 M,G, Set Varmeters & Modifications 1,2 Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification

• Design Change Unit

33. DC 76 Replacement of RV-1203 & 2203 1,2 Description - This change replaced existing relief valves in the letdown line of the chemical volume control system (RV-1203 & 2203) with a superior valve suited for the intended service.

Summary of Safety Evaluation

a. The probability of occurrence or consequences of an accident or malfunction of euqipment impor-tant to safety and previously evaluated in the Safety Analysis Report has not increased. The capabilities of the replacement valve as evalu-ated in the Stone & Webster letter of September 13, 1976, are acceptable for installation in the syst6'Jll.

b. The modification does not create the possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analy-sis Report. The new valve meets the pressure re-taining capabilities of the existing valve, there-fore, the integrity of the system will be maintained.

c. The margin of safety as defined in the basis for any technical specification is not reduced. This change does not affect the basis of any technical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis 1* of any technical specification.

Design Change Unit

34. DC 76 Removal of S/G Tube Rl C7, S/G A, . 2 Description - The basic purpose of this design change was to locate a 3" diameter hole in the secondary shell of the generator so that a leak-ing tube from Steam Generator "A", Unit No. 2 could be removed for analysis to determine the cause of the failure. In addition several other tubes were removed and visual inspections were conducted to provide data for the continued eval-uation of the steam generators.

Summary of Safety Evaluation The repair of the three (3) inch opening will be in accordance with the requirements of Section III of the ASME Code, just as the original vessel; therefore, all design criteria are main-tained. Therefore, all analyses remain valid and the consequences or probability of occurr-ences are not affected.

Since the welded plug satisfies Code require-ments, failure is not expected. Even if failure of the weld did occur and the plug is hypothesized to blow out and become a missle, the shield wall around the steam generator would contain the plug.

The proposed modification does not affect the heatup and cooldown limitations of the steam

• generator *

-*99-

Design Change Unit

• 34. DC 76 Removal of S/G Tube Rl C7, S/G A, Summary of Safety Evaluation (continued)

In the unlikely event of the plug being blown 2

out, the flow out of the hole would be less than the feedwater make-up rate. It should be noted that the rupture of the plug accident would affect the core in the same manner as a small feedwater line break. It should be noted that at the time Surry 1

~nd 2 was licensed a feedwater line break accident analysis was not required; therefore, it is not analyzed in FSAR.

The proposed change does not effect the basis of any technical specification.

In suJllillary, th~. proposed modification will meet applicable Code requirements and the same design criteria as was used in the initial design of the steam generator.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification *

• -100-

Design Change Unit

• 35. DC 76 Hot Head Issue - Installation of Thermocouples Description - The purpo~e of tl1is design change was to install three (3) thermocouples in the reactor vessel 1

head region to gather emperical information with respect to the actual temperatures in this area.

Summary of Safety Evaluation

a. The probability of occurrence or consequences of an accident or malfunction of equipment important to safety and previously evaluated iri the Safety Analysis Report has not increased.

b. The modification does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report.

c. The margin of safety as defined in the basis for any technical specification is not reduced. This change does not effect the basis of any technical specification.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification .

• -101-

Design Change Unit

• 36. DC 76 Isolating Reserve Station Service Transformers Description - The purpose of this modification was to install knife blade switches to isolate the dif-1,2 ferential and pilot wires on the lock out relays to avoid possible tripping of bus feeder breakers during reserve station service transformer testing.

i.

I Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety that was previously evaluated in the Safety Analysis Report is not increased be-cause the circuit is not affected with switches closed. Switch design and administrative control will insure that the switch is closed during normal operations. Knife blade switches are a better method of isolating circuits for testing than lifting wires, which could be advertently shorted causing harm to equipment and personnel. Also, they do not affect present control level.

b. A possibility for an accident or malfunction of a different type than one evaluated previously in the Safety Analysis Report isn't created; because, as above, the circuit is not affected during normal operations. With the mddification, isolation of RSS transformer, no other components are in jeopardy; hence, the system performance isn't adversely affected.

-102-

Design Change Unit

• 36. DC 76 Isolating Reserve Station Service Transformers Summary of Safety Evaluation (continued)

c. The margin of safety as defined in the basis for 1,2 any technical specifications is not reduced, be-cause the required "dependable alaternate source" is maintained during testing by back feeding from the opposite unit.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification *

-103-

Design Change Unit

• 37. DC 76 Steam Generator Support Upper Restraint Anchor System Studs Description - During an inservice inspection a broken 1,2 Vascomax stud and several cracked studs were found on the steam generator upper support girth straps. The studs and nuts were redesigned to minimize stress and corrosion.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety and previously evaluated in the Safety Analysis Report is not increased.

1. The redesign.of the Vascomax studs and nuts:

will reduce the probability of failure of the studs.

2. The new coating will give more protection to the studs from the 'environment.

b. A possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created.

1. The same material will be used in the upper restraint anchor system studs.

2. Manufacturing processes will be used to reduce stresses in the Vascomax studs.

c. The margin of safety is not reduced because the proposed modification will meet the station design

• criteria.

-104-

Design Change Unit

37. DC 76 Steam Generator Suppport Upper Restraint 1,2 Anchor System Studs(contiinued)

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification .

-105-

Design Change Unit

38. DC 76 Accumulator Level Transmitters 1,2 Description - In order to allow for more volume in Safety Injection Accumulator the top tap of the level transmitter was relocated. The tap was connected to the nitrogen supply line at the top of the accumulator.

Summary of Safety Evaluation

a. The probability of occurrence or the consequences of an accident or malfunction of equipment impor-tant to safety and previously evaluated in the Safety Analysis Report is not increased because the function of the accumulator is not changerl, only the path to the level transmitters.

b. A possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created because basic system arrangement and function is not changerl.

c. The margin of safety as defined in the basis for any technical specification is not reduced, the Safety Injection System function is not affected by this change.

Conclusion - This design change does not constitute an unreviewed safety question or change the basis of any technical specification *

• -106-

Design Change Unit

• 39. DC 76 Recirculation Spray System Su~unary of Safety Evaluation (continued)

b. A possibility for an accident or malfunction 1,2 of a different type than any evaluated previ-ously in the Safety Analysis Report is not created.

These changes have been evaluated and it has been determined that they will have no appre-ciable effect on the recirculation spray system coverage or operation. This can be demonstrated by the following comparisions:

1. Flow through one level switch cage and associaged tubing and fittings is 8 gpm during system operation and flow through two drain lines is 30 gpm (15 gpm each).

Total recirculation spray pump capacity is 3,500 gpm; therefore, the cumulative effect of two drain lines and one vented level switch is approximately one percent of total pump capacity.

2. Pressure drop through the new 8. 75 in. I.D.

pipe penetration sleeve is less than 0.5 psi.

Total system dynacmic pressure drop (including the DP across the nozzles) is approximately 50 psi; therefore, the change due to the de-creased penetration I.D. is less than one percent.

-107-

TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL

• -108-

TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL

• There were no tests or experiments which required NRC approval *

-109-

TESTS AND EXPERIMENTS NOT REQUIRING NRC APPROVAL

-110-

TESTS AND EXPERIMENTS THAT DID NOT

• ST-21

.REQUIRE NRC APPROVAL Special Test for Investigation of Erosion of Charging Pump Miniflow Line and Orifice The purpose of this test was to provide information to determine if cavitation or erosion existed in the charging pump miniflow lines. The test required valve lineups and operations which are normally expected and therefore created no new accidents.

In addition, the nature of the test did not reduce the margin of safety or increase the consequences of any previously analyzed accident. The test was performed four times on Unit One -

1-20-76, 2-26-76 (B arid C Pumps), 4-20-76 (A Pump), and 5-11-76 (B Pump); and once on Unit Two 7-76. The test results were satisfactory; however, further testing is anticipated to monitor the performance of the miniflow line.

ST-40 Steam Generator Narrow Range Level Indication The purpose of this test was to record steam generator narrow range level indications during full power steady state operation.

Since the test involved the use of normal station instrumentation, the consequences of any accident previously analyzed in the safety analysis report were not increased and no new accidents were created.

The margin of safety was not decreased. The test was successfully completed on Unit One on 1-4-76 with the acquisition of the re-quired data .

• -111-

ST-41 BFD Relay Drop Out Times

• This test was used to evaluate the drop out times for all BFD relays which are normally energized during power operation on the DC bus and provide reactor trip functions or safeguards initiation. The test was performed at cold shutdown conditions and therefore had no safety implications or affects on new or previously analyzed accidents. The test was completed on Unit One on 3-13-76 and Unit Two on 3-7-76. Only one relay exceeded the acceptable value of 30 msec. This relay has subsequently been replaced.

ST-42 Main Steam Trip Valve Modification Verification The purpose of this procedure was to verify that the cold closure time of the main steam trip valves was still less than the five second Technical Specification requirement after the installation of larger air cylinders per Design Change 75-41.

The test was performed at cold shutdown conditions and had no affect on any margin of safety. The test proved that the con-sequences of previously analyzed accidents would not be increa-sed since the modified valves retained closure times of less than five seconds. With the station at cold shutdown conditions no new accidents were created. The test was satisfactorily com-pleted on Unit Two on 4-24-76 (TV-MS-201B) and 5-17-76 (TV-MS-201 A,C) *

-112-

ST-43 Turbine Runback Troubleshooting

• The purpose of this test was to provide the sequence of testing necessary to troubleshoot portions of the Unit One turbine runback circuit. Since the test was performed at cold shutdown conditions which do not require the operability of the turbine runback circuit, the consequences of previously analyzed accidents were not increased, no new accidents were created, and the margin of safety was not decreased. The test identified no probl~ms with the protection rack circuitry on 4-7-76.

ST-45 Main Steam Trip Valve Rockshaft Stress Evaluation This procedure was utilized to evaluate the stresses on a main steam trip valve during Unit One power operation. The test equipment employed measured strain and vibrations in the valve rockshaft and body. This equipment did not impair the performanc.e of the trip valves and, hence, did not affect any previously analyzed accident which required use of the valves.

Neither did the test and equipment affect the margin of safety or create any new accidents. The results of the test performed on 5-26-76 indicated high strains: in the rockshaft which could be alleviated by valve modifications.

ST-46 Load Measurement for Main Steam Trip Valve The purpose of this test was to obtain field measurements of loads imposed on the main steam trip valves at cold arid oper-ating conditions after the valevs had been modified in accordance with design change 75-41. The test required the use of strain

• gauge instr1rtlllentation to monitor rockshaft performance.

-113-

ST-46 Load Mesurement for Main Steam Trip Valve (continued)

• The test setup was such that main steam trip valve performance was not affected, thereby assuring that the margin of safety was not reduced, the consequences of previously analyzed accidents were not increased, and no new accidents were created. Prelim-inary analysis of the data obtained on 7-7-76 indicated a success-ful reduction of strain in the main steam trip valve rockshaft after modification.

ST-47 Service Air Fitting Leakage This procedure was used to measure the air leakage through a sweated fitting in line 2"-ASC-CD21B downstream of 2-SA-82 at the containment boundary. A test was necessary to quantify leak-age experienced during the containment integrated lea~ rate test on Unit Two. With the station in cold shutdown conditions which do not require containment integrity, the testing imposed no re-strictions on previously analyzed accidents and did not reduce the margin of safety. Since all testing equipment was later removed no new accidents were created. The leakage rate was determined on 5-26-76. Subsequent repair of the fitting eliminated the leakage.

ST-48 Leak Check BD-TV-200E* and F The purpose of this test was to measure the air leakage through steam generator blowdown trip valves BD-TV-200E and BD-TV-200F. The test was necessary to quantify leakage experi-enced during the containment integrity leak rate test on Unit Two

• To preclude reducing the margin of safety and affecting

• any new or previously analyzed accident, the valves were tested in the cold shutdown condition.

-114-The leakage rate was established

ST-48 Leak Check BD-TV-200E and F (continued)

• ST-49 on 5-26-76 and the valves were later repaired to reduce the leakage to zero.

Leak Check Recirculati:an Spray Heat Exchanger This test procedure has been utilized on several occasions to meaure the air leakage from the recirculation spray heat exchangers on both units. Neither new or previously analyzed accidents were created or increased in probability as a result of this testing, since the units were in the cold shutdown con-dition which did not require the use of the recirculation spray system. Likewise, the margin of safety was not reduced. The procedure was utilized on the following dates on the noted heat exchanger 27-76 (lA), 11-6-76 (2D), 11-7-76 (2C), 11-7-76 (2D), 11-7-76 (lA), 11-7-76 (lB), 11-7-76 (lC) and 11-23-76 (2D).

Repairs ~s necessary were made to any heat exchanger which exhibited air leakage.

ST-50 Containment Heat Load Determination The purpose of this procedure was to collect data from station instrumentation to determine the heat load on the containment recirculation air coolers during normal full power operation. Use of existing instrumentation insured that no new accidents were created, while the nature of the test did not reduce the margin of safety or* increase the consequences of any previously analyzed accident. Data was collected on both units on 6-18-76 and Unit One only on 9-24-76 *

• ~us-

ST-51 2A Steam Generator 900 PSI Leak Test

• This procedure was used to provide the testing sequence and equipment setup to conduct a 900 psig leak test on the 2A steam generator shell following the installation of a three inch in-spection port. The test was performed at cold shutdown conditions to insure that the margin of safety was not reduced and the con-sequences of any previously analyzed accident were not increased.

Special precautions were taken to prevent the creation of any new accident. The test was successfully completed on 10-28-76 *

• -116-

OTHER CHANGES, TESTS, AND EXPERIMENTS

-117-

OTHER CHANGES, TESTS, AND EXPERIMENTS

• There were no tests, changes or experiments requiring NRC approval~

-ll8-

PERIODIC TESTS NOT COMPLETED WITHIN TIME LIMITS

• -119-

PERIODIC TESTS NOT CONPLETED WITHIN TIME LIMITS

• The following Periodic Tests (PT) required by Technical Specifications were not completed within the specified interval. In each case the PT was subsequently run satisfactorily.

PT NO. TITLE TECHNICAL SPECIFICATION PT-17.2 Containment Inside Recirculation 4.5 Spray Pump PT-19.1 RWST Chemical Addition Tank 4.5 Performance PT-22.2C Diesel No. 3 Fuel Supply 4.1 PT-23.2 Station Batteries (Due 1st quarter 4. 6-2 1976)

PT-23.2 Station Batteries (Due 2nd quarter 4. 6-,-2 1976)

PT-23.3 Station Batteries (Due 1st half 4.6-2 1976)

PT-31. 3 Seismic Instrumentation Check 4.1 (Due September, 1976)

PT-31. 3 Seismic Instrumentation Check 4.1 (Due October, 1976)

PT-38.5 Secondary Coolant Beta and Gamma 4.1 Tritium Activity

• -120-

i' CORRECTIVE MAINTENANCE

-121-

MECHANICAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO. 1 TOTAL NUMBER OF MAINTENANCE ORDERS COMPLETED 77 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

I r'

N 12-22-75 Containment Vacuum Electrical Penetratio None Installed new Electrical* NA 16 hrs.

N Penetration MR~Sl-6530 I Pump Plug Burned Out 1-6-76 Traveling Water Loose Baskets- None Tightened all baskets, inspec- NA 2 hrs.

Screens Hi-Level Bolting ted unit, MR-Sl-6648 1-CW-S-lD 1-6-76 Blowdown/Charging Pump Erosion None Renewed section of pipe 811 NA 18 hts, Service Water Piping WBTB-2-151 MR-Sl-6023 & 4801 1-9-76 EHC Syst 7m Pump Broken Vane None Renewed pump MR-Sl-6618 NA 5 days*

1-13-76 Primary Grade Water Mechanical Seal None Rebuilt mechanical seal NA 4 hrs.

Pump 1-PG-P-lB MR-Sl-6317 1-14-76 Traveling Water Screens None - Preventative None Tightened all baskets, inspect- NA 13 hrs.

Lo-Level 1 & 2-CW-S-lA ed all units. MR-Sl-6673 B,C,D, 1-15-76 Traveling Wa~er Screens None - Preventative None Tightened all baskets, inspect- NA 15 hrs.

Hi-Level 1 & 2 CW-S-lA ed units, replaced (1) basket B,C,D, on 2C MR-Sl-6676 1-15-76 Gaseous Waste Valves Diaphragm None --- Inspected FCV-GW-104B, renewed NA 9 hrs.

l-GW-104B, l-GW-5 diaphragm on l-GW-5 MR-Sl-6684 1-24-76 Vacuum Priming Pump Erosion None Installed new heat exchanger NA *20 hrs.

Heat Exchanger on MR-Sl-5154 1-VS-P-lC

MECHANICAL HAINTENANCE MONT!ll.Y OPERATING REPORT UNIT NO, 1 PAGE 2 JANU,\RY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd On Safe Operation ... To Prevent Repetition Safety Du~ing Repair Involved Malfunction For Maint.

Diaphragm None Installed new diaphragm & NA 2 hrs, 1-26-76* Chemical & Volume Control Valve Bonnet MR-Sl-6354 1-CH-88 Chemical & Volume Diaphragm None Renewed Diaphragm NA 1 hr,*

1-26-76*

Control Valve MR-Sl-6756 i-CH-106 C I Bearing None Renewed bearings and mechanical NA 7 bra.

...... 1-27-76* Boric Acid Transfer seal ~-Sl-6755 N Pump 1-CH-P-2A

~ Vanes Bearings None Rebuilt Pump MR-Sl-E789 NA 5 hrs.

1-29-76* Containment Vacuum &

Pump - Spare 1-29-76* Boron Recovery Pump *Mecham.cal Seal None Renewed mechani.cal seal NA 14 hrs, 1-BR-P-6A UR-Sl-6786

.. dS: ;f.,;_,,

~ D, S. TAYLOR- S lJPERVISOR MECHANICAL MAU rENANCE

MECHANICAL MAINTENANCE MONTHLY .Ol'ERATING REPORT UNIT NO. .1 FEBRUARY 1 . 1976 ..

TOTAL NUMBER OF MAINTENANCE ORDERS COMPLETED 78 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

I I-'

N l-15-76' Component Cooling None - Preventative None .,,

Performed Annual Preventative* NA 26 hrs.

.i:-- Pump 1-CC-P-IB Maintenance MR-Sl-6689 1

2-3-76* Gaseous Waste Va.Ive Worn - Parts None Rebuilt Valve MR-Sl-6838 NA 1 hr.

PCV-GW-107 2-6-76 Traveling Water Screen drive motor None ,Renewed three (3) baskets NA 10 hrs.

Screens - Lo Level control switch found MR-Sl-6877 1-cw-s-lA in off position caus~  ;,

ing High Delta P., -

2-9-76 Travelfng Watei: None -.Preventative None Tightened all screen baskets NA 7 hrs~

Screens Hi & Lo Level ,. ' and renewed inserts ':Att~si-6904 1 & 2 ~CW-S-lA,B,C,D  :,

2-12-76 Main Condenser Water Erosion - 31 leaking None 1lugged 31 tubes HR-Sl-6916 NA 3 hrs.

Box 1-CN-SC-lA tubes .

2-14-16 Main Condenser Water Erosion - 3 leaking None Plugged 3 tubes . MR-:Sl-6930 NA 2 hrs.

Box 1-CN-SC-lA tubes 2-16-76 Traveling Water Chain.broken by bind- None *1. Renewed 2 links of chain and HA 13 hrs, Screens Lo Level .

1-cw-s-lD ing baskets 3 baskets !IR-Sl-6943 l :.

. 3 hrs.

2-19-76 Main Condenser Water Erosion-2 leaking None Plugged 2 tubes HR-Sl-6989 NA Box 1-CN-SC-lD tubes 2-19-76. Main Condenser Water Erosion*- 2 leaking None Plugged 2 tubes MR-Sl-6990* NA Box 1-CN-SC-lB tubes ... ..,,,~. ., .... 2 hrs.

HECHA?UCAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO. 1 PAGE 2 FEBRUARY . ],976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Ti.me Req'd On Safe Operation ... To Prevent Repetition Safety Du~ing Repair

.Involved Malfunction For !-taint

• 2-22-76 Main Condenser Water Erosion - None Tested with sound equipment. NA 2 hrs,

• Box 1-CN-SC-lC Plugged 217 tubes and 89 one end only, due to lack of plugs will plug other end later.

MR-Sl-7009 I

I-'

N V,

I

d. n.s-;

~/_, TAYLOR - SUPERVISOR MF.cHANICAL MAINTENANCE .

l

--; I

~ .'*

!mCHANICAL MAINTENANCE (Other Safety !telated Systel!IS and lfajor !ter.as)

UNIT IJl FEBRUARY & MARCH 1 1976 PAGE 1 of 1 I

-Syste::? :>r Co?:1pone11t Results and Effect Precautions Taken for Time Required

.:.::I! Involved Cause of the Ifalfunction on Safe Operation Corrective Action Taken Reactor Safety ior Maint, I . I N i 0\-

I 2-24-76! Charging Pmnp Service None - Preventative None Renewed *piping with 90-10 Cu-Ni, N/A 16 hrs, I Water to Lube Oil MR-Sl-7015 I

i Coolers *. 1-CH-P-lA I

3-3-76 I Gaseous Waste Compresso None - Investigative None Disassembled compressor and checked N/A 24 hrs, I GW-C-2B for wear, found ,no wear, Inst. Tech, I

i Operations and Mechanics resolved I problem with valves. MR-Sl-6481 I

3- Charging Pump Service None - Preventative None Renewed piping with 90-10 Cu-Ni. N/A 16 bra.

l~-7, Water to Lube Oil MR-Sl-7047 Coolers. 1-CH-P-lB I

I I

I I

I I

I I

HRCIIAllICAL HAI?rrnNANCE (Safety Related Systems during Outage or Reduced Power P.eriods.)

UNIT NO. 1 1 of 3 TOTAL NUMBER OF MAINTENANCE ORDERS COMPLETED 200 . . .-~1- :.

Syste.~ or Component Results and Effect Precautions Taken for Time Required* ...

In\'olved Cause of the lfalfunction on Safe Operation Corrective Action Taken Reactor Safety for }faint.

• I i I I-' I N3-14-71 Main Steam Non-Return Severe erosion of valve None Renewed bonnet. stem & seal ring. Cold Shutdown 32 hrs.

-..J I Valve NRV-MS-lOlA stem & bonnet gland* MR-Sl-6564 I area - Normal wear 3-14-7J Containment Inst. Air Piston rings & valves None Renewed piston rings & valves. Cold Shutdown 24 hrs.

I MR-Sl-7137 Compressors l-1A-C-2B normal wear II 3-14-76 Boron Recovery Bottom Boron in pump motor None Renewed pump. MR-Sl-7187 Cold Shutdown 3 hrs.

Taajc~ l-BR-P-9 .' windings-Bearings 3-14-7~ Safety Injection Lifting early - valve None Disassembeled 1 cleaned 1 reassembeled and Cold Shutdown 9 hrs.

- I System Relief Valve seat-needed cleaning. tested.valve. MR-Sl-7179 RV-1857 I

3-14-7~ Charging Pump Service Erosion of Carbon Steel None Repiped with.90-10 Cu.-Ni. MR-Sl-7107 Col4 Shutdown 16 hril.

I Water to Lube Oil piping.

I Coolers. l-CH-E-5C 3-15-71 Steam Generator Tube Leak None Westinghouse Explosive plugged 24 tubes. Cold Shutdown 3-1/3 d~ys 1-RC-E-lA Mlt-Sl-7073 3-15-7, Cont. Inst. Air Piston rings & valves- None .. Renewed piston rings & valves. Cold Shutdown 3-1/.2 hrs.

Compressor l-1A-C-2A Normal wear. MR-Sl-7135 3-15-76 Reactor Coolant System Paclq.ng - Normal use None Repacked with Graphoil packing. Cold.Shutdown 3 hrs.

I I

l-RC-138 MR-Sl-.7198 3-16-7~ Gaseous Drains Valve Diaphragm - Normal None Renewed Diaphragm. MR-Sl-7205 Cold Shutdown 6 hrs~ .*,

i l-DG-14 . '

\

I , .

MECIIA?tICAL HAIHTENANCE (Safety Related Systems during Outage or Reduced Power Periods.)

UNIT Ill -: ..~, . (

. {:

,

:t::. /

PAGE 2 of 3 _,\'... ff.*:

-=**=============:;::::===========:;:::::;:======:=;::==================::;::::::===========::;:=====~

i s~*stell'. or Cor.iponcnt Results and Effect Precautions Taken for Time Required;°;\

1

. .--~  ! Involved Cause of the lfnlfunction on Safe Operation Corrective Action.Taken Reactor Safety for }faint.*:*:,

1 Chemical & Volume Gaskets - Cyclic None Renewed cage & bonnet gaskets, Cold Shutdown 7 hrs. ::

~16-71 Control Valves MR-Sl-7208 LCV-1460 A & B -* :

3-16-7 Chemical & Volume Gasket - Cyclic None Renewed bonnet gasket. MR-Sl-7210 Cold Shutdown 4-1/2 hrs.

I Control Valve I HCV-1200C 3-16-7~ Reactor Coolant Valve Gasket*- Cyclic None Renewed bonnet gaskets & repacked valve. Cold Shutdown 2 hrs~ .,

i 1-RC-95 MR-Sl-7211 i

3-16-'7~ Reactor Coolant Valve Packing*- Normal use None Repacked with Graphoil packing. Cold Shutdown 5 hrs.

l-RC-90 MR-Sl-7212 I

3-16-7~ Reactor Coolant Valve Packing - Normal use None Repacked witn*Graphoil packing. Cold Shutdown 4-1/2 hrs.

l-RC-58 MR-Sl-7214 3- 16-71 Reactor Coolant Valve Diaphragm None Removed nitrogen regulator and hard Cold .Shutdown 3 hrs.

PCV-1473 piped system. MR-Sl-7217 3-16-71 Pressurizer Line Loose fittings None Tightened fitting & filled with oil. Cold Shutdown 4 hrs *.

Hydraulic Snubbers MR-Sl-7219 I

3-16-76 Chemical & Volume Packing - Normal use None Repacked valve. MR-Sl-7220 Cold Shutdown 6-1/2" hrs~

! Control Valve l-CH-365 i

3-16-7~ Reactor Coolant Valve Packing - Normal* use None Repacked valve. MR-Si-7221 Cold Shutdown

• 6-1/2 hrs.*

., l-RC-17

~

I

HECUAHICAL HADITENANCB (Safety Related Systems durinn Outage or Reduced Power ~eriods.)

UNIT ,h PAGE 3 of 3 I.

System or Component Involved Results and Effect Cause of the Ualfunction on Safe Operation Precautions Taken for Reactor Safety Time Required * .

f-' --C~

- Corrective Action Taken for }!aint.

N""""

I.O I

• 1 3-16-761 Reactor Coolant Valve Valve internals needed None Cleaned valve internals. MR-Sl-7224 Cold Shutdown 3 hrs.

HCV-1549 cleaning .

3-16-76 Bergen-Patterson None - Preventative None Inspected snubbers - no deficencies Cold Shutdown 2 hrs.

Hydraulic Snubbers MR-Sl-7234 3-17-761 Residual Heat Valve. Boron eroding the bonnet None Renewed bonnet. to limitorque extens~on Cold Shutdown 9 hrs.

I MOV-1700 to limitorque spacer spacer. MR.-Sl-7233 3-17-76! Reactor Coolant Valve Gaskets - Cyclic None Renewed all gaskets in A & B. r.enewed Cold Shutdown 12 hrs.

i PCV-1455 A & B cage stem & bellows in A. MR-Sl-7209 I

i Lr~/'-1-,,

D.S. TAYLOR 1 SUPERVISOR - MECHANICAL MAIN ll'ENANCE r

iI

'I

-, i

.1 ! .,; ..

MKCIWIICAL HAIJITENAHCB (Safety Related Systems durinn Outane or Reducet Power P~riods.)

UNIT 01.

APRIL 1 1976 PAGE 1 of"l ..R. COHPLETED

• NUMBER OF M 192 System or Component Results ond Effect Precautions Taken for Time Required nnta tnvolvcd Cnuno ot tho Uul£unct:lon on nu.re OpOL't1Hon corrective Action Token ltooctor Safety for Maint.

4-1-76 Residual Heat* Gasket N.one Renewed Gland Seal Gasket Cold Shutdown 2 HRS.

....I w Pump 1-RH-P-lA MR-Sl-7264 .

0 I 4-2-76 Steam Generator Tube Leak None Explosively plugged h2 tubes, Cold Shutdown 16*BRS, RC-E-lC MR-Sl-7374 4-2-76 Reactor Coolant Bellows None Renewed internals reset to 600 psi. Cold Shutdown 20 HRS, Relie'f Valve RV-1203 MR-Sl-7276

.',t.l.J~/../

D, S, TAYLOR, SUPERVISOR MECHAN IAL MAINTENANCE '

. *w: I

MEC!IA?lICAL HAI?lTENANCE (Safety Related Systems during Outage or Reduced Power P.eriods,)

UNIT 1 Page 1 of 1 MAY 1976 TOTAL NUMBER OF M R WORKED 118

..:te srstem or Component Involved Results and Effect Cause of the Ualfunction on Safe Operation

• Precautions Taken for Reactor Safety Time Required.{'-!

for Maint-;*:,:*:;

Corrective Action Taken I

t:;s- 2-76 TV-MS-lOlA,B,C, Main Actuator pins not makin1 None Fabricated and installed new pins, Cold Shutdown 6 hrs, 1-' Steam Trip Valves contact,

_I: MR-Sl-12183 ,

'. 5- 2-76 1-VS-F-lB Containment Blading sheared from None Installed blade & hub assembly. Cold Shutdown 7 hrs.

I Recirc. Fan. hub - exact cause undetermined, MR-Sl-12179 II I

I i

i 1

I i

I i . .

' ' ~. ': ~ .. ' ,- . !

HECIWlICAL MAllffENAHCB (Other Safety ~elated Systems and }fajor Itel!ls)

.!!fil!...!

PAGE l of 2 MAY, 1976 TOTAL HUMBER OF M.R. COMPLETED 118 1 .System or Co!:\ponent Results and Effect Precautions Taken for. Time Requited

.. ~~ i Im*olved Cause of the Halfunction on Safe Operation Reactor Safety Corrective Action Taken for Maine.

I I-' I

~ 29-76 CH-P-2C Boric Acid Mechanical Seal Normal- None Renewed mechanical seal.MR-Sl-7351 NA 6 hrs, I Xfer Pump wear 4-14-76 l-BR-E-9 Piping Pin Hole Leak on Pipe None Pad ,.welded line. MR-Sl-7535 NA l hr, 4- 27-76 1-CN-SC-lC Main 2 existing plugs loose Hone Renewed Plugs MR-Sl-12062 NA 3 hrs, Condenser Waterbox

• s- 3-76 1-CN-SC-lB Main Tube Leak - Erosion None Plugged (1) Tube MR-Sl-12188 NA 2 hrs, Condenser Waterbox 5- 3-76 I 1-CN-SC-lC Main Tube Leak - Erosion None Plugged (3) Tubes MR-Sl-12198 NA 3 hrs, I

Condenser Waterbox 5-5-76 l-BD-5 Blowdown Valve Gasket - Cyclic None Renewed Gasket, MR-Sl-12409  :

NA 4 hrs, 5-9-76 Ill Emer. Diesel #1 Cylinder Head cracked None Renewed ill cylinder NA 10 hrs, from overheating 5-10-76 1-cN-SC-lB Main Tube leak - Erosion None Plugged (1) Tube MR-Sl-12438 NA 3 hrs,.

Condenser Waterbox 5-12-761 1-cs-sc-lA Main Tube leak - Erosion None Plugged (1) Tube MR-Sl-12452 NA 3 hrs, Condenser Waterbox 5-14-761 l-1A-C-2B Containment Valves & Piston rings None Rebuilt the compressor, MR-Sl-12447 NA 2 days I Inst, Air Compressor

• I. .

!mCIWtICAL MAINTENAUCE (Other Safety !lelat_ed Systems and Major Itel!ls)

.!!!fil'...!

HAY 1 1976 PAGE 2 of 2

.*. :a I

! Syste~ or Co~ponent Involved Results and Effect Cause of -the U.nlfunction on Safe Operation Precautions Taken for -

Time Required Corrective Action Taken Reactor Safety for :Maine.

15-76! 1-CN-SC-lB Main Tube leak - Erosion None Plugged (1) Tube, !fil-Sl-12463 NA 3 .hrs,

! Condenser Waterbox 5- 26-76 iI 1-SW-P-lB Emergency None - Preventative None Performed Preventative Maintenance check NA 30 hrs.

Service Water Pump I'

I 1 -

I  :

drL/-~>

D. S, TAYLOR'- SUPERVISOR, MECIWIJ;CAL : l!AINTENAHCE I. . -.~.. *.

• MONTllLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE

. UNIT ill

• JUNE, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 102

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 14 MONTHLY TOTAL *116

3. DESIGN CHANGES BEING WORKED 76-7, 74~68,74

4. PERIODIC TEST PERFORMED 0 I SUPERVISOR

MECHANICAL MAINTENANCE (Other Safety Related Systems an,d Major Items)

UlUT ill JUNE, 1976 lPAGE 1 of 2 System or CiJmponent Results and Effect Precautions Taken for Time Requir Date Involved Cause of the Malfunction on Safe nneration Corrective Action Taken Reactor Safetv for Maine I

t; :4-2-76 1-DG-P-lB Primary Drains Bearings failed,allowed Mone Rebuilt Pump. HR-Sl-7239 IIA 1 17 hrs.

y, r Transfer Pump rotor to penetrate stator

~-18-76 Number (1) Emergency Cracked head. Hone Renewed head, liner, piston assy. NA 2 days Diesel on 017 cylinder, renewed rod rings I and seals on 017 cylinder. : Checked crankshaft deflection. HR-Sl-12023 4-26-76 1~1A-C-2B Containment Valves None Renewed suction and discharge NA 6 hrs.

Instrument Air Compresso1 valves. MR-Sl-7512 J4-28-76 l-1A-C-2A Containment Valves None Renewed suction and discharge NA 6 hrs *.

I l Instrument Air Compresso1 valves and hyraulic unloader.

l MR-Sl-12072 I

4-30-76 1-cH-169 & 194 eves Diaphragm Hone Renewed Daiphragms.  !-fil-Sl-12148

• NA 8 hrs.

System I

I l

4-30-76 5-1-76 8-WBTD-21-151 Steam Generator Blowdown Piping Erosion l-1A-C-2A & B Containmen1 Valves & Piston rings Instrument Air Compresso1 None None Implemented Design Change 76-7 MR-Sl-12055 .

Renewed suction & Discharge valves, piston rings. HR-Sl-12034 NA NA 16 hrs.

2 days j 5-26-76 t,iitrogen System Hone-Design Change 74-68 Uone Implemented Design Change 74-68. NA 24 hrs.

MR-Sl-12520 I

ME~CAL HAIHmWfCE

. (Other:Safety Ralat~ Systems and Major Items)

UNIT IJl JUNE, 1976

!PAGE 2 of 2 System or Component Results and Effect Precautions Taken for Time Requit

_ Date Involved Cause of the Malfunction on Safe Oueration Corrective Action Taken Reactor Safetv . for Mainl I

I-' I w r-27-76 Riv~r Circ, Water Pump Bearings Hone Reworked p.ump, MR-Sl-12439 NA 17 days

-"'I 1-CW-P-lD 6-11-76 Ul Emergency Diesel Hone-Preventative Hone Tested for cracked heads - found NA 4 days i 3 cracked, Added chromates,

! MR-Sl-12492 & 12485 r-15-76* 1-CS-P-lB Containment Vanes Hone Installed rebuilt pump and overhauled HA 6 hrs, Vacuum Pump spare pump, llR-Sl-12617 & 12627 l-16-76 l-FCV-GW-104B Worn parts - normal use, None Renewed seat ring, stem, packing and HA 8 hrs.

gaskets, MR-Sl-6919 Ll6-76 Containment Vacuum Vanes None Rebuilt spare pump, MR-Sl-12626 & NA 6 bra, Pump - Spares llR-12628 Nitrogen Truck Supply None-Preventative Hone Installed Design Change 74-68 NA ~4 bra~

MR-Sl-12620 r21-76 D, S, TAYLOR - SUPERVISOR, MECW UCAL MAIN'lElWiCE

• MON'rllJ.,Y Ol'EltATINC SU11PLmmNT SIIRE'l' i-mctlANICAL MAINTENANCE UNIT* No. 1 JULY, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 147

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 23 MONTHLY TOTAL 170

• \

. 3. DESIGN CHANGES BEL'iG WORKED - - - - - - - - - - - - - - - - - - - - - - - - - - -

I f-'

w "I 0

4. PERIODIC. TEST PERFORMED

. MECHANICAL. SUPERVISOR I

'f'

. **: (.~

........' 1 HBCIWl'ICAL HAI?ITBNANCE (Safety Related Systems*durin~ Outage or Reduced Power P.eriods.)*

UNIT NO. 1 JULY, 1976 )

1°' 1 of 1 .. . ., **~/:JJ"

h l==~===========

;===========::;:;::;::;::=:::;:::::;:;::=:;:==================~==~:::::;::;:=:==:;:=====:::;

System or Component Results and Effect Preca*utions Talten for 'Time Required 1

! I Date Involved Cause of ~he Halfunction on Safe Operation Corrective Action Tak~n Reactor Safety for Maint.*'

/

dj

~7-19-76 Steam Generator Tube Leak None Plugged (1) leaking tube and (21) Cold Shutdown 2 days 1-RC-E-lC tubes as preventative measure.

J' 1 MR-Sl-128.52

()17-19-76

• Steam Generator Tube Leak None Plugged (1) Tube eac~ generator. Cold Shutdown 2 days 1-RC-E-lA & B tm-s1-12as6 & 12839

! 1

1 '-;7-19-76 Pressurizer Relief Rupture Disc ?lone Renewed rupture disc. MR-Sl-12738 Cold Shutdown 12 hrs.

f Tank*

• t 7-19-761 Letdown Relief Valve. Yalve destroyed ?fone Rebuilt, tested and reinstalled.valv~. Cold Shutdown 10 hrs.

t-,. 1-RV-1203

• internally by MR-Sl-22477

~

' continual reliev-

• I ing.

i1

' .i7-20-76,

.; I Hydraulic suppressors None-Preventative None Inspected Bergen-Patterson Snubbers no deficiencies. MR-Sl-12733 co'1d Shutdown 6 hrs.

I\ *J17-20-76 Reactor Coolant Pump Standpipe alarm- None Inspected all 3 seals-found no indica- Coid Shutd~ 4 days

! j.

. .i

..,I 1-RC-P-lA could find no problems with pump seals to tions of problem area. Renewed 02 seal as a preventative measure

• Details in .R Trip Report. MR-51-12555 cause this con-dition *.

17-20-76 Containment Instrument Normal wear None. Renewed valves & rings - each . Cold Shutdown 3 days I Air Compressors compressor.* ?fR-Sl-12734 & 1 127.3:;

l-1A-C-:-2A & B I

.... I , ..... '"*.. *- *'

ME~ICAL MAINTENANCE (Other:Safety Related Systems and Major Items)

UNIT NO. 1 JULY, 1976 1 of 2 System or Component. Results and Effect Precautions Taken for Time Requir.

Date Involved Cause of the Malfunction on Safe Ooeration Corrective Action Taken Reactor Safetv for ~faint i

1-76 Component Cooling Bent Shaft None Rebuilt pumps. MR-Sl-12076 NA 3 days Radiation Monitoring Pumps l-SW-P-6B & C 7-:2-76 Emergency Diesel Cracked head - prev- Noue Renewed 019 cylinder head. NA 10 hrs.

1-EM-G-1 ious overheating of MR-Sl-12759 engine. I i t, ...

~

7-76 Main Condenser Waterbox Erosion None Plugged (1) Tube. MR-Sl-12789 NA 3-1/2 hrs.

1-CN-SC-lB 14-76 Reactor Coolant Filter High Delta-P-Normal None Changed filters. MR-Sl-6419 NA 20 hrs.

- l-CH-FL-2 14-76 Chemical & Volume Control Valve l-CH-192 Valve stem . None Renewed bonnet assembly. MR-Sl-12166 NA 6 hrs.

15-76 Spent Fuel Pit Filter High Delta-P-Normal None Changed filters. MR-Sl-5505 NA 20 hrs.

l-FC-FL-2 16-76 Reactor Coolant Letdown High Delta-P-Normal None Changed filters. MR-Sl-12562 NA 10 hrs.

Filter l-CH-FL-5 i- 17-76 Seal Water Injection High Delta-P-Normal* None Changed filters. MR-Sl-1251:?. NA 10.hrs.

i !Filter l-CH-FL-4A I:

i1 18-76 . Boric Acid Filter *.

1-CH-FL-1

• High Delta-P-Normal Non,e Changed filters. MR-Sll558 NA 10 hrs

• 7- 20-76 Main Condenser 11-CN-SC-lD Waterboxe1 Erosion None Pluggal, (1) tube. MR-Sl-12896 NA 4 hrs.

1

• I I . .'

, , \\

,. ,, I MECHANICAL MAINTENANCE

. : (Other~Safety Related Systems and Major Itelll/ll)

UNIT No: 1 JULY, 1976 ii of 2.

System or Component Results and Effect Precautions Taken for "rime Requit I

1_ Date Involved Cause of the Malfunction on Safe Operation Corrective Action Taken Reactor Safety for Maint I 7~22-76 Main Condenser Water- Erosion None Plugged (1) Tube in A waterbox, NA 6 hrs, I-' '*

~ i boxes, 1-CN-SC-lA &*B MR-Sl-12926 0 *"-

, l ~23-76 Ii..

Emergency Diesel Cracked head - None Renewed #7 cylinder head, MR-Sl-12949 NA 12 hrs,

~. i 1.:.EM-~l previous overheating

! of engine, i

7r24-76 Containment Instrument *Piston rings 'None .Renewed HP & LP Piston rings, NA 10 hrs, Air Compressor MR-Sl-12953 1-1A-C-2A&B ,,

i

~ 24.:.76 Main Condenser Water- Erosion None Plugged (1) Tube, MR-Sl-12956 NA 4 hrs, i: box 1-CN-SC-lC 27-76 Containment Instrument Rings and valves None Renewed piston rings & valves, ,.

NA 10 hrs.

Air Compressor MR-Sl-12977 1-1A-C-2B '

f . 76 Boron Recovery Valve Stem sheared- None Renewed.bonnet and diaphragm NA 4 hE'.8*

r* 1-BR-206 diaphragm ruptured, MR-Sl-12931

'l J J t- .-t D, S, TAYLOR - SUPERVISOR, MECHANICAL MAINTENANCE

l

• MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE UNI.T NO. 1 AUGUST, 1976

. . .1. MAINTENANCE .ORDERS COMPLETED :NON~SAEETY ~RELATED* ,ITEMS

. *.2. . MAINTENANCE ORDERS COMPLETED MAJOR :OR* SAFETY RELA'TED ITEMS 13 MONTHLY TOTAL 157'

3. DESIGN CHANGES BEING WORKED *nc-75-36, DC-75-55. DC-76~2

4. PERIODIC TESTS PERFORMED PT-41 MECHANICAL MAINTENANCE SUPERVISOR

HECllAUICAL HAIN'rENANCE*

(Safety Related Systel!ls durin3 Outace or ~educecl Power Periods.)

UNIT HO. 1 AUGUST, 1976 PAGE 1 of 1

• Syste.~ or C01:1ponent Results and Effect l'Tecautions Taken for Time Required Involved Cause of the !!al.function on Safe Operation Corrective Action Taken Reactor Safety for :l-!aint.

I I

-~ 8-15-76 Reactor Coolant Valve Packing None Repacked valve on backseat. MR-Sl-12904 Cold Shutdown 4 hrs.

N l-RC-77 I

8-16-76 Chemical & Volume Packing None Repacked valve. HR-Sl-12903 Cold Shutdown 4 hrs.

Control System l-cH-314 8-16-761 Residual Heat Valve Packing - Preventative None Repacked valve, llR-Sl..;12929 Cold Shutdown 4 hrs.

I MOV-1700 8-17-76! Steam Generator None - Preventative None Hydrostatic test .of generator-no leaks. Cold Shutdown 3 days I 1-RC-E-lA MR-Sl-13095 i

8-17-761 Steam Generator Tube Leak Hone Plugged (1) Tube. llR-Sl-13096 Cold ShutdOIZll 3 days I 1-RC-E~lB I

3-17-7f Steam Generator Tube Leak None Plugged (1) Tube. ?IR-Sl-13097 Cold Shutdown 3 days 1-RC-E-lC 8-17-71 Containment Instrument Rings - Valves None RebLilt compressor. ?m-Sl-13144 Cold'Shutdown 14 hrs *.

Air Compressor.

l-lA-C-2B .'

I I

I .

8-17-76 vl Emergency Diesel None - Preventative None Replaced i/3,4,5,6,9,9 & 10 cylinder heads. Cold Shutdown 4 days ttR-Sl-13063 Chemicai &Volume Diaphragm - Grinnell None Renewed diaphragm, MR-Sl-13020 Ho.t Shutdown 35 mins.

Control System, l-CH-125

MECHANICAL MAINTENAHCB .

(Other Safety Related Systems and Major Items)

UNIT NO. 1 AUGUST 1 1976 PAGE 1 of 1 System or Component Results and Effect Precautions Tak.en for Tiae Required Involved on Safe Operation Corrective Action Taken Reactor Safetv for Maint. ..

Date Cause of the Malfunction 7E Containment Instrument Valves & piston rings None B.ebuilt & installed spare compressor. NA . 2 days Air Compressor MR-Sl-12939 l-1A-C-2B

• S:=5-:-ZE Main Condenser Water- Erosion None Plugged (1) Tube. MR-Sl-13038 NA S hrs

• box. 1-CN-SC-lB 8-12-] 6 Instrument Air Com- Valves & piston rings Hone Rebuilt compressor. MR-Sl-13050

• NA 3 days pressor. 1-lA-C-1 8-18-7 Ii Uain Condenser Water- Erosion None Plugged (1) Tube "C" Waterbox. NA 8 hrs.

boxes. 1-CN-SC-lA, MR-Sl-13159 B, C & D.

I 1!~~ -~ s. ~ l"t../

D. S. TAYLOR - : UPERVISOR, MECHANICAL MAIHTENJ NCE

• MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE IDUT Ill

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 123

2. . MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS

• 44 MO?ITHLY TOTAL 167

3. **

• DESIGN CHANGES BEING WORKED DC-75-51. Low Head Safety Injection Pre-fab.

DC-75-36, Boron Recovery Modification.

4. PERIODIC TESTS PERFORMED

~ 71,;i-,

MECHANI~ MAINTENANCE SUPERVISOR

UNIT NO. 1 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS)

PAGE 1 of 2 SEPTE!IBER. 1976 DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ I D INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAU,'T.

~*=---;-~~=--c;-=~-~~~~+==~==+-----.;;.:.;;.;,;;...;;;.;,;;.;;;;;,~;:;:;_-4,,.,.:;;;;;,..:;;:;,;,;~~;;.;...-1=--~==~.

9-24-76 Chemical/Volume Control Cloggecl filter - Uormal Uone Renewed filter element. MR-Sl-12561 NA 5 hrs.

System Filter 1-CH-FL-4B use 9-26-76 Containment Vacuum Gasket - Cyclic Hone Renewed gasket. UR-Sl-13432 NA 6 hrs.

System Valve l-UCV-1310A I

...... Hone Renewed gasket. MR-Sl-13435 NA 6 hrs.

.I:' 9-1.7-76 Safety Injection System Gasket - Cyclic V,

I Valve, l-HCV-1898 9-1.7-76 Chemical/VolUIJle Control Uiaphragrn - Cyclic None Renewed diaphragm. MR-Sl-13735 NA 2 hrs.

System Valve l-CH-416 9-28-76 Safety Injection System Gasket, seal - Cyclic ?lone Renewed gasket & seal. m\-Sl-13436 NA 8 hrs.

Valve. l-UCV-1936 9-28-76 Reactor Coolant System Possible tube leak ?lone Found no leak, renewed manway gasket. NA 6 days Steam Gen, 1-RC-E-lB Noue MR-Sl-13737 Found no leak, renewed manway gasket,

. NA 6 days 9-1.8-76 Reactor Coolant System Possible tube leak Steam Gen, 1-RC-E-lA lffi.-Sl-13736 Chemical/Volume Control Seat, disc~ Normal wear None Renewed complete valve. MR-Sl-13261 NA 10 hrs.

9-28-76 System Valve l-Cll-RV-1203 llone:; Renewed air line. MR-Sl-13379 NA . :l hrs.

9-29-76 Containment. Vacuum . . . .Air line - llormal wear System Valve 1-LCV-1460B Safety Injection System Uiaphrab'l!I - Cyclic Hone Renewed diaphragm. HR-Sl-13434 NA 2 hrs.

9-29-76 Valve, l-HCV-1549 9-29-76 Containment Vacuum Air line - Normal uear None Renewed air line, .. MR-Sl-13351 ,IA 2 hrs.

System Valve l-llCV-1200ll

UNIT NO, 1.

MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PAGJ,. 2 of 2 SEPTEMBER, 1976 II DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D I

I INVOLVED CAUSE OF THE l.fALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR* SAFETY FOR MAINT, II I

9-29-76 Reactor Coolant System Valve. l-PCV-1455A Packing - Normal wear Hone Renewed packing, MR-Sl-13299 NA 3 hrs, None Renewed diaphragm, UR-Sl-13433 NA 4 hrs, l 9-29-76 Safety Injection System Valve l-llCV-1550 Diaphragm - Cyclic

~ 9-29-76 Reactor Coolant Steam Gen, 1-RC-E-lC Tube - Erosion None Plugged (1) tube. llR-Sl-1-734 NA 6 days P'

., 9-29-76 Reactor Coolant System Rupture disc gasket - None Renewed .(1) rupture disc & gasket, NA 20 hrs, Tank l-RC-TK-2 Cyclic . MR-:-Sl-13300 9-30-76 Containment Instrument Piston rings - Normal None .Renewed piston rings. MR-Sl-13714 RA 20 hrs, Air Compressors uear l-IA-C-2A,B, j

!I I

I

~

• • ~.

. ,1**

U?JIT ?10. 1 MECHANICAL MAINTENANCE (OTHER SAFETY, RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 SEPTEl.ffiER, 1976 SYSTEM OR COMPONENT RESULTS AND-EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE :A"CTION TAKEN FOR REACTOR SAFETY FOR MAINT.

9::-.3-76 Containment Instrumert Rings an~ valyes none Renewed piston rings, valves and NA 10 hrs.

Air Compressors gaskets. , l-lR-Sl-13312 1-1A-C-2A,B 9-7-76 ?lain Condenser Water- Tube leak - Erosion ?tone Plugged (1) tube. l*fil-Sl-13376 NA 4 hrs.

box 1-C,~-SC-lD I

t'. 9-9-76* Boron Recovery Steam *1 Tube- Leak , 10A None Plugged (1) tube, MR-Sl-13309 NA 4 days

-..J Feed Heaters **

I 1-BR-E-lOA,B, 9-10-76 Chemical & Volume Grinnel <liaphragr.i valve - Uone Renewed diaphra,gia. HR-Sl-13403 NA 2 hrs.

Control System valve Diaphragm l-CH-29 9-12-76 Traveling Water Screem Baskets & chain Uone Renewed 4 baskets & 3 links of chain. 10 hrs.

Lo-Level. 1-CW-S-lll MR-Sl-13409 9-15-76 Chemical &"VolUIJle Grinnell diaphra8111 valve- None Renewed diaphragI'I. MR-Sl-12505 NA 2 hrs.

Control System Valve Diaphragm l-OH-132 9-10-76 Main Condenser Water- Tube Lenk - Erosion Hone Plugged (1) tube. MR-Sl-13457 NA 4 hrs.

box 9-27-76 Circ, Water System llire botto1.1 torn 011 six llone Renewed 6 baskets. MR-Sl-13719 NA 10 hrs.

Traveling Screens (6) baskets.

1-CW-S-lC 9-28-76 Heating Steam Boiler Leaking tubes - Uormal !lone Rolled 60 floor tubes & renewed NA 00 hrs.

"B" Boiler wear. gaskets. lfil-Sl-12713 D. S, TAYLOR - SUPERVISOR, MECHANICAi MAIN~ENANCE

UNIT 1 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS),

Page 1 of 3 OCTOBER, 1976 SYSTEM OR COMPONENT RESULTS A.~D EFFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

10-2()-76 Circulating Water High Delta-P None Repaired or replaced 18 baskets. Cold Shut4own 20 hrs.

1-Cw-S-lG and 1D MR-Sl-13780 10-23-76 }lain Steam !!SR A-B-C-D Tube Leaks None Tested for leaks, found none. Cold Shutdown 3 days MR-Sl-114084 10-24-76 Safety Injection Valve plugged. None Unclogged valve. MR-Sl-13940 Cold Shutdown 6 hrs.

l-SI-171 10-24-76 Reactor Coolant Packing leaks None Tightened Packing. MR-Sl-13901 Cold Shutdown 2 hrs.

dOV 1535 & 1536 10-24-76 Safety Injection Valves. Packing leaks None Repacked 1SI4-10, 12 & 77. Adjusted Cold Shutdown 6 hrs.

1-SI71. MR-Sl-13944 10-25-7ti Feedwater HOV-F~-151C Bouy to bonnet leak None Replaced bonnet gasket. MR-Sl-13920 Cold Shutdown 6 hrs.

10-25-76 Feedwater HOV-FW-151E Packing leak None Repacked valve. MR-Sl-13919 Cold Shutdown 4 hrs.

10-25-76

• eves 1-cH-166 Donnet leak None Replaced diaphragm. UR-Sl-13864 ,Cold Shutdown 1 hr **

Grinnell 10-25-76 eves 1-ca-314 Packing leak None Repacked valve. l!R-Sl-13910 Cold Shutdown 3 hrs.

10-25-76 Safety Injection Packing leak None Repacked valve. l*IR-Sl_:13929 Cold Shutdown *20 hrs.

MuV-1866 A,B,C,D,E,F 10-25-76 Refueling 1-RL-F-1 ***uigh delta-P None Replaced filter. l*IR-Sl-14134 Cold Shutdown 2 hrs.

lU-25-76 Feedwater MOV-151A \.lould not engage. None Operated valve satisfactorily. Cold Shutdown 2 hrs.

lfR-Sl-13752 10-25-70 Safety Injection Packing leaks None Repacked valves. IIR-Sl-13930 Cold Shutdown 20 hrs.

12 SI Valves lu-25-76 Heating Steam 1A Boiler Tube leak None Plugged 4 tubes. MR-Sl~l3895 Cold Shutdown 2 days

.!lli!!...!

MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).-

Page 2 of 3 OCTOBER. 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT DA'rE INVOLVED CAUSE OF THE l.fALFUNCTION ON SAFE OPERATION 10-26-76 Reactor Coolant l-RC-61 Packing leak. None Adjusted packing. MR-Sl-13925 Cold Shutdown 2 hrs~

10-27-76 eves MOV-127SA Packing leak. None Adjusted packing. MR-Sl-14231 Cold Shutdown 2 hrs.

10-21-76 eves Mov-121sB Packing leak. None Adjusted packing. MR-Sl-14232 Cold Shut40wn

• 2 hrs.

I 10-28-76 Spray Nozzles - Hi~ Lo Nozzles plugged. None Cleaned nozzles. HR-Sl-13396 Cold Shutdown 10 hrs.

I-' Level Intakes  ::- I

-P-

'f 10-23-76 Uydraulic suppressors Low on fluid. ?lone Refilled to normal level. HR-Sl-14165 Cold Shutdown 10 hrs.

l-RC-HSS-109-118-112-9-6 ll-13-14-124-143.

10-28-76 Circulating Water lD Screen inoperative. None Installed 6 baskets. ~m-s1~13716 Cold Shutdown 20 hrs.

Screen Low Level

. 10-28-76 Circulating Water 1A Screen inoperative. None Installed 4 baskets. MR-Sl-13463 Cold Shutdown 10 hrs.

Screen Low Level 10-29-76 Radiation Monitor Low flow None Renewed vanes. MR-Sl-14294 Cold Shutdown 2 hrs.

Pump 10-30-76 Steam Generator Sample Malfunctioning*valve; None Renewed valve. UR-Sl-13704 Cold Shutdown 2 hrs.

System 10-30-76 Containment Spray MOV-CS-101A & :S Valve leaks through None Lapped valve - test satisfactory.

HR-Sl-14221 Cold Shutdown 30 hrs.

• .. 10-30-76 Circulating Water Screen inoperative None Replaced 8 baskets. MR-Sl-13458 Cold Shutdown

• 30 hr~.

l-C\-I-S-10 10-31-76 Primary Grade Water Valve leaks through . None Renewed diaphragm. HR-Sl-124.75 Cold Shutdo~ 2 hrs.

.l-PG-10 (Grinnell)

Diaphragl!IS-leaking None Renewed diaphragms. iIR-Sl-13444 Cold Shutdodn 4 hrs.

10-31-76 Gaseous Waste 1-GW-115-116-126 (Grinnell)

!!!ill'...1.

MECHANICAL flfAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS) *.

Page 3 of 3 OCTOBER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE FOR MAINT.

INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY 1 0-31-76 Containment Vacuum TV-CV-150B Excessive leak through None Lapped -seat to disc tory. MR-Sl-14313

- tested satisfac- Cold Shutdown 10 hrs *.

i 0-31-76 Containment Vacuum Excessive leak through None Lapped seat to disc.- tested satisfac- Cold Shutdown 10 hrs.

TV-CV-15.lC tory, MR-Sl-14314

~ 1 0-31-76

\JI Containment Vacuum TV-CV-150D Excessive leak through None Lapped seat to disc tory. MR-Sl-14315

- tested satisfac-* Cold Shutdown 10 hrs.

0 I

1 0-31-76 Containment Vacuum Excessive leak through None ,. Lapped seat to disc - tested satisfac-** Cold Shutdown 10 hrs.

TV-CS-150A tory. MR-Sl-14312 1 0-31-76 Safety Injection Valve clogged. None Unclogged line and valve. MR-Sl-13454 Cold Shutdown 3 days l-SI-9 1 il-31-76 Sample System Valve stuck shut None Cleaned valve internals. MR-Sl-14025 Cold Shutdown 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 1-SS-lA ..

1 0-31-76 Safety Injection Valve clogged. None Un~logged line and valve. MR-Sl-13941 Cold Shutdown 10 hrs.

l-SI-166

~ .:

' . . -**. .. l,11*' :!~ ~- *.-~! *, ,. .*

... * - ...':.:;.,,: ..'.'.I .. .. *:*-,)*. l*',!"** . *,ii' * .. .*,

1*. .. . . . ...

-~ ~

h

• ' I ... .. ...

, ... . . ~- ,*. . ... .',

.":,;, .,**** !'.- *. ~ *.' :~-:-.~!

\

.' *: *:*.,. ~*. ¥-~.;_:.. 't~r. ."{;.~; ~ ~-*~.,. .'

-l,;~*,*-~.,/~,.--',.: ;~..;;, .i

UNIT 1.

MECHANICAL ~iAINTENANCE . :;**:

(OTHER SAFETY RELATED SYS1:EMS AND MAJOR ITEMS) :  ; . *

• OCTOBER, 1976

• r.a~.4.i. SYSTEM OR COMPONENT RESULTS ANDffiECT PRECAUTIONS TAKEN

=~

TIME REQ'D ",:

DATE I INVOLVED CAUSE OF THE MALFUNCTION ON SAFE bi>liRATtON CORRECTIVE. ACTION TAKEN FOR aEACTOR SAFETY FOR MAINT;

..J 10-1-76 'circulating Water Tube leak None ,. Plugged 5 tubes. MR.-Sl-13~01 NA 4 hrs.

D Waterbox 10-1-76 Instrument Air  ; Low amps None Replaced.valves. HR-Sl-13769 NA 20 hrs.

l-IA-c-2A, & 2B I i Circulating Water None Replaced 4 baskets. MR-Sl-13793 NA 10 hrs.

I-'

V, 10-3-76 all Low Level Screens ' Grinding noise *.

I-'

I 10-3-70 Circulating Water ,, Screen would not rotate. None* Replaced 6 baskets~ :* MR-Sl-13805 NA 10 hrs.

1-CS-S-lC 10-5-76 Circulating Water Tube leak None .. Plugged 1. tube_.. . MR-Sl-13819 NA 5 hrs *.

A *Waterbox '

10-11-76 Boron Evaporator *. Tube leak. None: Checked for leaking tubes.- found NA 20 hrs.

l-BR-E-2A none. MR-Sl-13863 10-15-76 Circulating .Water Screen would not rotate. None Replaced foot sprocket. HR-Sl-13822 Nt\ 40 hrs.

1-cw-s-1c 10-17-76 Refueling Canal Gate Inflatable seal leak. None Replaced seal. MR-Sl-13914 NA 6 hrs, D.S. TAYLOil - SUPERVISOR, HECHANICAL MA NTENANCE

UNIT NO, l MECHANICAL MAIN'tENANCB

* 'j.

(SAFETY RELATED SYSTEMS DURING OUTAGE.OR REDUCED POWER PERIODS).

PAGE 1 of 4 NOVElmER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT* PRECAUTIONS TAKEN TIME REQ'D DATE FOR MAINT, INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION  : CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY

~

11-1-76 Reactor Coolant Valve Valve Leaking through, None , *: ; : Renewed valve diaphragm (Grinnell) NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> TV-1519A * (Cyclic)  !; * *; MR-Sl-14326 h-2-76 Gaseous Waste Valves Diaphragm leakage, None  : ; Renewed valve diaphragms .(Grinnell) NA 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> l-BR-67 & 68 (Cyclic) , :- MR-Sl-13197 I 11-4-76 Chemical & Volume Valves leak through; None. * ./. .. ,.' Lapped valve disc to .seat. NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> i

I-'

U1 Control System Valves (Normal use)  :, '

N MOV-12117A,B & C

I 11-4-76 Chemical & Volume Valves leak through, None *:-,it ;::(/Lapped valve disc to seat,

' MP..-Sl-13989 * **

NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control System Valves (Normal use) *.:*

MOV-1286A,B & C  :.:;

• ,,, I *

• 11-5-76 Chemical & Volume Valve- leak through, None  :'.' : ; : :: .installed new valve intemals, NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control System Valve (Normal use)  :*

• i' ' 1 MR-Sl-14318 FCV-1160 , \ : I:.: : ,:

).1-7-76 Main Steam L,P, Rupture disc leaking, None ,.:!-:, ; ;:,Replaced rupture disc, ?m-sl-13897 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

• -.,i Turbine (Cyclic) 'I::

Ventilation System Refueling (PH) None  :*. :.* ; ;. Performed Liquid Penetrant test on I NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />

• 11-7-76

• 1-VS-F-lA-B-C ** , :, all blades - satisfactory. Checked

.. - 1 1'* : blade settings, MR-Sl-19233

• 'il-7-76 Gland Steam L,P,* Labrinth seal leaking None Replaced labrinth seals. ?IR-Sl-14363 NA 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> T*.*.-bine at /16 bearing, J, ' ... ;*:

.,t  : .*

,h-7-76 Service.Air 1-SA-Cl Annnal Inspection (PU) None 1!/i' i ;, .Performed annual inspection, NA ... *20 hours

!I  : . UR-Sl-14363

.U-7-76 Main Steam L,P, Rupture disc leaking, None . ,  ;: Replaced rupture. disc, MR-Sl-13896 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 1

Turbine (Cyclic) 11-3-76 Containment Escape DC-76-10 *** None Chicago Bridge and Iron installed ,

-_Escape Hatch, MR-Sl-14356 NA . 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.

Hatch *I I ,I,

.\-.

. UNIT NO. 1' MECHANICAL MAINTENANCE ....

,:/.':

(SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PAGE 2 of 4 NOVEMBER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ' V DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAIN'f *

.*.-r===~T,..,.,,,.....==~~""""'-~""'f==""""'====-=-~=.....,F-"========il--=------~==~;.,.;,,~...;.;;;;,;;;.;,;.,,-~,-.i~~~~~~:.:.-;;~,1....~""""',:.;,;,.;,.~

• 11-8-76 Emergency Diesel 03 Air side of radiator None Cleaned radiator. MR-Sl-13188. NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> dirty. (PM) 11-9-76 Containment Vacuum Valve leaks through. None .Lapped valve disc.to seat. NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Valve.TV~cv-150D (No'rm'ai Use) . MR-.Sl-14431 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I

u 76 Emergency Diesel 81 Air side of radiator None Cleaned radiator. MR-Sl-13187 NA I.J1 dirty. (PU) w 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> I 11-11-76 Instrument Air Annual Inspection (PM) None .. .Performed Annual Inspection. NA l-IA-C-2B , ,, ;

• MR-Sl-14224 . '* ..

Annual Inspection (PM)* None Performed Annual Inspection; NA 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />s*

ll-11-76 Instrument Air l-IA-C-2A , MR-Sl-14223 Mechanical seal leak. None  : .Replaced mechanical seal. MR-Sl-13491 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 11-11-76 Liquid Waste Pump l-LW-P-6A (Normal wear)

,*** 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Pumps not pumping. None <.

Replaced gaskets - bushings & adjusted NA

. 11-12-76 Radiation Monitor

~ump CC-P-6A-C & D (Norma_! wear) packing. MR-Sl-13492 Body to bonnet l~ak. None Re~laced bonnet gasket. MR-Sl-14348 NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

.11-12-76 Safety Injection valve HCV-1936 (Cyclic)

Packing leaking.(Cyclic) None Repacked valve. MR-Sl-14447 NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 11-12.:.16 Safety Injection valve MOV-lBBSC .

. 11-12-76 Valves leak through

• None ** *,Lapped valve discs to seats. NA 12 ~ours Containment Spray

..,~'! valves.

D MOV-CS-101C

..... _......... ,. ... , ..... , ..&. (Normal use-) *;rv*.~ir-1

.,,~.misl-14321 None Lapped valve disc to seat. NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 11-13-76 Instrument Air valve Valve leaks through.

l-IA-446* (Normal use) lffi-Sl-14452,,,.. . *---- ..

None* Lapped valve disc to seat,, NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

.11-13-76

• Instrument Air valve Valve leaks*through.

l-IA-939 (Normal use) MR-Sl-14451

UNIT NO, l MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS) :

• PAGE 3 of 4 NOVEMBER, 1976 DATE SYSTEM OR COMPONENT RESULTS A..~D EFFECT PRECAUTIONS TAKEN TIME REQ'D INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY . FOR MAINT.

.ll-16-76 -*Circulating Water Loose baskets, (Cyclic) None Replaced two (2) screens baskets, NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Traveling Screen MR-Sl-14493 1-CW-S-lC 11-17-76 Chemical and Volume Casing gasket*leak. None Replaced casing gasket, MR-Sl-14083 NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control System Pump (Normal use)

I 1-CH-P-lB I-'

U1 t11-19-76 Chemi~al and Volume Indication found during None Buffed indication subsequent PT NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Control System line  !SI PT inspection, satisfactory, MR-Sl-14510 2-CH-5-1502 11-19-76 Chemical and Volume Mechanical seal leak, None Replaced mechanical seal,* MR-Sl-1451 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />  :

Control System Pump (Cyclic) lt 1-CH-P-lB 11-20-76 Safety Injection Indication found during None Lightly surface ground indication, NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> line, 6-SI-49 ISI PT Inspection, subsequent PT satisfactory.

11-20-76 Safety Injection Indication found during None Lightly surface ground indication, NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> line,2-SI-74 ISI PT Inspection, s~bsequent PT satisfactory, 11-22-76 Refueling System Damage to car *and up- .. None Replaced Transfer Car. MR-Sl-14358 NA 400 hOUl'S Transfer Car ender, (Casualty) 11-22-76 Reactor Coolant Tube removal from None Westinghouse removed tube R2-C42 NA 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> 1-RC-E-lC Steam Generator for inspection, MR-Sl-14544 11-24-76 Reactor Vessel !SI None None Westinghouse performed IS! NA 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> Inspection Inspection of Reactor Vessel Nozzles; etc, MR-Sl-14218 11-24-76 Circulating Water

• Traveling Screen Broken Baskets None Rebuilt screen, MR-Sl-12942 NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> l-CW-S-2D

• UNIT NO. 1 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE. OR. REDUCED .POWER PERIODS) .: : .

1.'AGE 4 of 4 NOVEMBER, 1976 SYSTEM OR COMPONENT RESt11.,TS ~ ~FFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE FOR MAINT.

INVOLVED CAUSE OF THE l.fALFUNCTION ON SAFE OPERATION C.ORR!CTIVE ACTION TAKEN FOR REACTOR SAFETY 11-24-76 Chemical & Volume Suspect*line plugged None Verified line not plugged. NA 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Control System line with boron. MR-Sl-14351 l-CH-56-152 11-30-76 Boron Recovery Filter High D/P (Cyclic) None Replaced filter assembly. NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l-BR-FL-3B ., .. MR-Sl-12886

..... 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

..n 11-30-76 Boron Recovery Filter  : High D/P (Cyclic) None Replaced filter assembly. i NA J1 I 1:..BR-FL-JA MR-Sl-5525

' I: ';,.~, ..

• ,,I

.. ~... ,

D.

d;;t,/~

s. TAYLOR, SUPERVISOR - imcHANICAL MAI !ITENANCE

}~ONTHLY UNIT NO. 1

• OPERATING SUPPLEMENT SHEET*

MECI*L\NICAL .MAINTENANCE

. DECEHBER,. 1976 ...

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY'RELATED ITEMs** -116 2.

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MAINTENANCE ORDERS COMPLETED MAJOR OR.SAFETY-'RELATED ITEMS 32

. MONTHLY TOTAL 148,

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3. DESIGN CHANGES BEING WORKED DC-73-23,. 74.:;:.14; 76-31

4. PERIODIC TESTS PERFORMED I

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I MECHANICAL MAINTENANCE

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SUPERVISOR i:': .

UNIT tlO. 1 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS)-

PAGE 1 of 2 DECEUBER, 1976 PRECAUTIONS TAKEN TIME REQ'D SYSTEM.OR COMPONENT RESULTS AND EFFECT FOR MAINT.

DATE CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY

.INVQLVED CAUSB OF THE MALFUNCTION ON SAFE OPERATION Lightly ground weld crown, sub- NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-6-76 Reactor Coolant Pipe Indication found during None ISI Inspection_ sequently UT satisfactory.

4" RC-151502 lffi-Sl-14548 Installed repair kits and refilled* NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 12-8-76 Snubbers 2-WFPD"HSS Leaking fittings and None reservoirs MR-Sl-14644 10 & 3 La'pped disc to seat. Tested NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-12-76 Reactor Coolant Check Leaks through (Normal None use) satisfactory. MR-Sl-14327 Valve 1-RC-160 Replaced valve internals. MR-Sl-14199 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-13-76 Sample System Valve Leaks through (Normal None TV-SS-102B use)

Replaced valve internals. MR-Sl-14208 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> p-13-76 Sample System Valve Leaks through (Normal None IJ1 TV-SS-104B use)

"I12-13-76 Adjusted valve stroke and spring NA 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Sample System Valve Leaks through (Normal None use) tension. MR-Sl-14209 TV-SS-104A None Performed PT and visual inspection NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 12-17-76 Reactor Coolant Inspect nozzles (3) for ISI Inspection of all three (3) Reactor Th Nozzles.

Th Nozzles ~m-sl-14559 Reinspected -weld, found sa.tisfactory. NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12-19-71 Reactor Coolant Line Support weld indication None

~m-sl-14442 4" RC-15502 Lapped disc to seat, tested satis- NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-19-71 Safety Injection Valve Leaks through (Normal None use) factory. lffi-Sl-12760 ISI-109 Lapped disc to seat, tested satis- }IA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-19-71 Safety Injection Valve Leaks through (Normal None factory. lffi-Sl-14616 ISI-147 use)

Lapped disc to seat, tested satis- NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-20-7 Safety Injection Valve Leaks through (Normal None factory. ~m-sl-14614 ISI-130 use)

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UNIT NO, l MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS .DURING OUTAGE OR REDUCED POWER PERIODS).

Page 2 of 2 DECEMBER 1976 SYSTEM OR COMPONENT RESULTS A..'ID EFFECT PRECAUTIONS TAKEN TIME REQ'D

• DATE FOR MAINT.

• INVOLVED CAUSE OP THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY 12-20-76 Recirculating Spray Welds leak None Ground out welds and rewelded, tested NA 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> Sump Penetration Welds satisfactory. MR-Sl-15940

• • 12-22-76 *Reactor Coolant Valve Leaks through (normal None Lapped disc to seat, tested satis- NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

• l-RC-160 use) factory. MR-Sl-14724 12-22~76 Reactor Coolant Valve Packing leaks (Cyclic) None Repacked both. valves. MR-Sl-13746 NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> PCV-1455 A & B 12-27-7 Safety Injection Valve Body to bonnet leak None Renewed bonnet gasket. MR-Sl-13990 NA 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> MOV-1869B (Cyclic) 12-27-7( Residual Heat Removal Packing leaks (Cyclic) None Repacked valves. MR-Sl-14 789 NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I Valve MOV-RH-1700 I-'

U1 (X) l\!-28-71 Chemical and Volume Valve lifts low and None Repaired valve internals and set NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control Valve RV-1203 leaks through (Cyclic) lift pressure at 600 PSI. MR-Sl-13867 12-29-71 Reactor Coolant Valve Valve leaks through *None Machined seat and disc, lapped disc NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> PCV-1456 (Normal use) to seat, tested satisfactory.

MR-Sl-13366 12-29-71 Reactor Coolant Valve Leaks through _(normal None tlachined seat and disc, lapped disc NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> PCV-1455C use) .,. to seat, tested satisfactory.

MR-Sl-13368 12-30-76 Vents Gaseous Valve Leaks through (normal None Lapped disc to seat, tested sati*s- NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> TV-VG-109B use) factory. MR-Sl-14429 12-30-76 Safety Injection Valve Leaks through (normal None Lapped disc to seat, tested satis- NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> ISI-129 use) factory. t!R-Sl-14615

UNIT NO. 1 MECHA.~ICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS Ai.1D MAJOR ITEMS)

Page 1 of 2 DECEMBER, 1976

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SYSTEM OR COMPONENT RESULTS ANVEili'ECT PRECAUIIC>NS TAi(EN I Til*!E REQ 'D

. DATE . . INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT,

• r.r*i 12-3'-76 Liquid Waste Filter High D/P (Normal use) None Replaced filter elemert ~m~sl-12885 NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lLW-FL-3 12-6-76 Main Steam Valve  :(.eaks through (Normal use) None Rebuilt valve internals. MR-Sl-13323 NA .80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> PCV-MS-102 12-&-76 .Main Steam Ill L.P Routine inspection of None Inspection satisfactory, replaced NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Turbines blading - manway cover covers. MR-S1-l4lcl6 removal.

12-13-76 . Circulating Water *1A" ~ddy Current (Routine) None Eddy Current of 10% of tubes. NA 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> Waterbox MR-Sl-14449 112-13-76 Circulating Water "B" Eddy Current (Routine) None Eddy Current of 10% of tubes. NA 70 hour8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br />s=

l.n Waterbox MR-Sl-14364

\l)

I 12-14-76 Circulating Water Will not rotate (Cyclic) None Rebuilt screen. tffi-Sl-13788 NA 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Traveling Water Screen Low Level "lC" 12-14-76 Safety Injection None Installed None Uanufactured platforms for all three (3 NA 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Access Platforms accumulators. MR-Sl-14440 12-19-76 Ventilation System Manufacture 'Test Blank None Manufactured test blank. MR-Sl-1284' NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> i PT-16.4 of VS-lOOA B, C and D 12-22-76 Component Cooling Uechanical Seal Leak None Replaced mechanical seal. MR-Sl-14638 NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Pump 1-CC-P-lA (Normal use) 12-29-'76 Circulating Water Loose baskets (Cyclic) None Replaced one (1) basket. MR-Sl-14796 NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Traveling Screen Low Level "lC"

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UNIT NO. 1

• .* iiEcHANrCAt MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

.* . Page :i of 2 ,DECEMBER, 1976

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SYSTEM OR COMPONENT RESULTS AND EFFECt PRECAUTIONS TAKEN TIME REQ'D

.. DATE I_NVOLVED CAUSE OF THE MALE'UNCTION ON 8Al!'ILOP:SMT%0N CORRECTIVE ACT!ON TAKEN FOR REACTOR SAFETY FOR MAINT.

... .. ;,:i, iJ<- "I*

. 12;;,2?~76. Circilla,ting Wat:~r Broken Inserts (Cyclic) None Replaced eleven (11) inserts a~d NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Travelilig Screen five (5) baskets. MR-Sl-14788 J High Level ;,ID" I

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I D. s. TAYLOR, SUPERVIS0R-MECHA1HCAL MAINTENA? CE .

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MECHANICAL~ MOlffllLY OPERATING llBPOllT UNIT NO. 2 JANUARY, 1976 TOTAL NUMBER OF MAINTENANCE ORDERS COMPLETED 173*

Preca~tions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

1===r==========¥===========t===============I=~======~;;;=~~;;;~;;;~;;;

• Erosion - Restriction None Repair weld - Pin hole leak NA ~ hrs.

0

.~ 12-26-7511 Charging Pump*

'"";"' 2-CH-P-lB orifice MR-S2~5229 1-2-76 Main Condenser Water Suspect - Tube to None Plugged 57 tubes MR-S2-5257 NA 3 hrs.

Box 2-CN-SC-lD Tube Sheet Roll*

i' 1-2-76 Main Condenser Water Suspect - Tube to None Plugged 60 tubes MR-S2-5259 NA 21s hrs. ,l.i i I

Box 2-CN-SC-lD Tube Sheet Roll *.

I 2-ui . - .Steam Generator Blow- Erosion None Pad welded discharge pipe HA S hrs.

1 near 2-BD-l~ MR-S2-5252 'j down Piping 1-2-76 2" WGCB-601 Main Condenser-Water Suspect-Tube to None Plugged 81 tubes MR-S2-5247 NA 3 hrs.

l!

Box 2-CN-SC-lC Tube Sheet .Roll I 1-3-76 Containment Vacuum Condensation in line None Removed water from suction line NA 21s hrs.

MR-S2-5246 '

Pump 2-CS-P-lB i

l-~-76 Traveling Water Screen1 Overload of trash None Replaced S baskets }IR-S2-5264 HA 7 hrs.  !

Hi-Level 2-CW-S-lD against baskets *

• 1-7-76 Steam Generator Blow- . Erosion - Steam None Welded patch on tank MR-S2-5122 HA 10 hrs, down Tank 2-BD-TK-8 impingment Erosion None Plugged S tubes, cleaned drain *HA 20 bra.

1-10-76 Bearing Cooling Heat Exchanger 2-BC-E-lA valve *. HR-S2-5289 '

MECHANICAL MAINTENAN<E MONTHLY OPERATING REPORT UNJ;T NQ. 2 PAGE 2 JA11111AR:Y 1_976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

1-17-76 Containment Inst. Gasket None Renewed gasket on oil cover NA 1 hr.

Air Compressors changed oil in 2-1A-C-2A,B, 2-1A-C-2B MR-S2-5331 ..

1-17-76 Main Feedwater Reg, Packing - Normal use None Repacked with Grafoil packing Cold Shutdown 1 hr.*

Valve FCV-2498 MR-S2-5297 '

1-18-76 Main Steam Trip Valve Packing - Normal use None Repacked valve MR-S2-4890 Cold Shutdown 2~ hrs*.

l I TV-MS-201C I-'

CJ'

';"1-18-76* Reactor Coolant System Packing - Normal use None .Repacked with Grafoil packing Cold Shutdown 11 hrs.

MR-S2-5335 ,

Valve 2-'RC-20 1-18-76 Steam Generator Blow- *Gasket - Cyclic

• None Installed Fisher recolllllll!nded Cold Shutdown 8 hrs.

down Trip Valve Gasket Set, MR-S2-4547 TV-BD-200B '

i 1-18-76 Steam Generator Blow- Gasket - Cyclic None Renewed Bonnet Gasket MR-S2-529i Cold Shutdown 1 hr.  ;

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down Valve 2-BD-18 l-lS:76* Reactor Coolant System None - Preventative None Inspected Bergen-Patterson Cold Shutdown 2 hrs

• Hydraulic Snubbers .Snubbers MR-S2-5342 1-18-76 High Press, Heater Press, Breakdown None Renewed pressure b~eakdown Cold Shutdown 28 hrs.

Drains Pump sleeve - allowed sleeve and packing sleeve 2-SD-P-lB packing erosion MR-S2-5321  ;

• I-18-76 Main Steam Flow Trans- Packing - Normal use None Repacked valves HR-S2-5334 Cold Shutd~wn 6 hrs. '

mitter Root Valves 2-MS-96,130,131,167, rI 170 l-iS-76* RWST Overflow None* - Design Change None Implemented Design Change 74-1 Cold Shutdown 8 hrs.  !

74-1 MR-S2-3803 l~t'-761 Chemical & Volume Confrol System

- Line clogged with Boron, FT 2110 Leaking None Cleared line of Boron and renew-ed Flow Transmitter 2110 MR-S2-5062 & 4377 Cold Shutdown 3 hrs. '

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MECIWUCAL MAINTENANCE MONTHLY OPERATING: REPORT

• UNIT HO *. 2 .

PAGE 3 JAl.llTAYn'

• 1976 Precaution* Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved ~!function On Safe Operation To

• Prevent Repetition Safety During Repair For Maint.

Secondary Drains Level Type. of Trim. Needs None Renewed valve stem, MFG. Guide Cold Shutdown 24 hrs.

1-19-76 Control Valve .to be changed to Bushings and sleeved plug guides LCV-SD-206 *stellite Guide. MR-S2-4232 .

l-li9-76 Pressurizer Relief Solenoid Valve None Renewed Solenoid Valve Mlt-S2-5349 Cold Shutdown 3'5 hrs.

Valve PCV-2455C '

48 hra *  :'

. jl.-19-76* Steam Generator Erosion None* Explosive plugged (2) Tubes Cold Shutdown f-J 2-RC-E-lC Row 1 Column 62, Row 2 Column 48 O'I w MR-S2-5333 i I

None Renewed gaskets on reservoir HA .. 5 hrs.

1-19..;76 Hydraulic Snubbers Gasket on Reservoir  :

Grinnell Safeguards MR-S2-5347  ;.

Area 1-19-76 Feedwater Valve MOV-FW-251A Vaive was .jammed on backseat - possible

'None Removed motor - operated valve by hand - reinstalled motor Cold Shutdown 3 hrs.

• ~* i over-torque MR-S2-5354 . 'i:

1 hr ... I 1-20-76 Main Steam Dump Valve Packing - Normal use Hone Repacked valve MR-S2-5376 Cold Shutdown . I TV-MS-205B iI 1-20-76 Main Condenser Water None Hone Investigated could find no HA 3 hrs. I Box 2-CN-SC-lB indication of leaks. MR-SZ-5375 I I 1-20-76* Residual Heat Valve Packing-Temp. packing Hone Repacked valve with Graphoil Cold Shutdown 71s hrs.

MOV-2700 from construction ribbon.pack. MR-SZ-5360 l had not been changed 1-22-76* Reactor Coolant Valve Packing - Normal use None Repacked with Graphoil MR-S2-5428 Cold Shutdown 2 hrs. .

2-RC-16 't

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1-23-76* Main Steam Trip Valve Rockshaft was cracked None Renewed Rockshaft and sent brokeE Cold Shutdown 30 hrs.

TV-MS-201B on end near actuator shaft to Battelle Lab. MR-S2-538b i

1-23-76~ Main .Steam.Trip Valve None - Preventative None Removed* Rockshaft and sent to Cold Shutdown 30.hrs.

TV-MS-201A Battelle Lab. MR-S2-5419

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MECHANICAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO, 2 PAGE 4 JANUAAY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

1-23-76* Main Steam Trip Valve None - Preventative None Inspected valve MR-S2-S420 Cold Shutdown 30 hrs, TV-MS-201C 1-23-76* Main Steam Trip Valves None - Preventative None Removed valves and capped lines Cold Shutdown 20 hrs.

2-MS-100,101,133,134, Valves no longer MR-S2-5427 171, 172 needed,

,1-23-76 Traveling Water Screen1 None - Preventative None Tightened all baskets and inspec- NA s hrs.

t--' Lo-Level 1 & 2-CW-S-lA ted all units MR-S2-S438 O'I

.i::- BC, D 1

1-23-76 Traveling Water Screen ~one - Preventative None Tightened all baskets and inspec- HA s hrs, '

Hi-Level 1 & 2-cw-s-lA ted all units, MR-S2-S439 B,C,D, I

'1.'I '

1-23-76* Feedwater Valve None - Preventative None Installed new valve MR-S2-5426 Cold Shutdown 4 hrs. i 2-FW-33

.1-23-76* Steam Generator Blow- None *- Preventative

• None Installed new valves MR-S2-542S Cold Shutdown s hrs *.

down valves  :

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2-BD-21,22,24 I 1-23-76* Steam Generator Blow- None - Preventative None *Installed new valves MR-62-5445 Cold Shutdown 15 bra.

I down valves j 2-BD-11, 12, 14 1-27-76 Main Condenser Water Suspect tube to t~be- None Plugged 106 tubes MR-S2-5476 NA s hrs, Box 2-CN-SC-lB sheet roll.

1-27-76* Containment Vacuum Elect. penetration None Installed new elect, penetration NA 12 hrs, ...

Pump 2-CV-P-lB plug shorted plug. MR-62-5477  ;

1-28-76* Containment Vacuum Vane.a None Installed rebuilt pump MR-62-5490 NA 4 hrs, Pump 2-CV-P-lA 1-31-76* Instrument Air None - Preventative None Performed annual P.M. MR-S2-5308 NA 13 hrs,

Compressor 2-IA-C-l d~lv-v 1 ,*

D. S, TAYLOR-SUPERV SOR MECHANICAL MAINTENAI CE

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MECHANICAL MAINTENANCE MONTHLY OPERATING REPORT UNIT-' *No. 2*

FEBRUARY 1 1976 TOTAL NUMBER OF MAINTENANCE ORDERS COMPLETED 151

• Precautions Taken To System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maini I

-*==,======t==========t============l=======;:===4==~~~;;;;;=!~

~1-13-76 Instrument Air Com- None~ Preventative *None Performed Annual PreventativQ NA 12 hrs.

I.J1 pressor 2-IA-C-l Maintenance MR-S2-5306 I

.1-18-76 Blowdown Trip Va1ve Gasket - Cyclic None Renewed gasket set with new NA 4 hrs.

TV-BD-200D type graphite impregnated flexitallic, MR-S2-4536 ,; '

d

2-4-76 Traveling Water Strainer - High AP Bone 'Cleaned strainer & replaced 2 hrs. f Screens Hi- Level  ;.

(3) nozzles MR-S2-5616 I

2-CS-S-lB -------

None Implemented Design Change Cold Shutdown 16 hrs.

2-5-76* Containment Access None - Preventative DC 73-127 73-127 MR-S2-.S.l32 ,::.

• I Emergency Hatch 12 hrs.

I 2-6-76 Blowdown System None - Preventative None Renewed valves with sealed Cold Shutdown Valves 2-BD-1-2 & 4 /Bonnet Val'llles (Conoval)  !

..-..  :, lfil-S2-5527 I 2-6-76

• Main Steam Trip Valve Packing None Renewed stuffilll box gasket & Cold Shutdown µ hrs. I TV-MS-201A repacked, ~-S2-5614 i

• Cold Shutdown 1 hr.

I Renewed flange gaskets 2-6-76 *Reactor Coolant System Orifice Gasket*- Cyclic None t MR-S2-4861 'I I

None ,Renewed flex gasket, MR-S2-4862 Cold Shutdown lls hrs. I 2-6-76 "B" Reactor Coolant Gasket - Cyclic .,,.~. i Pump Seal Water By-pass line

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HECHANICAL MAINTENANCE MONTHLY OPERATING REPORT

• UKJ;T NO, 2 PAGE 2 l"EBB.UAR:r, 1976 Precautions-Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety Du~ing Repair For Maint.

2-7-76* Main Steam Non-Return Steam cut in Bonnet None Repaired steam cut & renewed Cold Shutdown 40* hrs.

Valve MS-NRV-201A ~eal ring area bonnet seal ring. MR-S2-5523 2-7-76 Safety Injection Gasket - Cyclic None Renewed flexitallic gasket .Cold Shutdown 4 hrs.

Check Valve MR-S2-5619 and 5627 2-SI-79 & 85 None Renewed flexitallic gasket Cold Shutdown 4 hrs.

2-7-76* Safety Injection Gasket - Cyclic Check Valves MR-S2-5615 & 4867 2-SI-240 & 238 1

2-7-76* Bergen-Patterson None - Preventative None Inspected snubbers - no Cold Shutdown 31:i hrs~

Hydraulic Snubbers defiencies MR-S2-5528 Tube Leak - Denting None Explosively plugged 42 tubes Cold Shutdown 5 days ,,;

2-8-76* Steam Generator 2-RC-E-lC Tube Wall thinning . ?m-s2-552S I I

2-10-76 Service Water Pumps None-Preventative None Implemented Design Change i NA ii hrs.

. 2-SW-P-4A,B, Design Change 73-76 73-76 1m-s2-so6e l 2-10-76* Main Steam Trip Valve Linkage *adjustment None ~djusted linkage MR-S2-5672 Hot Shutdown 5 hrs.  ;

J TV-MS-201A '*

2-11-76 Reactor .Coolant Valve Packing None Replaced valve MR-S2-5660 -HA 1 ht.  !

2-RC-24 2-11-76 Residual Heat Valve Packing None Repac~ed valve MR-S2-5661 kA. 5 hrs.

MOV-RH-2700 ';

2-17-76* Liquid Waste Pump Mechanical Seal None Renewed mechanical.seal NA 8 hrs. i LW-P-8 }m-S2-5351 i 2-23-76 Traveling Water Baskets None Renewed (2) baskets tightened NA. Sis hrs;. *'

Screens Hi-Level all bolts. MR-S2-5852  :

2-CW-S-lD

. D .S *. TAYLOR - SUP RVISOR

. MECHANICAL MAINTE ANCE i

HECUAllICAL HAI?ITENANCE (Safety Related Systems during Outace or Reduced Power Periods.)

UNIT NO. 2 OUTAGE TUBE LEAK C 'STEAM GENERATOR PAGE 1 of 2 Ti.ITAL NUMBER OF MAIN'IENANCE ORDERS COMPLETED 123

==:;::::=========::::::::;::==========:::::;:;:::;:::::==:==;;=:.=====================;:=::==========::::;=:====-

I Syst~'TI or Component Results and Effect Precautions Taken for Time ltequired/,"..*;:

I Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for Maint. :" '.

• I -- i

'I-'

C'\J.,~761 Reactor Coolant Valve . Packing - Normal use None Repacked valve, MR-S2-5931 Cold Shutdown 7 hrs,

• 'i" ... I 2-RC-77 3-7-76

-* I 2-RC-E-lC Steam Generator Tube Leak - cause not yet determined None Westinghouse Explosive plugged 115-tubes, MR-S2-5928 Cold Shutdown . , 40 hrs,

.\t**

I 3- 7-76 Reactor Coolant Valve Packing - Normal use -None Repacked valve, MR-S2-4856 Cold Shutdown

• 4 hrs.

2-RC-9 3-7-76 Cont, Inst. Air Valves - Normal wear None Renewed suction and discharge valves Cold Shutdown 3 hrs.

Compressor 2-1A-C-2B and piston rings. MR-S2-594~ & 5941 None Rebuilt valve, MR-S2-5914 Cold Shutdown 3-7-76 Sampling System Trip Valve. 2-TV-SS-201A Bellows ruptured -

normal use.

8 hJ;.B,

..'~. . i 3-7-76 Reactor Coolant Valve Packing - Normal use None Repacked valve, MR-S2-5668 Cold" Shutdown 3 hrs.

2-RC-95 3- 7-76 Reactor Coolant Valve Packing. - Normal use None Repa~ked valve. MR-S2-5666 Cold 'Shutdown 1 hr, MOV-2535 3-7-76 Reactor Coolant Valve Packing - Normal use Nor;ie Repacked valve, MR-S2-4857 Cold Shutdown . 2 hrs, **

2-RC-60 .. *:*.::.I

• l ..

I i

3-8-761 Charging Pumps 2-.CH-P-lB Service Water Line to Coolers - Erosion None Renewed piping with 90-10* Cu-Ni MR-S2-5657 Cold Shutdown 16 hrs. .*~.ji I  :~ r,_ "i

--;z:**.

I Charging Pumps Service Water Line to

• None 'Renewed piping with 90-10 Cu-Ni Cold Shutdown 3-9-761

! 2-CH-P-lA Coolers - Erosion MR-S2-5971

1mciwn:CAt HAnrrENANCE (Safety Related Systems during Outage or Reduced Power Periods,)

UNIT NO, 2 PAGE 2 of" 2

System o.

Component Results and Effect Precautions Taken for i

I Time Required

.? Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety I for Maint, I I f-'

°' 3 76j Charging Pumps Service water line to None Renewed* piping with 90-10 Cu-Ni Cold Shutdown

• 16 hrs, ._

CXl I

i 2-CH-P-lC Coolers - Erosion MR.-S2-59M ,

3-11-761 Cont. Inst. Air Valves - Normal wear None Renewed suction & discharge valves, Cold Shutdown 2-1/2 hrs. ..*.*'

I Compressor 2-1A-C-2A MR.-S2-6009 '

• *~....

I!

*>J:-.__

i 'i' 1*!

'I '

i I

I I

II D,

d.1.~~

s. TAYLOR..:. SUPERVISOR, MECHANC tAL MAINTENANCE I

i  ;

.i

;: :~. '

!,~

I

. I

.. \ .  ::::~. 1**

HECIIAllICAL HAIHTENANCE (Safety Related Systems during Outace*or Reduced Power P.eriods.)

UNIT 2.

MAY, 1976 PAGE 1 of 4 TOTAL NUMBER OF M R COMPLETED 245

tc I S}*ste.'11 or Component Involved Results and Effect Cause of the ?falfunction on Safe Operation Precautions Taken for Reactor Safety Time Required-for Maint*;

• Corrective Action Taken I *':**  :**:

I-' 4- 28-76 2-CH-FL-2 Normal use. High delta None Changed filters. MR-S2-5688 NA 6 hrs, ...

C\

\0 P. , _....... ,::-

I 5-8-76 TV-BD-200E-Blowdown Bonnet Gasket - Cyclic None genewed gasket set. MR-S2-5633 Refueling Shutdown 9 hrs.

Trip Valve

. 5-11-761 MOV-RS-256A Recirc.  ;:**-: ~ '

Failed PT-16.4

• None Reseated valve. MR-S2-12333 Refueling Shutdown 4 days , ..

Spray System Seat leakage *:. j 11-76! Fcv-211JB eves System Diaphragm None Renewed diaphragm. MR-S2-4125 Refuel-ing~Shutdown _ 3 hrs.

\.;~:

5-12-76! TV-BD-200F Gasket - Cyclic None Renewed gasket set. MR-S2-12392 Refueling Shutdown 10 hrs *. ,**

! Blowdown Tirp Valve 5-12-76i 2-CH-21 eves System Diaphragm None Renewed diaphragm. MR-S2-5506 Ref~eling Shutdown 2 hrs. ..

5-12-76 MOV-CS-200B Containment PT 16.4 seat leakage None ... .

Reseated valve. ~-S2-3994 Refueling Shutdown 3 days  !

Spray System.

5-12-76 BR-P-4B Primary Drain None.- Preventative Hone Performed semi-annual PM. MR-S2-5720 Refueling Shutdown 17 hrs.

Tank Pump 5- 13-76 2-EE-EG-1 Emergency None - Preventative ?fone *Performed semi-annual PM. MR-S2-6187 Refueling Shutdown 3 days Diesel .* !,

5-13-761 TV-MS-201A,B,C, Main None - Preventative None Accomplished*Design Change 75-41 Refueling Shutdown 18 days.

Steam Trip Valves I

I MR-S:Z:-12302 & 12089 .

• 1 I

--, 'I . .  :

..*. *4--: .. ii1*

HECIWJICAL HAINTENANCB (Safety Related Systems durinz Outace or Reducec! Power Periods.)

.!lli!!.1.

PAGE 2 of 4 MAY, 1976 System or Component Results and Effect Precautions Taken for Ti!lle Required :, ~t

.:c12: Im*olved Cause of the Halfunction on Safe Operation Corrective Action Taken Reactor Safety for .Maint~* *;':_;

I to-14-76 0

TV-2519 A & B Primary Diaphragm None Renewed diaphragm.

6129 MR-S2-12436 & Refueling Shutdown 4 hrs.

I Grade Water System 5-15-76 Fev-2177 eves System None-*Preventative None inspected valve internals, MR-S2-12396 Refueling Shutdown 6 hrs. ...

/-;..~.~

5-15-761 2-RC-160 Reactor PT-16~4 - seat leakage None Reseated valve, HR-S2~12437 Refueling Shutdown 10 hrs.  :.:/f I

Coolant System H 5-15-76! 2-RS-11 *Recirc, Spray PT-16,4 - seat leakage None Reseated valve. HR-S2-12374 *Refueling Shutdown i System i Bellows None Renewed bellows. . MR-S2-5747 Refueling Shutdown 5-16-76j TV-SS-201B Sampling System I .. .!_ ::

PT-16.4 - seat leakage None Reseated valve. MR-S2-12410 Ref\leling Shutdown 20 hrs.:.**. *..

• 5-16-76! TV-SI-201B Safety Injection System 5-16-76 FCV-2160 eves System PT-16.4 - seat leakage None Reseated valve. MR-S2-12408 Refu!!ling Shutdown. lOhrs,::'._

5-16-7E MOV-CS-201C & D PT-16.4 - seat leakage None Reseated valve HR-S2-12372 Refueling Shutdown ~20 *hrs/ --

Containment Spray - ..

System ...

5-20-71. HCV-2500 Safety Injec- - PT-16.4 - seat leakage None Reseated valve MR-S2-12435 Refueling Shutdown 10 hrs, .. J tion System

. $.j

.~.~~J*t~

~:'f*\

5-20-1d 2-RC-60, 2-PG-132, PT-16.4 - seat leakage None Reseated 2-RC-160, renewed diaphragm Refueling Shutdown I

i TV-PG-2519A .. on 2-PG-132 & adjusted stroke on

• I TV-PG-2519A, MR-S2-12482 I . .

HECIIA?lICAL HADJTENANCB (Safety Related Systems durin3 Outage or Reduced Power Periods.)

UNIT 2 MAY, 1976 PAGE 3 of 4 . ~ q!":." *;

=====:::;::::========::::;:::::::======:;:::================:=;==========:::;=====*

System or Component Results and Effect Precautions Taken for . Time Required :-;

,: *. te Involved Cause of the lfalfunction on*safe Operation Corrective Action Taken Reactor Safety for Maini:;-:;

• I

~5- 20-76 I-'

I TV-MS-201C Main Steam Trip Valves None - Special Eng.

Test.

None Installed linkage containing strain gage. MR-S2-12496 Refueling Shutdown

• _.,..,.; '.(:l

. *S- 20-76 Accumulator Level None - Design Change None installed Design Change 73-23. Refueling Shutdown 200 hrs~ .* ::..-:-:

Transmitters MR-S2-6159 .. -:.*

5-20-761 MOV-CS-201A & B PT-16.4 - Seat leakage None Reseated valve MR-S2:..12385

• Refueling S~tdown 120 hrs *. ~-_-

! Containment Spray.

I System 5-21-761 PCV-2456 Reactor Coolan Suspected seat leakage None Inspected valve internals - reseated Refueling Shutdown

.?;i'.l.~

30 hrs.*-*.:

.. - ! System i

MR-S2-5091  : ~'

-~-

- . ?- : ..J **

5- 21-761 63 Emergency Diesel None - Design Change None Performed mechanical function on Refueling Shutdown 6 hrs. _::;. (

I 74-97 Design Change 74-97. MR-S2-12507 **r:}.:*f:

5-21-761 PCV-2455C Reactor Suspected seat leakage None Inspected valve internals- MR-S2-5108 Refueling Shutdown 30 hrs *.

Coolant System 5-22-76 2-RC-E-lB Steam Generator Gasket None Repaired handhole gasket seating area by machining. MR-S2-12499 Refueling Shutdown

~* ....

60 hrs. * * *

' 5-23-7f 2-CH-P-lA,B,C, Charging None - Preventative None Installed miniflow orifices as per Refueling Shutdown_ 15 days Pumps DC 75-43 Design Change 75 "HR-S2-12380 . :;*.,

r .,

d 5-24-7, 2-RC-E-lB Steam Tube Thinning None Explosive plugged 102 tubes. Refueling Shutdown 25 days Generator MR-S2-12085 . .,

I *: ..-*:~. -::

I I

--, I i

,: . .1*-J.; , .

L L__

HECllAll'ICAL HAINTENANCB (Safety Related Systems during Outage or Reducei Power P~riods.)

illUT 2 MAY 1 1976 PAGE 4 of 4 System or Component Results and Effect Precautions Taken for Time Required Dace Involved Cause of the Halfunction on Safe Operation Corrective Action Taken Reactor Safety for }laint,

.!,.5-25-71 *Safety Injection Check None - Preventative None: Renewed bonnet gaskets, MR-S2-12443 Refueling Shutdown 8 days

-...J Valves 2-SI-79,82,85, N 91,88,94, 241, 242, 24',

.I 109, 147 .

5-25-71 2-RC-E-lA Steam Tube leak - Erosion None Explosive plugged 101 tubes and Refueling Shutdown 25 days Generator assisted Westinghouse in obtaining:: 'I a tube support plate sample. I' MR-S2-12083, 12413 & 12514 5-25-7 2-RC-E-lC Steam None - Preventative None Explosive plugged 21 tubes, Refueling Shutdown 25 days Generator MR-S2-12091 5-25-7 TV-SI-200 Safety Lower cage gasket cut, None Renewed gaskets, packing & adjusted Refueling Shutdown 10 hrs.

Injection System stroke, *MR-S2-12424 5-25-H . 2-DG-10 Gaseous Drains Diaphragm None Renewed diaphragm MR-S2-12368 Refueling Shutdown 2 hrs.  :

System 5-26-7 2-VS-F-lA,B,C Hone None Reset fan blades for pressure test Refueling Shutdown 20 hrs.

Containment Recirc. and restored to normal. MR-S2-5888

.... 12361, 12519 Fans 5-26-7D TV-SI-201A Safety PT-16.4 - seat leakage None Reseated valve MR-S2-12523 Refueling Shutdown 20 hrs.

Injection System 5-26-7b 2-S.I-229 Safety Gasket - Cyclic None Renewed bonnet: gasket. UR-S2-l2356 Refueling Shutdown 10 hrs.

System 5-26-7~ FIC-2155 Reactor Cool- Boron Blockage on None Cleaned Transmitter. MR-S2-12560 Refueling ~hutdown 10 hrs, I I ant Flow Transmitter float I l I

. . ~

MECHANICAL MAINTENANCE (Other Safety ~elated Systems and Hajor IteI!IS)

UNIT 2 MAY, 1976 PAGE 1 of 1 S)*stem or Component Results and Effect Precautions Taken for Tice Required

.:ie Im*olved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for ~!ainc.

I I-'

....... S-1-16 W

I! Circ.

2-CW-P-lA River Pump None - Preventative None Renewed bearing, reworked shaft to NA 55 days I shaft c?upling & aligned. MR-S2-5818 I

5- 24-76  ! Lube 2-LO-E-lA & B Main Oil Cooler Tube Leak - Erosion None Plugged 114 tubes 2-LO-E-lA. NA 10 days Plugged 41 tubes 2-LD-E-lB. MR-S2-5704 I

s- 25-76 1 2-FW-E-3B Feedwater Tube Leak - Erosion None Plugged 5 tubes. MR-S2-5434 NA 30 hrs. '\\

i Heater -

I I

fZ/~  :

D, S. TAYLOR - SUPERVISOR, MECHANICA MAINTENANCE I

I' .

• MONTULY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE

. UNIT i/2

• I I .

. Jmm, 1976

1. MAINTENANCE QRDERS COMPLETED.NON-SAFETY RELATED ITEMS 186

2. MAINTENANCE ORDERS COMPLETED.MAJOR OR SAFETY RELATED ITEMS 35

• 'MONTHLY 'J:OTAL 2.21

3. DESIGN CHANGES BEING WORKED 75-22, 76-4, 74-21, 75-52~ 75-111, 75-21

4. PERIODIC TEST PERFORMED 2 A~I_./

MECHAN~SUPERVISOR

(Safety Related Systems .durinR Outage*or Reducl!li Power P.eriods.)

UllIT 02 JUIIB 1 1976 J

l PAGE 1 of 4 - *~::

• 1 Results and Effect

'I ;I Date System or Component Involved Cause of the lfalfunction on Safe Operation Corrective Action Taken Precautions Taken for Reactor Safety Tia!e Required for Maine.

i.

t4 76 2-RC-E-2 Preasurizer Hone Hone Stenciled bolts for*inservice inspectioD Refueling Shutdown 10 hrs.

V,  :

requirements. HR-S2-12044 .

Il , 76 Steam Generator Main

.Steam Safety Valves None - PT-13.0 Hone Performed PT-13.0. MR-S2-5722

• Refueling Shutdown *- 5 hrs. "

!S-8-76 2-1A-C-2A & B None-Preventative None Overhauled Compressors.* Ifil-S2-12395 Refueling Shutdown 24 hrs.

i

i j

I I Containment Instrument Air Compressors

!i 76 Pressurizer Safety None-PT-12.0 None *Performed PT-12.0. HR-S2-57l6 Refueling Shutdown 6 hre **

i Valves s' -lS-76 Auxiliary Feed Pump None-Preventative Hone Performed.Annual P.H. Renewed thruat Refueling Shutdown 5 days i 2-FW-P-3A shoes and liner. lfil-S2-6178 I

5-18-76 Auxiliary Feed Pump None- Preventative None Performed Annnual P.at. Renewed inboard Refueling Shutdown. 2 weeka 2-FW-P-2 & 2-FW-T-2 & outboard thrust shoes. MR-S2-6177 &

MR-S2-6179 l

I

! ~-18-76 Steam Generator

. 2-RC-E-lB & C None-Design Change 75-22 & 76-4 none Performed Design Changes 75-22 & 76-94.

UR-S2-12093 & 12094 Refueling Shutdown

. 19 days

• .(

5 76 Feedwater Flow Venturi None-Preventative Uone Flushed Venturi Hozzles. lill.-S2-12425 Refueling Shutdown 6 days *'

76 2-Cll-P-lC Charging None-Preventative Hone 1 Performed Annual P.M. check. MR-S2-5711 Refueling Shutdown *11 days ,,

Pump, .. '

.,. I

-~.

I ..

I I . . *' ,,

. HEC!IA?IICAL HADITENAHCB (Safety Related Systems durinn Outace .or Reducecl Power P.eriods.)

. UlUT #2

• JU?m, 1976 5

/PAGE 2 of 4 System or Component Results and Effect Precautions Taken for Time Required l "r*ate Involved Cause of the Ualfunction on Safe Operation Corrective Action Tak~n* Reactor Safety for }lain t.

• i i Boron Evap. Pump None-Preventative Hone Performed Annual P .M. MR-S2-5717 Refueling Shutdown 4 days

. ~-, 5-21-76 1-BR-P-lA  ;.J j ;5-23-76 Sampling System Ruptured bellows None Renewed bellows. lm-S2-5744 * *Refueling Shutdown 6 hrs.

io I

• valve. TV-SS-201A 5-25-76 Containment Instrumen Hone - Preventative Uone Implemented Design Change 74-21 & 75-52 Refueling Shutdown 21 days Air Compressor *Design Change 74-21 & lfil-S2-12375 2-1A-C-2A,B, 75-52

5-25-76. &eactor Coolant Pump None - Preventative None Inspected 01,2 & 3 Mechanical Seals. Refueling Shutdown 5 day.a

• • I I 2-RC-P-lC lfil-S2-12348 i1

)

' . 5-25-7E Reactor Coolant Pump llone - Preventative Uone Inspected 02 & 3 Mechanical Seals

• Refueling Shutdown 6 days 2-RC-P-lB Renewed 02 Seal Asay. l.fR-S2-12347

' 5-25-7E I Reactor Coolant Pump Hone - Preventative Hone Inspected #2 & 3 Mechanical Seals. Refueling Shutdown 5 days 2-RC-P-lA lfil-S2-12346

~ 5-25-7E Safety Injection !lone - Preventative Hone Renewed Flexatialic Gaskets in (9) Refueling Shutdown 3_ days' i l Check Valves 611 and (3) 12" chl\!ck valves.

1.*1 I

l1R-S2-12443 5"-26-7E Safety Injection Seat and Disc marred. None Hachined, lapped and blued. l.fR-S.2-12523 Refueling Shutdown 2 days

'i Trip Valve.

l TV-S1-201A

.l j I i 5-26-U Mechanical portion None - Refueling None Performed work as per OP-4.1. Ref.ueling Shutdown 29 days I of Refueling MR-S2-12353

, . I. .

MECHANICAL HADITENANCB (Safety Related Systems. durin11 Outage or 'Reduced Power Periods.)

• muT n2

• JUtm, 1976 4

],...,.., 'I nf'

• nate i5-28-76 System or Component Involved

• Recirc, Spray System None - Preventative Results and Effect Cause of the Halfunction on Safe Operation None Corrective Action Tak~n Installed*new valves per Design Change Precautions Taken for Reactor Safety Refueling Shutdown Time Required.

for }laint.

30 days Valve 2-RS-255A & B 75-111. MR-S2-12341,12570 & 12571  !

I rJ5-28-76 Containment Instrument Packing None Re.newed Packing. ?m-s2-12575 & 12576 Refueling Shutdown 2 hrs;* t Air Compressor. ' i

!j,-,s-761 2-1A-C-2A & B Hydraulic Snubber Hone - Preventative None Inspected hydraulic *snubber as per MMP-P-G-014. MR-S2-12301 Refueling Shutdown 10 days

,\,

• ~

.l1 15-29-76 Safety Injection Slight scoring None Lapped, blued & tested. MR~S2-12336 Refueling Shutdown 30*hrs. *,

i t J Valve MOV-Sl-2860A &B & 12237 }

., iS-29-76 Main Steam Power Seat scored None Renewed seat, lapped & blued, Hll-S2-5637 Refueling Shutdown 48 hrs.

Operated Relief Valve RV-MS-201C

(

.*,.* 5-29-76 Recirc. Spray Heat Erosion None (1) Tube Leaking, plugged a pattern of Ref~eling Shutdown 24 hrs.

Exchanger 2-RS-E-lA 7 tubes. HR-S2-12542 j

.J

• *J5-30-76 Steam Generator Feed None - Preventative None Performed annual P,M, MR-S2-6181 Refueling Shutdown 12 days

. *1 Pump 2-FW-P-lA .:

.5-30-76 . Low Head Safety None - Design Change None Completed.Design Change*75-51. Ref~eling Shutdown 36 days Injection System 75-51 tm-S2-6105 5-31-76 Containment Vacuum Vanes None Installed rebuilt pumps, M~-S21 12587 &. . 'NA 4 hrs

• Pump 2-CV-P-lA,B lffi-S2-12588 I

I I

i ,

~-

' . '. ... l

• ~'

.*: HECIIAUI(:AL HAD~~

,(Safety Relat~d Systems*d~r~g*Ou~ace:or, ~u~e! PoweT ~eriods.)

mar' O'i.

• Jmra, 1976

• 1"' II

~ .PAGE 4 of 4

• .~ System or Component Results* and Effect

• Precautions Taken for Time Required Involved* Cause of .the Hal.function on Safe Operation Corrective Action Tak~n Reactor Safety for Maint. *

. i~,; rate jj.:.I

' 76

• Reactor Purification. Mechanical.Seal. Rone Renewed Hechantcal Seal *.* HR-S2-12378 6 hrs.

'!I System 1-RL-P-lB ,' '"g

- , *~25-76 Safety Injection _ :Erosion None Renewed Flow Transmitter. UR-S2-12817 NA 7 hrs.

I ' *system Flow Transmitte i FI-2942 1

i j

.j l

D. S. TAYLOR - SUPERVISOR, 1mcHA?lCIAL MAD IIENAHCE lJ

! l

. , I

• I *

,I'*' *I I

-, j .... , l

• • -... ~ **,, >. ~

'.;(()ther;.Safety Re,h~ed.Sf~tems and Major Items)

,UNJ

• T tl2 1976

~AGE 1 of 1

• system.or.Component . Results and Effect Precautions Taken for Time Bequir Date Involved Cause *of* the Malfunction

• on**safe Ooeration Corrective Action Taken Reactor Safety for Main*t I i

,:. *1- *.**.

I"" ;4-29-76

........ Traveling wa*ter . N~rma1'*use ** *:'.None Cleaned piping and nozzles, and .NA 5 days

'\O L Screens Lo-Level renewed rubber deflector'lips.

.',. .1

}. j. MR-S2-5715 jS-26-76 Extraction Steam. Gasket None Renewed flange gasket. MR-S2-6158 Refueling Shutdown. - 1 day i Safety Valve ,!

i SV-US-206A  ;

I 16-2-76 Main Condenser Water* Erosion None Plugged (1) Tube in C & D. NA 10 hrs.

Boxe~, 2-CS-SC-lA,B, MR-S2-12603 ,,

l

., C &D 6-10-76 Main Turbine IJ4 'Bearing wiped.during '-Hone Renewed fl4 Bearing, MR-S2-12618 NA 7 days Be.aring startup.

• 6-13-76 .Main Condenser Water Erosion *Hone Plugged (3) tubes, HR-S2-12730 NA 3. hrs.

.Box 2-cw-sc-1c 6-14-76 Main Condenser Water *Erosion None Plugged (1) Tube, HR-S2-12740 NA 3 hrs. L 1'

Box 2-CW-SC-lB . '

• ... "~*** ...~,*, . --*-* ,:- . *,.~.- *,

n; s. Taylor, Supv. Mech. Maint.

• MONTHLY OPERATING SUPPLEMENT SHEET.

MECHANICAL MAINTENANCE UNIT NO. 2 JULY, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 72 2.

MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS

. MONTHLY TOTAL 74 °

3. DESIGN CHANGES BEING WORKED 1

I 1--'  :'(

00 0

I

4. l'ERIODIC TEST *PERFORMED 0

MECHANI~ MAINTBNAHCE (Other.Safety Related Sys~ems and Major Items)

UNIT NO. 2 JULY, 1976 1 of 1 System or Component Results and Effect Precautions Taken for Time Required Date Involved Cause of the Malfunction on Safe Oneration Corrective Action Taken Reactor Safetv for Maint.

I

~ _15..;71 Chilled Water PIDDp Mechanical seal None Rebuilt outboard mechan~cal seal.

MR-S2-12967 NA

• 10 hrs.

1--' 1-CD-P-lB I

7-20-7! Boric Acid Filter High Delta-P-Normal None Changed filters. MR-S2-12628 NA 10 hrs.

2-CH-FL-1

)

D.

d~/H/

s. TAYLOR - SUPERVISOR, MECHANICA ~ MAINTENANCE i

• MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE UNIT NO. 2 AUGUST, 1976

l. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 50

2. HAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 5 MONTHLY TOTAL 55

3. DESIGN CHANGES BEING WORKED DC-75-55, DC-76-2 I 4. PERIODIC TESTS PERFORMED PT-41 r-'

CX)

N I

A ~/rv' MECHANICAL MAINTENANCE SUPERVISOR

HECIWIICAL HAI?rrENANCB (Safety Related Systems during Outace or !teducec! Power P.eriods.)

WIT NO. 2 AUGUST. 1976 PAGE 1 0f 1 System or Component Results and Effect Precautions Taken for Time Required I'*a:e Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for ~!aint.

I I r-'

10"-SI-362-153 None - Preventative None Ground area by weld number 15 & .rewelded * .Cold Shutdown 00 I.,)

I 7-ll-71 10"-SI-363-153 as per L.H.S.I. Design Change Report.*

HR-S2-13066

• 2 days 8-2-76 Pressurizer Relief Rupture disc had bll.nute None Renewed rupture disc. 1m-s2-1Jo9s Cold Shutdown 12 hrs.

Tank crack. .l I ";

a-2-76 !I Letdown Relief Valve. Seat damage. None Reworked. tested and reinstalled valve. Cold Shutdown 12 hrs.

RV-2203 !m-S2-13092 i -

i i

I' I

I I

I i

i . . ..

,._H 0 .

l.

I i

MECHANICAL, MAINTENANCE (Other:Safety Related Systems and Major Items)

UNIT NO. 2 AUGUST, 1976 PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Time Required.

Date Involved Cause of the Malfunction on Safe Ooeration Corrective Action Taken Reactor Safetv for Maint.

I f,-1 00

+:-

a-u-.~ Liquid Waste Pump Mechanical seal None Renewed mechanical seal. MR-S2-13108 NA 2 days I l-LW-P-2B

.8-20-, 6 Main Condenser Water- Erosion None Plugged (2) tubes. MR-S2-13177 NA 6 hrs.

box~ 2-CN-SC-lC (

r.: ~

t-

' ~

II~ 7. r~W D.S. TAYLOR - SUPERVI OR, MECHANICAL MAINTENANCE

• MONTHLY OPERATING SUPPLEMENT SHEET

. MECHANICAL MAINTENANCE UNIT NO. *2

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 107

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 33 MONTHLY TOTAL 140

3. DESIGN CHANGES BEING WORKED nc~16-39 1 2A Steam Generator Tube Recoval, DC-76-4, J. Tube Uodification 2A Steam Generator.

4. PERIODIC TESTS PERFORMED I

(X)

\J1 I

MECHANICALINTENANCE SUPERVISOR

U!l'IT UO. 2 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PAGE 1 of 2 SEPTE~IDER 1976 SYSTEM OR COMPONENT RESULTS AIU> EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE FOR MAINT.

INVOLVED CAUSE OF THE 1-iALP'UNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY 9-17-76

• Steam Generator Blow-* Gasket - Cyclic Hone Renewed gasket set. lfR-S2-13077 Cold Shutdown 10 hrs.

down Trip Valve.

1V-BD-200C 9-18-76 Pressurizer Spray Valve Packing - Hormal use None Repacked valve. HR-S2-13329 Cold Shutdown 2 hrs.

PCV-1455B

.1

~9-19-76 Feedwater valve Packing - llormal use Repacked valve. MR-S2-13346 Cold Shutdown 8 hrs.

MOV-FW-251 E & F

°'

I 9-19-76 Reactor Coolant System Packing - Uormal use None Repacked valve. lfR-S2-13342 Cold Shutdown 2 hrs.

valve. HCV-2557A 9-19-76 Reactor Coolant System Packing - lformal use None Repacked valve. HR-S2-13341 Cold Shutdown 2 hrs.

valve. LCV-2460A 9-19 r-Chemical & Volume Packing - Uormal use None Repacked valve. lfR-S2-13330 Cold Shutdown 2 hrs.

Control System valve HCV-2311 9-19-76 Bergen Patterson Hone - Preventative . Hone Inspected snubbers & checked fittings. Cold Shutdown 4 hrs.

Hydraulic Snubbers MR-S2-13326 9-20-76 Residual Heat Valve Hone - Preventative None Repacked valve. lfil-S2-13323 Cold Shutdown 2 hrs.

MOV-2700 9-21-76 Chemical & Volume Gasket - Cyclic None Renewed bonnet gasket & repacked Cold Shutdown 10 hrs.

Control System value valve. MR-S2-13350 HCV-2310A 9-22-76 Sampling System Trip Bellows assembly packing None Renewed bellows assembly, packing, NA 12 hrs, Valve SS-201A gaskets - Cyclic gaskets. llll-S2-13331 9-23-76 Chemical & Volume ** Seat, disc, bellows None Renewed complete valve. NA 4 hrs.

• -C.ontrol- System RV-22133 assembly - Cyclic ~m-s2-12454

I ..

I tnUT HO, 2 MECHANICAL MAINTENANCE i

I (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PAGE 2 of 2 ~ , n"J SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE FOR REACTOR SAFETY FOR MA.INT.

INVOLVED CAUSE OF THE.MALFUNCTION ON SAFE OPERATION CORRECrIVE ACTION TAKEN

!1-23-76 Reactor Coolant System Packing - llormal use Uone Reneweq packing, HR-S2-13357 NA 6 hrs, Valves 2-RC-12, 2-RC-13 9-27-76 Chemical/Volume Control Diaphragm - Cyclic ?lone Renewed diaphragm, MR-S2-12901 NA 2 hrs.

System Valves. 2-CH-208 I 2-CH-210 I-'

CX)

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1-:'

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UNIT 2.

• I *; I *: ~

MONTHLY OPERATING SUPPLEMENT SIIEET MECHANICAL MAINTENANCE OCTOBER, 1976

.~' , ~*  : *:

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED*. ITEMS

2. . MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY.- RELATED ITEMS- ~12 MONTHLY TOTAL 50

. 3. DESIGN CHANGES BEING WORKED DC-76-oa,: DC-76-04. DC-76-03. DC-76-44. DC-73-23.*

DC-76-46 .

4. PERIODIC TESTS PERFORMED I

f--' *1

00. *; ..

• Cf . ~ *

.. i: '

..... i*

MECHANICAL MAINTENANCE

.: ,*.* ..

• SUPERVISOR

UNIT 2 MECHANICAL MAINTENANCE .:  :

(SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

Page 1 of OCTOBER, 1976 SYSTEM OR COMPONENT RESULTS A,.~D*EFFECT PRECAUTIONS TAKEN TIME*IIBQ 1 D DATE. FOR MAINT.

INVOLVED CAUSE OF THE l-fALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY

• 10-1-76 Polar Crane Galled gearing .None .Replaced gears in iii Gear Box. Cold Shutdown 100 hrs.

. , .... MR-S2-12096 ,

10-4-76 Steam Generator Tube plug le~king. None Welded leaking plug. UR-S2-13324 Cold Shutdown 3 days 2-RC-E-lB

• 10-6-76 Steam Generaotr Tube leak. None Plugged 4 tubes. ?IR-S2-13325 Cold Shutdown 3 days I 2-RC-E-lC 1--'

CX>

'f 10-11-76 Decay Heat Release. Bonnet leak None Welded steam cut. MR-S2-12869 Cold Shutdown 3 days HCV-MS-204  :

10-11-76 Air Compressor. Gasket leak. None Replaced head gasket; MR-S2-l3483 Cold Shutdown 4 hrs, 2-SA-C-lA 10-13-76 Reactor Coolant Orifices Flange leaks None Replaced gaskets. MR-S2-13455 Cold Shulldown 6 hrs, *I "B" FE-2491 "C" FE-2482

. 10-14-76 Reactor Coolant Valves. Packing leaks,: flange None Adjusted packing, tightened flange

• Cold Shutdown 2 hrs, - ,'

2-RC-90, 2-RC-91, leak. MR-S2-13454 2-RC-41, 2-RC-51' 10-14-76 Chemical & Volume Pump casing leak. None Replaced gasket. MR-S2-13394 Cold Shutdown 3 days Control System 2-CH-P-lC 10-16-76 Recirc, Spray System Chloride Sti:ess ?lone Hydrolasered piping. MR-S2-13521 Cold Shutdown 10 hrs *.

2-RC-E-lA Corrosion *

'10-20-76 Circulating Water Pump low d1.scharge None Rebuilt pump. HR-.S2-13211 Cold Shutdown 5 days 2-CW-P-2B pressure.

10-22-76 Fuel Handling Crane Design Change None Implementect.D.C. MR-S2-12664 Cold Shutdown 3 days 10-27-76 Steam Generator Design Change None Implemented D.C. MR-S2-13389

• Cold Shutdown 10 days 1-RC-E-lA . .. ... -

ffLL D,

• S, TAYLOR -/SUP~RVISOR, ?IECHAN:&CAL MAINTENAl CE ....

UNIT NO~. 2***:: . '

MONTHLY OPERATING SUPPLEMENT SHEET MECHA.~ICAL MAINTENANCE NOVEtIBER, 1976.

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY.RELATED ITEMS 74.

• I j:

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY. RELATED ITEMS * . 17

• MONTHLY .TOTAL 91

3. DESIGN CHANGES BEING WORKED DC-76-31 *.

.~ .

/I I

4. PERIODIC TESTS PERFORMED I

I-'

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MECHACALMAfNTENANCE i

SUPERVISOR I*

~ - - * ~ * ,*. ~*-**,_*_.*.

I I

I UNIT NO. 2 MECHANICAL MAINTENANCE cs~ RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS) : ' .... :* .. ' ,,

NOVEMBER, 1976 PAGE 1 of 2 SYSTEM OR COMPONENT RESULTS A.'lD EFFECT PRECAUTIONS TAKEN

• TIME REQ 1 D DATE FOR MAINT.

INVOLVED *CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAI<EN FOR REACTOR SAFETY

• 11-3-76 Main Steam System Seat, Disc* leakage None Lapped disc to seats & renewed, NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Valves PCV-MS-202 (Normal 'wear.)* * :.* * *gaskets. MR-S2-13497 MOV-MS-207 11-3-76 Safety Injection .Solidified boric acid None Opened tank and removed scale and NA 60.hours System Tank 2-SI-TK-2

• and scale. boric acid. Cut valve out to remove I & valve 2-SI-9 boric*acid plug & rewelded.

~

\Cl MR-S2-13425 I-"

I, 11-11-76 Chemical & Volume .~asket :- Cycli~ .. None Renewed bead gasket. MR-S2-13438 NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Control.System Pump*.

2-CH-P-lA

.'*.:1 11-14-76 Chilled Water System Tube leaks - Corrosion None Replaced tube bundles. MR-S2-6130 NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> '.

Air Ejector Condensers 1-CD-EJ-2A & 2B 11-16-76 Chemical & Volume Mechanical seal leaks. None Replaced mechanical seal. MR-S2-13592 NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control System PIJ!llp (Normal wear) 2-CH-P..;lA 11'"'.16-76 Feedwater valves Packing leakaije (Cyclic) None Repacked valves. *MR-S.2-13579 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> FCV-255A,B & C 11-17-76 Chemical & Volume Relief valve leaking. None T~sted valve to 500 psi, no leakage NA 6'hours Control System through. noted. MR-S2-13584 RV-2203 11-17-76 Reactor Coolant Opened*primary manways None Leak:* *tested and closed S/G. NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 2-RC-E-1-C Steam for suspe.cted tube MR-S2-13502 Generator leaks.

11-18-76 Reactor Coolant Opened primary manways None Leak tested and closed S/G. NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 2-RC-E-lB for suspected tube MR-S2-13503 Steam Generator leaks. *

• UNIT NO. 2.

MECHANICAL MAINTENANCE (SAFETY BELATED SYS~ DURING OUTAGE OR REDUCED POWER PERIODS)*:" * ;, . ***, ""

• ':PAGE 2 of 2 NOVEMBER, 1976 SYSTEM OB. COMPONENT RESULTS A.'tP EfnCT ,. - ... . . PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF 'IHE 11ALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

Reactor Coolant Opened primar:y ..manways None :Leak tested, _R:plugged 5 tuqes. NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 2-RC-E-lA for tube plugging. MR-S2-13552 Steam Generator 11-19-76 Chemical & Volume Mechanical seal leaka. None Replaced mechanical *seal. NA *10 hours Control System.Pump. (Cyclic) MR-S2-13556 I 2-CH-P-lC i,,.

~ 11-19-76 Reci~culating Spray Tube leakage. None Plugged two (2) Tubes. MR-52-13585 NA 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

. I System 2-RS-E-lD Cooler 11-19-76 Reactor Coolant . Diaphragm retaining None Drilled out and replaced broken ~ hours Ji screws broken. 1/4" - 20 screws. MR-S2-13608 ','i"'.

2-RC-E-lB Steam Generator 11-21-76 Reactor Coolant Rupture disc leaking. None Replaced rupture disc. MR-S2-13637 NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 2-RC-E-2 Pressurizer Relief Tank 11-25-76 Circulating Water Drive pin sheared. None Replaced one (1) basket & one (1) NA 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Screen 2-cw-s-lA drive pin. MR-S2-13655 11-25-76 Reactor Coolant Tube leaks. None Westinghouse- performed _preventative NA 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 2-RC-E-lA-lB-lC plugging,~402 tubes). MR-S2-13499 11-26-76 Safety Injection Valve leak through. None Lapped valve disc to seat. Tested NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Relief Valve satisfactory. MR-S2-13661 RV-2885C D. S. TAYLOR, SUPERVISOR - lmCHANICAL MAINTENANCE

-, . ~

• UNIT NO. 2 MONTHLY OPERATING SUPPLEMENT SHEET MECHANICAL MAINTENANCE DECE?IBER, 1976

• 1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 149

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY. RELATED ITEMS 32 MONTHLY TOTAL 181

3. DESIGN .CHANGES BEING WORKED DC-76-31

-4. PERIODIC TESTS PERFORMED I

1--'

\0 w

I ICAL MAINTENANCE SUPERVISOR

UNIT NO, 2 MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PAGE 1 of 3 DECEMBER, 1976.

SYSTEM OR COHPONENT RESULTS A.~D EFFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE AciroN TAKEN FOR REACTOR SAFETY FOR MAINT.

12-2-76 Service Water System None-Annual Preventative None PM performed in accordance with NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 1-SW-P-lC Maintenance MMP-P-SW-006 MR-S2-6185 12-4-76 Chemical and Volume Solidification of Boron None Rodded out solidified boron. NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control System MR-S2-13613 12-4-76 Safety Injection Lines plugged with None Cut lines and removed solidified boron NA 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> System solidified boron and rewelded. MR-S2-13618

. I , 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 12-4-76 Seal Water InJection Normal usage None Renewed filter elements. MR-S2-12630 NA Filter 2-CH-FL-4A 12-6-76 Safety Injection Design Change 73-23 None Modified sensing lines. MR-S2-13615 NA 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Accumulators I

I-'

,2-7-76 Seal Water Injection Normal usage None Renewed filter elements. MR-S2-12631 NA 10 .hours I Filt.er 2-CH-FL-4B 12-7-76 "C" Stm, Generator Bolts over stressed None Renewed existing Vascomax bolts with NA 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Support Strap*s new ones. UR-S2-13744 12-7-76 Safety Injection Gasket deteriorated None Cleaned gasket surfaces and renewed NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> System SI-TK-2 gaskets. MR-S2-13736 12-7-76 "B" Stm, Generator Bolts over stressed. None Renewed existing Vascomax bolts with NA 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Support Straps. new ones. MR-S2-13785 12-7-76 Service Water System None-Annual Preventative None PM performed in accordance with NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 1-SW-P-lA Maintenance MMP-P-SW-006, MR-S2-6184 12-7-76 "A" Stm. Generator Bolts over stressed None Renewed existing Vascomax bolts NA 40.hours Support Straps with new ones. MR-S2-13746 12-8-76 Hydraulic Snubbers Normal usage None .Rebuilt both snubbers. MR~S2-13740 NA* 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 2-WFPD-HSS 5 & 2

MECHANICAL MAINTENANCE (SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).

PGE 2 of 3 DECEMBER 1976

=~==a,===,===-====;===~,========-=-====~~~~~~=~~===--a--=--~==~,=========;~

SYSTEM OR CO}ll'ONENT RESULTS A.~D EFFECT PRECAUTIONS TAKEN TIME REQ'D' DATE FOR MAINT.

INVOLVED CAUSE OF THE HALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY 12-8-76 Hydraulic Snubbers Normal usage None Installed new "o" ring kits in NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> SHP-HSS-14A & 14B reservoirs and filled with oil.

MR-S2-12871 12-8-76 "A" Main Steam Line Normal usage None Installed new "o" ring kit in NA lO*hours Hydraulic Snubber reservoir and filled with oil.

Reservoir MR-S2-12907 12-8-76 Grinell Snubbers Normal usage None Installed new "o" ring kits in NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> SHP-HSS-16,17,18,19, reservoirs and filled with oil 20 MR-S2-12867 12-9-76 Reactor Coolant Sys. Normal usage None Replaced diaphragm MR-S2-13739 NA 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I HVC-2522-B r'

'{l2-9-76 Reactor Coolant Sys. None None Retorqued primary manway bolts to NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Steam Generator Man- 1600 foot pounds, MR-S2-13765 ways 12-9-76 Containment Access Normal usage None Replaced two bearings and adjusted NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Door door. MR-S2-13713 12-9-76 Main Steam System None None 'Retorqued secondary manways to NA 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Steam Generator Man- 500 foot pounds and handholes to ways 250 foot pounds. MR-S2-13766 12-9-76 Snubber 2-HSS-RH-20 Normal usage None Install new "O" ring kit and filled NA *a hours reservoir with oil. MR-S2-13781 12-11-76 Circulating Water Sys. Normal usage None Plugged one tube - "A" Box NA 20 hciurs Main Condensers Plugged one tube - "B" Box Plugged two tubes- "D" Box MR-SZ-137813 12-15-76 Charging System None - Inspection None Inspected orifice and verified no NA 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> FE-1127 blockage. MR-S2-13815

UNIT NO, 2 MECHANICAL MAINTENANCE~

(SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS).*

PAGE 3 of 3 DECEMBER, 1976 SYSTEM OR COMPONENT RESULTS A,.~D EFFECT PRECAUTIONS TAKEN THIE REQ ID DATE FOR MAINT.

INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY

=====et==============el==============F===========l======~====~===~====+===========!~s-=--:.,,"'===-=-l~*

12-15-76 Reactor Coolant System Stuck Rod None Disassembled Control *Rod Drive Mechan- NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Control Rod Drive ism, replaced latching mechanism and.

Mechanism D-6 reassembled. MR-S2-13808 12-17-76 Reactor Coolant System Design.Problem None One h1.mdred-fifty-one Tubes (151) NA 4 days Plug Leaking Tubes in plugged by Westinghouse, MR-S2-13318 "A" S/G 12-19-76 .Main Steam Generator None-Inspection None Opened secondary side for inspection NA 40 houi;s "A" of Top Support Plate and tube bundle.

MR-S2-13344 12-24-76 Chemical and Volume Recurring problem with None Removed valve and replac*ed with one NA 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> I Control System this valve. from Unit #1, MR-S2-13854 f-"'

'l> RV-2203

'f' 12-24-76 Reac.tor Coolant System Design Problem None Removed manways, plugged two (2) tubes, NA 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> Steam Generator Tubes closed manways. MR-S2-13912 2A Steam Generator

UNIT NO. 2 MECHANICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEc1S A.'ID MAJOR ITEHS)

PAGE 1 of 1 DECEMBER, 1976

- .. - _,_ .. SYS'IE=M=O=R=c=o=~ll'=-*-=oN=El=N=T===============,=RE=s=u=L=T=S=Al=N;;;D;;.EF="FE"'c"'T~~==================.==PRE=='c""A""UT='=r'='oN"'s-T""AKE'==N=~==T""r=ME===RceE""'Q"""D=-~

'.,:E INVOLVED CAUSE OF THE HALFUNCTION ON SAFE OPERATIC!{ CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

12-15-76 Chemical and Volume Normal- usage None Removed flow element, clean~d and NA Control System reassembled. MR-S2-13813 FIC 2158 12-15-76 Main Steam System Packing Cyclic None Repacked and adjusted packing as NA 2-TV-MS-201A-B-C necessary. ?ffi-SZ-13805 12-19-76 Bearing Cooling Unknown None Plugged nine (9) tubes in "B" and two NA System Heat Exchan- (2) tubes in "A". Replaced expansion gers A & B joint in "B". MR-S2-13711 12-20-761 High Level Intake Normal usage None Replaced two .(2) baskets. MR-S2-13877 NA Screen. 2-CW-SID 12-23-76 I Gaseous Drain Normal usage None Renewed valve bonnet and diaphragm. NA I 2-DG-14 MR-S2-13913 I

f-'

.....I I

• S. TAYLOR, SUPERVISOR - MECHANICAL MAIN1[ENANCE

.,1

• ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO, 1

JANUARY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd

,=====f====I=n=v=o=l=v=ed====f===Ma=l=f=u=n=c=t=i=on=====t=====O~n=S=a=f~e=O;:;p~er~a=t;i;o~n====:J::=:=:;T;;o~;P;r;ev;en~t~:;;R;;e;;;p;;e;;t;i;t;i;on;:;==:!=::;;;s;a;fe;t;y~D;u;r~i;n;g~Re~p~a;i~r~=d:::F~o~r~Ma~i~n~t:::.=

tc;l-2-76* MOV-CS-lOlA Dirty Contacts on None Cleaned torque switch contacts EMP-C-MOV-18 3 hrs, 00 . MR-Sl-6613 I

torque switch Electrical Penetration* None Replaced penetration & motor EMP-C-EPL-27 10 hrs, 1-2-76* 1-CV-P-lB and motor shorted MR-Sl-5964

'*tI MOV-CS-102A Defective Limit switch None Replaced limit switch assembly EMP-C-MOV-18 4 hrs, 1-5-76*

for valve open indica- }ffi-Sl-6623 ting light Personnel Hatch Inner Door lack pin mechan- None Freed pin MR-Sl-6645 NA 1 hr, 1-7-76 Door ically stuck Car. leveling limit None Adjusted leveling limit switch NA 1 hr, 1-7-76 Auxiliary Building Elevator switch out of adjust- MR-Sl-6651 ment Open Coil None Replaced coil NA 21s hrs, 1-7-76 Auxiliary Feedwater.

Valve PCV-MS-102 im-sl-6650 Defective motor and None Replaced motor, and overload NA 171s hrs, l-S:-76 Unit Heater HS-HV-22B overload relay relay MR-Sl-5638 Micro switch contacts None Adjusted tension on micro-switch?s NA 1 hr.

1-12-76 Acid and Caustic Tank level switches not making contact MR-Sl-6152 WT*lOB, WT-109 1.:.21-76 Fire Water Initiated Deluge pressure switchEs None Dried out deluge pressure NA 1/2 hr.

alarm wet switches MR-Sl-6695

ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT

. UNIT HO. 1 PAGE 2 TANflAn- 1Q7f; Precaution* Taken To Date System or Component Cause of the Results and Effect Corrective Action *Taken Provide for Reactor Time Req'd On Safe Operation ... To Prevent Repetition Safety Du~ing Repair Involved Malfunction For Maine.

1-22-76 Electrical Penetration Low Pressure on pene- None Charged penetration to spees. NA lls hrs, B-18 tration 1-22-76 Security Gate 4 Close limit switch out None Adjusted limit switch MR-Sl-6507 NA l's hrs.

of adjustment 1-23-76 Flash Chamber High Micro switch out of None Adjusted micro swi,tch MR-Sl-6702 NA 1 hr.

Level Alarm adjustment I LS-WT-105 t-'

\0

\0 1-23-76 Auxiliary Steam Drain,* Micro switch out of None Adjusted micro switch MR~Sl-6554 NA 2 hrs.

I Rec. LS-AS-100 adjustment 1-21..16 Bearing Coolin~ Open on B Phase None Removed all tape from motor leads NA 8 hr11. *,  :-

BC-P-lA and retaped MR-Sl-6769 kl 1-27-76 Breaker fqr .. Insulation on wires . None Replaced wire and contacts on assembly and tightened. all NA 6 hrs. '

1-vs-F-2Sc from Bus to *Breaker Brittle and burnt connections MR-Sl-6475 ..

• Checked all heaters, replaced . NA 8 hrs. i 1-29-76 Security.TV Cameras Camera heaters None*

inoperative A & E heaters MR-Sl-6622.

i

1. -v~ R. E. NICHOLLS-SUPEE VISOR i

ELECTRICAL MAINTENA~ CE l

I

MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE FEBRUARY, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 25

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 31 MONTHLY TOTAL 56

3. DESIGN CHANGES BEING WORKED.73-129, Personnel Hatch Modification, 74-1, RWST, I

N 74-97, Diesel Wall Tank Modification, 75-7 Component Cooling Heat Exchanger Radiation Monitor 0

0 I

ELECTRICAL.SUPERVISOR L _ _ __

• ELECTRICAL MAINTENANCE MONTHLY OPEBATING REPORT FEJSRUARY, 1976

• UNIT NO. 1 Precautions Taken To

~~ ilte I System or Component Involved Cause of the Malfunction Results and Effect On Safe Operation Corrective Action Taken To Prevent Repetition Provide for Reactor Safety During Repair Time Req F-or :-r.ai:::

I N

0 2-2-76 Air Conditioning Insufficient discharge l~one Repaired leak in unit and had. NA 4 hrs,

...... VS-E-FDR-B pressure . system recharged. MR-Sl-6967 I

2-3-76 Air Compressor Defective overload None Replaced overload assembly. NA 2~ hrs.

IA-C-3B assembly MR-Sl-6850 2-3-76 Heat Tracing Line Thermostat's out of None ,Readjusted thermostats NA 2 hrs.ii l-CH-148, 149 adjustment

• MR-Sl-6845 2-6-76 Electrical Penetration1 Low Nitrogen pre~~ure None - Recharged p~netrations MR-Sl-6880 NA. l's hrs.

18B,17E,16E,2D, 2E 2-6-76 I Seismic Instrumentatio1 None None .. ...  ;

Performed PT-31.3 *:.,. I ~* *. NA 4 hrs.

Test PT-31.3 ..

2-6-76 Fire Protection System None None li>~rformed PT-24.4 NA 8 hrs.

PT-24.4 2-16-76 Fire Protection Halon None None Perf~rmed PT~24,6 NA 4 hrs.

1301 System PT-24.6 .. . .

2-18-76 neat Tracing System None None Performed PT-27 NA 8 hrs.

i PT-27 2-20-76. Refuelin~ Water ,Floats not.adjusted None Adjusted floats as per Design

. NA 2 hrs.

Storage Tank according to Revision ., ~-

,. Change 74-1 . MR-Sl-6612 74-1

. *. ;,;;**:*****.*_l:. .. .

I ..  ! ':~-'~ . . ::.

ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO. 1**

PAGE 2 FEBRUARY 1976 Precautions Taken.To Date System or Component Cause of the Results and Effect Corrective Action* Taken Provide for Reactor Time Req'd Involved f1alfunction On Safe Operation To Prevent Repetition Safety During Repair 'For !tlint.

2-24-76 Electrical Penetrations* Low Nitrogen pressure None Recharged penetrations NA ~ hr.

D-2,E-16, E-17 MR-Sl-6994 2-26-76 Electrical Penetration Low Nitrogen pressure None Recharged penetration NA 10 min.

I B-18 MR-Sl-7031 2-27-76 Air Conditioning Defective control None Replaced control transformer NA 3 hrs.

VS-E-FDR-C transformer MR-Sl-6965 I

N 0 2-29-76 Station Batteries None None Performed PT-23.1. NA 8 hrs.

N PT-23.1 I

rp ~ I} ~_,,g PIL R. E, ~ICHOLLS - SUPERVISOR

-- ~

ELECTIUCAL MAINTENANCE

~

MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE MARCH 1 1976

1. MAINTENANCE ORDERS CQMPLETED NON-SAFETY RELATED ITEMS 46

2. MAINTENANCE ORDERS CO~ETED MAJOR OR SAFETY RELATED ITEMS. 11 MONTHLY TOTAL 57

*.* .f.

3. . DESIGN CHANGES B£1NG im'RKED.

• Di~sel Wall. T~nk M~di"fi~ation, Flood Control, LQK Head I

N 0

w Safety Injection, RS 255A & B, Eme~gency Turbine 01:f.. Pump Modification 75-j4

• I

4. PECODIC TEST PERFORMED 16

• ELECTRICAL HAIHTE!:lA?lCE (Safety :1lllhrfed Systems* during Outage or Reduced Power Periods.)

UNIT l MARCIi 1976 PAGE*! of 1

~ate I

Syste.~ or Compon~nt Involved Results and Effect Cause of the lfalfunction on Safe Operation Corrective Action Taken Precautions Taken* for Reactor Safety ITime Required

, for !*!ai:, c.

l-1...,, I I

N i 0 Reactor Coolant Pump None None Took oil samples from motors and had N/A 3 hrs,

.i::- Motors 1-RC-P-lA, I analyzed. Test satisfactory.

1-RC-P-lB, 1-RC-P-lC Mlt-Sl-6971 3-15-76' 1-N.RV-11S-101A None None Disconnected valve for mech. maint, EMP-C-MOV-11 5 hrs, Reconnected and tested, test satisfac-tory, ' UR-Sl-6970 3-15-76 Boron Recovery BottOID! Motor g:i,ounded Hone Replaced motor and tested, test satis~ EMP-C-EPL-12 8 hrs.

Pump l-!3R-P-9 factory, MR-Sl-6972 3-15:-76 CLS Relay Defective Coil None Replaced ccilil and tested, test satis.... : EMP-C-RT-24 3 hrs.

CR-CLS-1B6 factory. MR-6979 3-17-76 Containment Sump Pump Motor grounded Hone Disassembled, cleaned and dried motor, EMP-C-EPL-27 10 hrs, l-DA-P-4A repacked bearings. Reassembled and tested, test satisfactory. MR-Sl-6961

I

~18-761 MOV-FW-151A Defective agastat None Replaced agastat and tested, test EMP-C-MOV-18 2 hrs,.

! I timer, satisfactory. }IR-Sl-7263 3-18-761 MOV-RH-1700 Defective packing ring.

None Disconnected MOV for Mech, Maint, Reconnected and tested, test satis-EMP-C-MOV-11 I I

4 hrs, I factory. !IR-Sl-7246 I

I I

ELECTnICAL llAillTEUA?lCE (Other Safety Related* Systel'l& and Hajor Items)

MARCH 1 1976 PAGE 1 of 1 System or Component Results *and Effect Precautions Taken for Tillie Require*

Date Involved Cause of the lfalfunction on Safe Operation Corrective Action Taken Reactor Safety for ~!air:r I

N 0

U'3- 24-76 Heat Tracing Ckt. Defective Strip None Replaced strip heaters. MR-Sl-7121 EMP-C-HT.,.37 5 hm I

1-CH-P-2D Heaters

£2rrk;*~/

R. E. NICHOLLS - SUPERVISOR ELECTRICAL !' l't.INTENANCE iI I

I II I II i

• I' il ....*

. .~.. .:*: .

ELECTllICAL UAUITEllAllCE (Safety Releated Systems* during Outage or Reduced Power Periods.)

UNIT 1 APRIL, 1976 PAGE 1 nf 1

,::'ate  !

Systc.~ or Component Results and Effect Precautions Taken for I Time Req:.i::.rccc Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety I for !*:a::.:-i c *

~!

~i 4-29-7!>

I Motor Operated Valve Torque Switch Conta~t Hone Adjusted Torque Switch Contact. EMP-C-MOV-18 llu; I  !

• MOV-1381 not making MR-Sl-12143 I

• 4-30-h Containment Air Defective Motor Bearing None Replaced outboard motor bearing. EMP-C-EPL-27 16 hrs.

Recirc. Fan. lfil-Sl-012165 1-VS-F-lB i -

I I

I R. E. NICHOLLS, SUPERVISOR El ECTRICAL MAINTENANCE I

i I

I I I

I

-, I . .

• . ~ '

• • MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 89

2. MAINTE?~ANCE ORDERS COMPLETED MAJOR OR SAFETY 'RELATED ITEMS 19 MONTHLY TOTAL 108

3. DESIGN CHANGES BEING WORKED. 74-55,73-127. 75-21 (completed) 75-43 (cnmp]eted)

I N

0

-...J 73-111, 75-51 {Completed Unit #2) 75-44 (completed on Unit 2) 74-97 (completed)

I

4. PER:ODIC TEST PERFORMED 16 ELECTR1CAL SUPERVISOR

ELECTRICAL IIAillTEUANCE (Other Safety Related Syste!'ls and Major Items}

UNIT 1 MAY, 1976 PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Time* Required Date Involved Cause of the Halfunction on Safe Operation Corrective Action Taken Reactor Safety for Maint I

N 0 5-4-76 Personnel Hatch Ground on outer door None Replaced defective wiring. MR-Sl-12184 NA NA (X)

I circuitry.

5-5-76 Boron Stripper Pump Pump tripped on over-*,: None Checked motor.All checks normal. Started NA NA BR-P-7A load motor. Motor drew excessive amperage.

Had Control Room notify Mechanical Dept.

MR-Sl-12412 5-9-76 Containment Vacuum Defective overloads None Replaced overloads. HR-Sl-12434 NA NA 1-CV-P-lA 5-25-76 Charging Pump Lube Trips on overload None Hotor grounded. Installed new motor. NA NA Oil Pump 1-CH-P-lB Replaced overloads. MR-Sl-12522 R. E. NICHOLf.S - SUPERVISOR. ELECTRI AL MAINTENANCE

• • MONTHLY OPERATING SUPPLEMENT SHEET

• ELECTRICAL MAINTENANCE JULt, 1976

a. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 128 2*. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 08 MONTHLY TOTAL . 136

• l 0

3.

.._,~...;..;.-----~...;;.;.__.;..~----------------

DESIGN CHANGES BEING WORKED. 74-55 (Flood Control)

I.D I

4. PERrODIC TEST PERFORMED 16 UNIT 1 UNIT 2 (4) PT-34 (5) PT-34 (1) PT-24.4 (1) PT-23.2 (1) PT-24.6 (1) PT-27 (1) PT-27 ELECTRICAL SUPERVISOR (1) PT-31.3 (1) PT-23.2

ELECTRICAL llAIUTEUA?~CE (Other Safety Related Systeris and Major Items)

UNIT NO. 1 JULY, 1976 System or Component Results *and Effect Precautions Taken for Time Required Date* Involved Cause of the lfalfunction on Safe Operation Corrective Action Taken Reactor Safety for Maint.

1, N:

t-'! 7-6-76 BR Ueat Rracing, Circuit Defective Heat Tape None Replaced 24 ft. Heat Tape, MR No. Sl- EMP-C-HT-20 8 Hrs.

o. 21, Panel I 012130 I!

' 7-17-76 1-RC-P-lA None-Preventative None Drained oil flushed pots and refilled EMP-P-LU-28 10 Hrs.

Maintenance with oil, MR No. Sl-012117.

7-17-76 1-RC-P-lB None-Preventative None Drained oil flushed pots and refilled EMP-P-LU-28 10 Hrs .*

.Maintenance with oil, MR*No. Sl-012118 * '*

7-17-76 1-RC-P-lC None-Preventative None Drained oil flushed pots and refilled EMP-P-LU-28 10 Hrs.

Maintenance .with oil, MR No. Sl-012119.

R.,E. Nicholls, Supervisor El~ctrical i

• Maintenance

MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 121

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 7 MONTHLY TOTAL 128

3. DESIGN CHANGES BEING WORKED- 75-34*, 75-44, 75-51, 74-97 and 75-43.

I N

t,-1 t,-1 I

4. PERIODIC TEST PERFORMED 7 ELECTRICAL SUPERVISOR

ELECTRICAL llAillTEUANCE (Other Safety Related Syetel'le and Major Items)

JUNE, 1976 UNIT /fl PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Time Required

)ate* Involved Cause of the lfalfunction on Safe Operation Corrective Action Taken Reactor Safety for Maine.

6-16-76 l-SW-P6 DC-75-7 None

. Completed DC 75-7. J,ffi-Sl-4603 DC-75-7 NA 6-21-76 #3 Emergency Diesel DC 74-97 None Completed DC-74-97. MR-Sl-6482 DC-74-97 NA \

Wall Tank Level Transmitter 6-21-76 Reactor Coolant Pwnp Open coil in relay None Replaced relay. J,ffi-Sl-12662 EMP-C-RT-24 HA '{

Bus lB Undervoltage BFO 485 alarm

~~#~

R. E. UICHOLLS, SUPERVISOR-ELECTRICAL 11'1 NTENANCE

--, I '

.. .':. ~ -

MOHTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE September, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 81

2. MAINTEHANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 9 MONTHLY TOTAL 90

3. DESIGN CHANGES BEING-WORKED. DC 75-51 75...45 75-36 I

N f--'

w I

4. PERIODIC TEST PERFORMED 15 UNIT 1 UNIT 2 PT-34 (5) PT-34 (5)

PT-23.1 (1) pr.:..23.1 (1)

PT-31.3 (1) PT-27 (1)

PT-27 (1)

• I' UlHT 1 ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

Page 1 of 1 SEPTEMBER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

~-3-70 Heat Tracing l!ark lie,, Defective Heat Tape !lone Replaced 2 ft. of Heat Tape. EMP-C-HT-20 4 hrs.

2-CH-148 Panel 8, l!n.-Sl-13073 Circuit 17A 9-3-76 Heat Tracing Panel 9, Defective Heat Tape Uone Replaced 25 ft. of Heat Tape. EMP-C-HT-20 10 hrs.

Circuit 17 MR-Sl-13279 I

N

..... 9-7-76 Heat Tracing Panel 8, Defective Heat '.Lape !lone Replaced 48 ft, of Heat Tape, EMP-C-HT-20 14 hrs,

-'=" Circuit 21 llR-Sl-13280 I

9-6-7b Emergency Diesel ifo.1 Defective JlVR Relay None Replaced HVR Relay. HR-Sl-12026 EMP-C-EE-21 6 hrs *.

Annunciator 9-9-76 Heat Tracing Mark Uo. Low Temp. cause<l by None Re-positioned thermostat, llR-Sl-13293 EMP-C-HT-20 2 hrs, 2-CH-143, 147 & 40. thermostat out of position.

9-13--76 Reactor Coolant Pump BFD Relay 48S failed. None Replaced BFD Relay, llR-Sl-13407 EMP-C-RT-24 3 hrs, Bus Alarm 9-30-16 Instrument Air Dryer Thermostat faile<l. None Replaced thert.1ostat. :_ llR-Sl-13289 EMP-C-lA-31 6 hrs.

~~~~ L.. \>..~.~ J)Jf 1 R, l , NICHOLLS,'"'SUPERVISOR-LlIBCTRICAL l!AINTEi AHCE

• . I l

,,I i:

M0?1THLY OPERATING SUPPLEMENT SHEET ELECTRICAL*MA;NTENANCE UNIT NOS

• 1\. & 2 "AUGUST, 19?6 I

1.. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 68 1

2. MAINTEHANCE ORDERS COMPLETED MAJOR OR SAFETY- RELATED ITEMS 6 i: MONTHLY TOTAL 74 N

I I-'

u, 3.

DESIGN CHANGES BEING WORKED- 74-55~ 75-45, 75-36

. I

4. PER10DIC TEST PERFORMED 12 UNIT 1 UNIT 2 PT-34 (4)

• PT-34 (4)

PT-23.1 (1) PT-23.1 (1)

PT-23.3 (1)

PT-23.4 (1) CAL SUPERVISOR

I  :

ELECTRICAL llAIHTElIANCE (Safety Related Systems* during Outage or Reduced Power Periods.)

UNIT NO. 1 AUGUST, 1976

• PAGE 1 of 1 i System or Component Results and Effect Precautions Taken for Time Required

.':.to? I Involved Cause of the lialfunction on Safe Operation Corrective Action Taken Reactor Safety for }faint,

~i!-4-76 I CH-.34 Heat Tracing Misadjusted thermostats None Reset thermostats. MR-Sl-12916 EMP-c..:.HT-20 6 hrs.

~ I Circuit 2B ,Panel 9 I

8-4-76 Lines l-CH-38, 143 and Defective Heat Tape None Replaced 3 ft. Heat tape. lffi-Sl-12918 EMP-C-HT-20 10 hrs.

149 Heat Tracing Panel 8, Circuit 17.

8-11-7{ Emergency Diesel ;/2 Not Applicable None Reset louver control to open at 160°F Engineering Study 76-09 4 hrs.

vice 175°F. MR-Sl-13002 8-13-7{ 2-CH-148 '& 149 Heat Hisadjusted thermostats None Reset thermostats. MR-Sl-13086 EMP-C-HT-20 5 hrs.

Tracing Panel 8 & 9.

8-13-7f Emergency Diesel #1 Not Applicable None Reset louver control to open at 160°F Engineering Study 76-09 4 hrs.

vice 175°F. MR-Sl-13064

,!,. r'

• *....... *  :.;*.

~.\'llh .,...J \,\.,.J R.E. lUC-HOLL'S, SUPERVISOR - ELEC' RICAL MAINTENANCE

.\.

MOm.'ULY OPERATING Su"PPLEMEtlT SHEET ELECTRICAL MAINTENANCE OCTOBER, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS. 163

2. MAINTEliANCE ORDERS COMPLETED MA.10R OR SAFETY RELATED ITEMS 1 MONTHLY TOTAL 164 I

3. DESIGN CHANGES BEING WORKED- 75-51, 75-45, 75-36, 76-08, 75-38, 75-44, and 76-27.

1-v \:

t--"

-...J I

4. PER:ODIC TEST PERFORMED 15 UNIT 1 UNIT 2 PT-23.4 (1) . PT-34 (4)

PT-34 (4) PT-23.1 (1)

PT-23.1 '(1) PT-27 (1)

PT-27 (1) 'ELECTRICAL SUPERVISOR PT-24.6 (1)

PT-23.2 . (1)

U!UT HO. 1 ELECTRICAL MAI1'TENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 OCTOIJER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN . TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

-~.:.

a 10-7-76 Charging Pump Oil System. !1otor would not stop Wene Replaced overload contactor and main EMP-C-EPL-07 and 6 hrs.

(1-CH-P-lC) contact coil. HR-Sl-13810 EMP-C-EPL-12 I

N f--'

co I

I d~

R. E.1 lUCHOLLS - SUPE RVISOR 0 ELECTRICAL MAINT ~NANCE

• MO?ITHLY OPERATING SUPPLEMENT SlIEET ELECTRICAL MAINTENANCE

1. "MAINTENANCE ORDERS.COMPLETED NON-SAFETY RELATED ITEMS 106

2. MAINTEUJ\NCE ORDERS COMPLETED MAJOR OR. SAFETY RELATED ITEMS 47

• MONTHLY . TOTAL

• i,53 3 * . DESIGN CHANGES BEING WORKED:76.:.33; 76-08; 76-38; 7-5-44; 75-51;73-111; 76-31; 75-34; 75-21;

• I N

I-' 73-23; 75-36

\D I

4. PERIODIC TEST PERFORMED 14 UNIT I UIJ IT 11 **

(4) 34 (4) 34

~

(1) 23.1 (1) 23.1 . .

(1) 31.3 ( 1) 27 I *

(1) 31.2 EC ICALSUPERVISOR

( 1) 27

ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

UIIIT tJO. I PAGE I of 5 UOVE/1BER 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY F.OR MAINT.

11/9/76 EPDC Single Phase Preventat ilie /1aintenance None Performed Procedure EtlP-C-EPDC-9 Inverter Procedure EMP-C-EPDC-9 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

{MR Sl-014111) 11/9/76 CW MOV-CW-lOOC Preventative Maintenance tlone Performed Procedure Et1P-P-MOV-45 Procedure EMP-P-MOV-45. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

{MR Sl-014144)

I 11/9~76 SW MOV-SW-101A Preventative Ila in tenance tlone Performed Procedure EMP-P-MOV-45 N Procedure EHP-P-HOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> N {HR Sl-014155)

I-'

I 11/9/76 SW MOV-SW-101B Preventative Maintenance tlone Performed Procedure EIIP-P-IIOV-45 Procedure EHP-P-HOV-45 1,5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

{HR Sl-014154) 11/9/76 SW HOV-SW-103A Preventative Maintenance None Performed Procedure EHP-P-IIOV-45 I Procedure EHP-P-HOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

{MR Sl-014156) 11/9/76 SW HOV-SW-103D Preventative tlaintenance *uone Performed Procedure EIIP-P-110V-45.  :

Procedure EHP-P-HOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR Sl-014159) 11/9/76 SW MOV-SW-103B Preventative Maintenance None Performed Procedure EMP-P-MOV-45 Procedure EMP-P-HDV-45 1,5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />  :

"{HR Sl-01~158) 11/9/76 SW MOV-SW-103C Preventative Maintenance None Performed Procedure EHP-P-/IOV-45 Procedure EHP-_P-MOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

{MR Sl-014157 11/9/76 SW MOV-SW-102A Preventative t1aintenance None Performed Procedure EIIP-P-MOV-45 Procedure EHP-P-HOV-45 2 hours

{MR Sl-014160) 11/9/76 CH MOV-CH-1286B Disconnect and Reconnect !lone Disconnected and Reconnected Procedure EHP-C-HOV-11 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for Mechanical Dept, (MR Sl-014304) 11/9/76 CH MOV-CH-1287B Disconnect and Reconnect !lone Disconnected and Reconnected Procedure EHP-C-MOV-11 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for Meehan i ca I Dept, (IIR Sl-014302) 11/9/76 CH MOV-CH-1287C Disconnect and Reconnect !lone Disconnected and Reconnected Procedure EMP-C-MOV-11 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for Mechanical Dept, (MR Sl-014303)

. , **.* ,..i .,._.; *,. ' *******; ** *;: : " ; * ,* ' . , :* * * ~' ** *J * -, *** * * . .

ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

U~IT ~O. I .

DAl'C  ? nf I; tlOVEMBER 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN, TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

11/9/76 CH HOV-CH-1206C* Disconnect and Reconnect None Disconnected and Reconnected Procedure EMP-C-HOV-11 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for Mechanical Dept. (HR 51-014306) 11/10/76 CW MOV-CW-106D . Preventative 11a in tenance !Jone Performed Procedure EHP-P-110V-45 Procedure EMP-P-HDV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR 51-014153)

I J'1 / J°J /76 VS HOV-VS-I OOB Preven tat i ve Maintenance None Performed Procedure EMP-P-HOV-45 Procedure EMP-P-HOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> N

N N

(MR 51-014249)

I 11/11/76 SW MOV-SW-102B Preventative Maintenance None Performed Procedure E11P-P-HOV-45 Procedure EHP-P-MDV-45 ~-5 hours (MR 51-014236) 11/12/76 VS 1-V5-F-IA Preventative 11aintenance !lone Performed Procedure EMP-C-EPL-40 Procedure EMP-C-EPL-40 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I

. (tiR Sl-014018) ..

11/12/76 EPH Hain Generator, Main Preventative Maintenance None Cleaned and Checked All Relays Procedures-EMP-RT-01 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> Transformers, and (MR 51-014399) EMP-RT-02 5 tat ion Service EMP-RT-03 Transformers Relays EHP-RT-04 EHP-RT-05 EHP-RT-06 EHP-RT-07 EHP-RT-08 EHP-RT-09 EHP-RT-11 '

• 1,;12/76 Screen Wel 1 #1 Preventative Maintenance lfone. Cleaned and Checked Relays Procedures-EHP-RT-01 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> .

Transformer (MR 51-014375) EHP-RT-07

.. .. -* . EMP-RT-12 '

11/12/76 EPH Circuit Breaker Preventative Maintenance None Dismantled, Cleaned, and *1 nspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ISG] (MR 51-014001) EMP-P-RT-12 11/12/76 EPH Bus .IA, 1B, and lC Preventative Maintenance None Performed Procedure EMP-RT-04 Procedure EMP-RT-04 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (MR 51-1-400) r

. ... ~ **-~'

ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MA.TOR ITEMS)

PAGE 3 of 5 Ulll T rrn. I 1Jn11i:w,i:o tQ SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN , TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

11/15/76 CH MOV-CH-1286A Disconnect and Reconnect None Disconnected and Reconnected Procedure EMP-C-MOV-11 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for Mechanical Dept. (MR Sl-014305) il/15/76 CH MOV-CH-1287A Disconnect and Reconnect None Disconnected and Reconnected Procedure EMP-C-HOV-11 I hour for Mechanical Dept. (HR Sl-014301)

, 11115176 EPH Circuit .Breaker Preventative /1aintenance None Dismantled, Cleaned, and Inspected N 15H10 Procedu res-EMP-P-E Pll-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> N (MR 51-014064) EMP-P-RT-18 I.,.)

111/15/76 EPH Ci rcul t Breaker 15H1 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR 51-014056) EMP-P-RT-13 11/15/76 EPH Circuit Breaker 15J3 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR 51-014067) EMP-P-RT-35 i,ir 11/15/76 EPH Circuit Breaker 15J8 Preventative Maintenance ,None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 IJours (MR 51-014071) EMP-P-RT-23A 11/15/76 EPH Circuit ~reaker 15H3 Preventative Maintenance.

None Dismantled, Cleaned, and Inspected

.*(MR S1-014057)

Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> EMP-P-RT-33 11 /15/76 EPH Circuit Breaker 15H8 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR 51-014062) EMP-P-RT-19A 11/15/76 EPH Circuit Breaker 15H11 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 houn (MR 51-014065) EMP-P-RT-17 11/17/76 VS 1-VS-F-lB Preventative 11aintenance None Inspected, Bridged, and llegge red Procedure EMP-C-EPL-40 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

... (MR 51-014019) 11/17/76 EPH Circuit Breaker 15H9 Preventative Maintenance tlone Dismantled, Cleaned, and Lnspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR 51-014163) EMP-P-RT-16 11/17/76 EPH Circuit Breaker 15J11 Preventative llaintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (11R 51-014074) EHP-P-RT-15

ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

UU IT tlO. I PAGE 4 of 5 NOVEMBER 19__16 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN , TIME REQ'D DATE INVOLVED CAUSE OF.THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR HAINT.

11/17/76 EPH Circuit Breaker 15J9 Preventative tla i ntenance None Dismantled, Cleaned, and Inspected Procedures-EHP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR 51-014072) EMP-P-RT-14 11/18/76 CL5 Relay CR-CL5-1A12 Inspect and Test tlone Installed New Relay Procedure EHP-C-RT-24 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR 51-006977) --*-

~11/18/76 CLS Relay CR-CL5-1A13 Inspect and Test tlone tnstal led flew Relay N Procedure EMP-C-RT-24 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

.i:,- (MR 51-006978)

I 11/18/76 EPH Circuit Breaker 15J10 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR S1-014073) EMP-P-RT-22 11/24/76 EPH Circuit Breaker 15D1 Preventative tlaintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I~'

(MR Sl-014082) EHP-P-RT-47 11/27/76 EPH Circuit Breaker 15F1 Preventative Maintenance None Dismantled, Cleaned, and Inspected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR Sl-014017) EMP-P-RT-49 11/27/76 EPH Circuit Breaker 15E1 Preventative Maintenance Hone

, Dismantled, Cleaned, and lf"!spected Procedures-EMP-P-EPH-43 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (MR Sl-014016) EMP-P-RT-48 0

11/29/76 FW HOV-FW-151B Preventative Maintenance

~

None Performed Procedure EMP-P-MOV-45 Procedure EMP-P-HOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR Sl-014290) 11/29/76 FW MOV-FW-151E Preventative Maintenance None Performed Procedure EHP-P-MOV-45 Procedure EMP-P-MOV-45 2 hours (MR 51-014297) 11/29/76 FW MOV-FW-151D Preventative Maintenance None Performed Procedure EMP-P-MOV-45 Procedure EHP-P-MOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR Sl-014296) 11/29/76 FW MOV-FW-15._!F Preventative Ila i ntenance None

.. .. Performed Procedure EMP-P-i~OV-45 Procedure EMP-P-MOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR 51-014298) 11/29/T6 FW MOV-FW-151A Preventative tlaintenance tlone erformed Procedure EIIP-P-IIOV-45 rocedure EMP-P-MOV-45 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (MR Sl-014289)

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ELECT~ICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

Ulll T 110. I Dl\~J: <; nf E; NOVEMBER 1q 6 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN, TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

11/29/76 EPCR Part Lengtn Control Disconnect and Reconnect Hone Disconnected and Reconnected Procedure EHP-C-EPCR-17 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Rod for Refueling (HR S1-013974)

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-ff~* * ,YM"',,.,-.IY',rjl'/ 6 R. E. N_I CHOl:LS, SUPERVISOR-ELECTRICA MAINTENANCE i

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• UUIT NO. 1 MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE DECEMBER, 1976

1. MAINTENANCE ORDERS COMPLETED NON-SAFETY RELATED ITEMS 80

2. MAINTENANCE ORDERS COIB.'LETED MAJOR OR SAFETY RELATED ITEMS 18 MONTHLY TOTAL 98

3. DESIGN CHANGES BEING WORKED. DC-76-33, 76-27, 75-44, 75-51, 76-31, 73-23, 73-29.

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4. PER10DIC TEST PERFORMED 8 (5) PT-34 (1) PT-23.1 (1) PT-27 (1) PT-31. 3

~OR

UNIT NO. 1 ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 2 DECEHBER 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEU TIME REQ'D DATE. INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

12-2-76 EPH Circuit Breaker Preventative Maintenance None Cleaned and inspected. MR-Sl-14066 EM'-P-EPH-43 2 hrs.

15J2 EMP-P-RT-32 12-2;..75 EPH Circuit Breaker Preventative llaintenance None Cleaned and inspected. MR-Sl-14052 EMP-P-EPH-43 3 hrs.

lSJS EMP-P-RT-26 12-13-76 EPH Circuit Breaker Preventative llaintenance None Cleaned and inspected. MR-Sl-14032 EMP-P-EPH-43 3 hrs.

15A3 EMP-P-RT-51 12-13-76 EPH Circuit Breaker. Preventative llaintenance None Cleaned and inspected. MR-Sl-14059 EMP-P-EPH-43 3 hrs.

15HS EMP-P-RT-25

,12-14-76 EPH Circuit Breaker Preventative Maintenance None Cleaned and inspected. HR-Sl-14060 EMP-P-EPH-43 3 hrs.

N N

15H6 EMP-P-RT-31

'i" EPCR Rod Drive Motor 16 hrs.

12-17-76 Preventative Maintenance None Cleaned, inspected and changed bearings EMP-C-EPCR-8 Generator Ill UR-Sl-14137 EMP-C-EPL-40 12-17-76 EPH Circuit Breaker Preventative Maintenance None Cleaned & inspected. UR-Sl-14041 EUP-P-EPH-43 4 hrs.

15B3 EMP-P-RT-53 12-17-76* EPH Circuit Breaker Preventative Maintenance None Cleaned & inspected. MR-Sl-14046 EMP-P-EPH-43 4 hrs.

15C3 EMP-P-RT-37 12-17-76 EPCR No. 2 Motor Gener- Preventative Maintenance None Cleaned & inspected. MR-Sl-13964 EMP-P-EPCR-34 2 hrs.

ator Circuit Breaker 12.:.17-76 EPCR No. 1 Motor Gener- Preventative Maintenance None Cleaned & inspected. l!R-Sl-13954 EMP-P-EPCR-34 2 hrs.

ator Circuit Breaker 12-17-76 EPH Circuit Breaker Preventative Uaintenance None Cleaned & inspected. }!R-Sl-14068 EMP-P-EPH-43 3 hrs.

15J4 EMP-P-RT,-30 12-17-76 EPCR Rod Drive Motor Preventative Maintenance None Cleaned, inspected & changed bearing *. EMP-P-EPCR-8 16 hrs.

Generator 112 MR,-Sl-14138 EMP-P-EPL-40

UNIT NO. 1 ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 2 of 2 DECEMBER 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DA,TE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

J.2-23-76 EPL Circuit Breaker Preventative Maintenance None Cleaned and inspected. MR-Sl-14734 EMP-P-EPL-42 2 hrs.

14H6 12-23-76 EPII Circuit Breaker Prevenative Maintenance None Cleaned and inspected. MR-Sl-14061 EMP-P-EPH-43 3 hrs.

15H7 EMP-P-RT-21 12-23-76 EPL Circuit Breaker Preventc,t:i ve Maintenance None, Cleaned and inspected. MR-Sl-14733 EMP-P-EPL-42 2 hrs.

14Hl 12-23-76 EPL Circuit Breaker Preventative tlaintenance None Cleaned and inspected. MR-Sl-14735 EMP-P-EPL-42 2 hrs.

14H10 12-29-76 EPCR CRDM Boric Acid Buildup None Disconnected and reconnected the CRDM's, EMP-P-EPCR-14 36 hrs.

EMP-P-EPCR-16 12-30-76 EPH Circuit Breaker Preventative Maintenance None Cleaned and inspected. MR-Sl-14058 EMP-P-EPH-43 3 hrs.

I 15H4 EMP-P-RT-20 N

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R* E. NilHOLLS, SUPERVISOR l ~ECTRICAL MAINTENANCE

ELECTRJCAL MAINTENANCE MONTHLY OPERATING REPORT UNIT NO. 2 JAUUARY 1 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor

• Time Req'd Involved Malfunction On Safe Operation To. Prevent Repetition Safety During Repair For Maint.

I N 2~ hrs.

N 1-2-76* Containment Radiation Pump indicating light None Reconnected wire MR-S2-5130 EMP-C-EPL-07 I.O Monitor GW-101 inoperative, loose I

wire.

1-3-76 Gland Steam Exhaust Motor Grounded None Replaced motor. MR-S2-4815 NA 1 hr.

Fan A 1-5-76 D Water Box Level switch full of None Drained water, and dried NA 3 hrs.

LS-VP-200E water contacts MR-S2-4664 1-6-76 Gia-tonics Unit 02 Defective speaker None Replaced speaker MR-S2:-5268 NA 1 3/4 hrs.

Containment Pers_onnel Hatch I

l-8-76 MOV-MS*202 Bolt missing. None Replaced missing bolt. NA 35 min.

MR-Sl-5129  ;

I 1-8-76 Slow speed indicating Loose connection on None Tightened loose connection. NA 2 hrs.  ;

light for 2-CH-P-2D light socket Auxiliary Shutdown  :

Panel 1-10-76 Auxiliary Boiler IJ2 Defective Start-Stop None Replaced Start-Stop switch NA 4 bra.  :

Transfer Pump switch MR-S2-4753 1-12-76 LS-VP-201 Magnetrol switch full None Cleaned switch and reinstalled. NA 4 hrs~

of mud and rust. MR-S2-5294 1*

. ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT 1

_!!NIT NO. 2 PAGE 2 JANUARY, 1976 1 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time*Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

1-12-76 LS-VP-204 Magnetrol switch full None Cleaned switch and reinstalled. NA 4 hrs.

of mud and rust. MR-S2-5293 l-13-76 Plant drinking water Control circuit dis- None Connected control circuit and NA 2 hrs.

chlorine pump connected checked manual and automatic operation. MR-S2-5282 Ground detection systei None Found shorted splice, removed NA 4 hrs. i I 1-17-76 Main Generator Ground  !

N Detector grounded. old tape and retaped. MR-S2-5168 I.,.)

0 I 1-17-76 Hydrogen seal filter Timers incorrectly set None Changed timer setting from SOX timers and wired wrong. to 2.5% changed contacts from NA 4 hrs.:

Run continuously N.O. to N.C. MR-S2-4916  ;

1-17-76* NRV-MS-201B Torque switch contacts None Cleaned torque switch- contacts NA 2 hra.- I

\

. dirty MR-S2-5327 I 1-19-76* 2-RC-P-lA None None Took oil samples from upper and NA. 2 hrs. II lower oil pots and cooler for lab analysis MR-S2-5165 119 76 * - --

2 RC P lB None None Took oil samples from upper and lower oil pots and cooler for NA 2 hril-..*

lab analysis. MR-S2-5166 1-19-76* 2-RC-P-lC None None Took oil samples from upper and NA 2 hrs.

lower 911 pots and cooler for lab analysis. MR-S2-5167 1-19-76* MOV-FW-251A None NOne Disconnected valve for mechanical EMP.i-C-MOV-11 5 hrs.

department reconnected and set limits. MR-S2-5169 1-20-76 Power Operated Relief Limit switch for open None Adjusted limit switch MR-S2-5345 NA 1 hr.

Valve RIJ-MS-201A indication out of adjustment.

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ELECTRICAL MAINTENANCE MON.T!ll.Y OPERATING REPORT UNIT NO. 2 PAGE 3 JANUARY 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved }o!alfunction On Safe Operation To Prevent Repetition Safety During Repair For Maine.

1-20-76* Safety Injection Valve. Defective heat tracing None Replaced heat tape MR-S2-5356 NA 1.5 hrs.

2-SI-9 1-20-76 Fire Water Alarms: Deluge pressure None Dried out deluge pressure switche1 NA 1 hr.

Fire Water System switches wet, I

initiate interior hose system, I

1-21-76 2-FW-P-lB Defective inboard None Replaced bearing. MR-52-5324 NA 15 hrs.

N w bearing I-'

I 1-23-76 Blowdown* Trip Valve Cam Switch for light None Adjusted cam switch MR-S2-5436 NA 1 hr.

TV-BD-200F indication out of adjustment.

(

1-23-76* NRV-MS-201B Defective torque None Replaced torque switch.MR-S2-5435 EMP-C-MOV-18 2 hrs. \,

switch 1-24-76* 2-VS-F-60C Motor bearings bad None Removed motor,replaced bearings, EMP-C-EPL-27 13,5 hrs.

reinstalled and tested. MR-S2-5181 1-24-'76* 2-VS-F-60F Motor bearings bad None Removed motor, replaced bearings, reinstalled and tested ?IR-S2-444 EMP-C-EPL-27 13.5 hrs.

1-25-76 2-SD-P-lB Motor stator shorted None Had motor rewound off-site, re-instaliled and tested. 11R-S2-5132 NA BO hrs.

1-26-76 Electrical Penetration Low Pressure on None Charged penetration to 12 PSIG NA 1 hr.

A-3 .penetration Intercom System, Defective intercom !lone *Replaced unit. MR-S2-5489 NA ~ hr.

1-30-76 Health Physics unit. unit.

R. E. NICHOLLS-SUbERVISOR ELECTRICAL MAINTE~ANCE

. ,, ,,. =' . . -

.ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT FEBRUARY, 1976 UNIT NO. 2*

I Results and Effect Corrective Action Taken Precautions Taken To Provide for Reactor

• J.te I System or Component Involved Cause of the Malfunction On Safe Operation To Prevent Repetition Safety During Repair Time Rcq

For Main,

~2-2-76 Heat Tracing Line Thermostat's out of None Readjusted thermostat's NA _l~ hrs.

\.,.)

N l-CH-245, 246 adjustment ./ MR-S2-5511 I

2-3-76 Turbine Trip Valves Limit switches out None Adjusted limi.t switches NA 1 hr.

SV-1, SV-3 adjustment MR-S2-5513 2-4-76 Charging Pump Motor None None Inspected motor and changed EMP-P-LU-28 5lf hrs.

2-CH-P-lA oil. MR-S2-55~9 2-4-76 Reactor Coolant Pump Motor 2-RC-P-lB None

.. None Took oil samples from oil pots and cooler,* test satisfactory.

NA 2~ hrs. I I

MR-S2-5558 2-5-76 Charging Pump Motor None None I' ,.** Inspected motor ~nd. :~hariried oil EMP-P-LU-28 2 hrs. i 2-CH-P-lC  :, MR-S2-5561 I

2-5-76 Charging Pump Motor None None *,tnspected motor and changed oil EMP-P-LU-28 111 hrs.  ;

2-CH-P-lB MR-S2-5560 I 2-6-76 Residual Heat Removal None None Inspected moto3: and changed oil EMl'-P-LU-28 *s hrs. l Motor 2-RH-P-lB MR-S2-5557 '

I 2-7-76 Component Cooling None None*i Inspected motor and changed oil EMP-P-LU-28 'I hrs. i Motor 2-CC-P-lD }ffi-S2-5563 2-7-76 I Shroud Cooling

• Defective motor / !, None Replaced motor MR-S2-5141 EMP-C-EPL-27 35 hrs.

2-VS-F-60B 2- 7-76 Component.Cooling Not\e None Inspected motor and changed oil EMP-P-LU-28 6 hrs.

I Motor 2-CC-P-lC MR-S2-5562 I' . . .

I I

ELECTRICAL MAINTENANCE MONTHLY OPERATING REPORT UNI:T NO, 2 PAGE 2 FEBRUARY, 1976 Precaution* Taken Tc Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety Du~ing Repair For Maint.

2-9-76 Main Steam Valve None None Disconnected for mechanical EMP-C-MOV-11 10 hrs.***

2-MS-NRV-201A maintenance, reconnected and tested satisfactory.flR-S2-5565 2-11-76 Main Steam Trip *Valve Limits out of adjust- None Adjusted limits and tested. EMP-C-MS-32 4 hrs.

2-TV-MS-201A ment ~IR-S2-5567 2-11-76 Charging Pump Breaker Tripped on time over- None Bridged, meggered and reset. NA 1~ hrs.

I Tested satisfactory.

N 2-CH-P-lA current I.,.) MR-S2-5674.

If 2-20-76 Refueling Water Floats not adjusted None Adjusted floats as per Design NA 3 hrs, Storage Tank according to Revision Change 74-1, MR-S2-5251 74-1 2-23-76 Heat Tracing System None None Performed PT-27 NA 8 hrs, PT-27

'j 2-26-76 Electrical Penetration Low Nitrogen pressure None Recharged penetration NA 10 min, A-3 MR-S2-5876 .

2-26-76 Electrical Penetration Low Nitrogen pressure None Recharged penetration NA 10 min, A-18 MR-S2-5875 2-29-76 Station Batteries None None Performed PT-23,1 NA 8 hrs.

PT-23.1 R. E. NICHOLLS - SUPEIIVISOR ELECTRICAL MAINTENANCI

ELECTRICAL ?!AI!-lTEll.MlCE (Safety Releated Systems* during Outage or Reduced Power Periods.)

.J!!i!:U.

MARCH 1976 PAGE 1 of 1 I'

Syste.~ or Component Results and Effect Precautions Taken for  ! '.!'ice R1:quir.,c

'.~ate Involved Cause of the Halfunction on Safe Operation Corrective Action Taken Reactor Safety I for :-ra::.:: c.

I '

w 3-8-76!I N

Electrical Penetra- Penetration appeared None Disconnected penetration and performed EMP-C-PE-35

+" 15 hrs.

I tion.17A for 2-RCP-lA to be overheating. insulation test, test satisfactory. EMP-C-PE-21 Reconnected penetration. MR-S2-5572

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ELECTRICAL IIAl?lTEUA?tCE /

(Other Safety Related Systel'ls and Major Items)

UNIT NO, 2 MARCH 1 1976 PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Ti::ie Rcqui:-.:

Date Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Rear.tor Safety for* ~!.1in t I

N (j.)

\Jl 3-19-76 2-SD-P-lB Upper Thrust Bearing None Replaced bearing, lfil.-S2-6045 N/A 15 hi:s I

defective

.3-31-71 Pressurizer Heater Defective Breakers None Replaced breaker #1 on panel Ul. Re- N/A 4 hrs, Breakers Panels ill & placed breaker US on panel #2. Tested,

1. 2 test satisfactory. MR*S2-6149

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• R, E* NICHOLLS.- SUPERVISOR ELI tTRICAL MAINTENANCE I

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ELECTRICAL HAUlTEllAllCE (Safety Releated Systems* during Outage or Reduced Power Periods.)

.!fil'!.2 APRIL, 1976 PAGE 1 of 1 I

Syste.~ or Component Results and Effect Precautions Taken for I Ti:le Requir'"d

)ate Involved Cause of the Halfunction on Safe Operation Corrective Action Taken Reactor Safety I for :-!ai;i c, I

4-7-76: Motor Operated Valve Motor grounded None Disassembled, cleaned and dried motor. EMP-C-MOV-19 16 hrs.

MOV-SW-206B Reassembled and tested. MR-S2-6192 I

4-22-71 Motor Operated Valve Defective Torque and None Replaced Torque and Limit Switch EMP-C-MOV-18 MOV-SW-202B 2 hrs~

Limit Switch Assembly Assembly. MR-S2-12067 l '.

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ELECTRICAL lfAillTEUA?fCE (Other Safety Related Systeris and Hajor Items)

.!lli!1...l APRIL, 1976 PAGE 1 of 1 System or Component Results. and Effect Precautions Taken for Time Requir.,d Date Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for !-!aint.

~-7-76 Motor Operated Valve Motor Grounded None Disassembled, cleaned and dried EMP-C-MOV-19 16 hrs.

N t.,.)

MOV-SW-206A motor. Reassembled and tested.

-..J MR-S2-006191 I

4-7-76 *Motor Operated Valve Motor Grounded None Disassembled, cleaned and dried EMP-c-MOv:..19 16 hrs.

MOV-SW-206B motor, Reassembled and tested.

MR-S2-006192 4-13-76 Motor Operated Valve Motor Grounded Hone Disassembled, cleaned and dried EMP-C-MOV-19 16 hrs.

MOV-CW-200A motor. Reassembled and tested.

MR-S2-005759 I

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R. E, NICHOLLS SUPERVISOR ELECTRICAL MAINT ENANCE j

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0 ELECTRICAL HAUlTElTAHCB (Safety Releated Systems* during Outage or Reduced Power Periods.)

.!llill._2 MAY, 1976 PAGE 1 of 2 System or Component Results and Effect Precautions Taken for Time Required

).ati! I Involved Cause of the llalfunction on Safe Operation Corrective Action Taken Reactor Safety for }!ai::ic.

I N 5-1-761 Pressurizer Heaters None None Perform preventative maintenance. NA I.,.)

00 I Control MR-S2-12234 I

5-6-76 Radiation Monitor Filter will not advance.

• None Cleaned and Lubricated. MR-S2-1238tl NA RM-259 5-6-76 Instrument Air None None Preventative Maintenance. MR-S2-12127 EMP-C-EPL-27 2-IA-C-2B 5-6-76 Ventilation 2-VS-F-3A None None Preventative Maintenance. MR-S2-12136 EMP-C-EPL-27 5-6-76 5-10-76 Ventilation 2-VS-F-3B Motor Operated Valve None None None None Preventative Maintenance. MR-S2-12137 Completed Design Change 75-43.

EMP-C-EPL-27 EMP-C-MDV-11 MOV-2275C MR-S2-12268

.5-10-7b -Electrical Penetration None None Preventative Maintenance

• Performed EMP-C-PE-21 Leak Test. MR-S2-12282

_ 5-10-76 Motor Operated Valve None None Completed Design Change 75-43. EMP-C-MOV-11 '

MOV-2275B MR-S2-12269 5-14-76 Feedwater MOV-251 A,B None None Disconnected, reconnected & tested for NA

&C Mechanical Department. HR-S2-12267 5-15-7~ Service Wate.c Leak through None Adjusted limi.t switches. MR-S2-12440 EMP-C-MOV-18

' MOV-SW-203A & B

ELECTRICAL HAUITEHA?JCE (Safety Releated Systems* during Outage or Reduced Power Periods.)

UNIT 2 MAY, 1976 PAGE 2 of 2

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'.=ta System or Component Involved Results and Effect Cause of the lfalfunction on Safe Operation Corrective Action Taken Precautions Taken for Reactor Safety Time Required for Maint.

I 5-15-76 Service Water Valve failed to operate None Checked limit switches, everything NA N I MOV-SW-206A & B remotely. appeared in order. Had Control Room w '

cycle valve. Tested satisfactorily.

'f,_,,_,l Service Water Limit Switches out of None MR-S2-12441 Adjusted lll!lit switches. MR-S2-12278 MOV-CS-201C adjustment.

5-18-7 Service *wate:i:: Limit switches out of Uone Adjusted limit switches. lffi-S2-122*75 NA MOv-cs-;rn1n adjustment.

5-21-7 Containment Spray Limit switches out of None Adjusted limit switches. lffi-S0-12277 NA MOV-CS-201B adjustment.

5-21-7 Containment Spray Check adjustment of None Adjusted limit switches. MR=S2-12276 NA MOV-CS-201A Limit switch.

MAINTENANCE

• *ELECTRICAL HAI}lTmWlCE (Safety Related* Systems* during Outage or Reduced Power Periods.)

UIUT /12 i

JUNE, 1976 f PAGE 1 of 1 I'"' :

Syste.~ or Comp~nent Results and Effect Precautions Taken for Time Required Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for Maint.

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,6-3-76 I Main Steam Trip Valve Valve indicates inter- Hone Replaced snap lock switch, Adjusted NA NA

! TV-MS-ZOlB mediate position when for proper indication, MR-S2-12087

?J shut, ..

.] 6-3-76 HOV-RS-255A &*B Design Change 44 None Disconnect & reconnected motor for Design Change 75-44, ?fil-S2-12297 DC 75-44 NA 16-7-76 MOV-CS-202B Faulty return spring Hone Replaced torque limit switch, lffi-S2-12661 EMP-C-MOV-18 NA 6-8-76 BR-P-4B llater Leaking into motor None Replaced motor, MR-S2-4990 EMP-C-EPL-27 NA

ELECTRICAL IIAIIITEHAHCE (Other Safety Related Systeris *nnd Hajor Items)

UNIT NO, 2 JULY, 1976 System or Component Results and Effect Precautions Taken for Time Required'.

!)ate* Involved Cause of the ?!alfunction on Safe Operation Corrective Action Taken Reactor Safety for ~laint, 76 CH Heat Tracing Defective Heat Tape None Replaced 8 ft, Heat Tape, MR No. S2- EMP-C-HT-20 10 Hrs.

l-CH-Bl-1, Ckt. 23B, 012839.

Panel 8 76 ClH Heat Tracing Defective Heat Tape None Replaced 15 ft. Heat Tape, MR No, S2- EMP-C-HT-20 2-CH-358, Panel II 6 Hrs.

012875.

7-30-76 S.I. Heat Tracing, Panel Defective Heat Tape None Replaced Heat Tape, MR No. 62-012929. EMP-C-HT-20 8 Hrs.

11, Circuit 1A 7-30-76 CH Heat Tracing, 1-CH- Defective Heat Tape None *Replaced 14 ft, Heat Tape, MR No. S2- F.MP-C-HT-20 6 Hrs.

230, Circuit 5, Panel 8 012926.

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• • • • i' R. E.Nichols,Supervisor

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Electrical Maintenance

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ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS) r U,M.A.A_&&.11...,6"' ... .,.""

SYSTEM OR COMPONENT RESULTS A.""D EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

J 9-3-76 Emergency Diesel #2 Battery cell blew. None Replaced battery check out battery EMP-C-EPDC-22 12 hrs.

charger. m-sl-13223 9-16-76 Main Gnerator Protection KD-41 Relay out of None Adjusted KD-41 Relay. llll-Sl-13206 EMP-P-RT-02 2 hrs, System adjustment, I

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R. E. NICHO .LS, SUPERVISOR-ELECTRICAL MAINTEUANCE

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ELECTRICAL MAINTENANCE (Other Safety :Related Systems and lfajor Iteos)

UNIT NO. 2 AUGUST, 1976 PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Time Required

!late Involved Cause of the lfalfunction on Safe Operation Corrective Action Taken Reactor Safety for }'.aint.

S-l1-7ii Emergency Diesel D2 Defective louver None Replaced louver control. .MR-S2-6093 EMP-C-EE-31 6 hrs.

I control.

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\,l.\\'\... ".,,..)., .0.J

. R.E. HICHO'nS, SU ERVISOR - ELECTRICAL MAINTEli I\NCB

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. ELECTRICAL MAINTENANCB

{OTHER SAFETY RELATED .SYSTEMS AND MAJOR ITEMS)

PAGE 1 of I UIIIT 110. 11 Nll\1~*1A~C'R 1Q Ft.

SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN. TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

11/30/76 Heat Tracing Panel 10 and Defective lleat T;ipe tlone Rep.laced Defective lleat Tape Procedure EIIP-C-HT-20 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 11 Circuit 4 (MR S2-:-013633)

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R, E, NICHOLLS, SUPERVISOR - ELECTRICA MAINTENANCE

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• UNIT NO~ 2 MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE DECEHBER, 1976

1. MAINTENANCE ORDERS COHPLETED NON-SAFETY RELATED ITEMS 39

2. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 6 MONTHLY TOTAL 45.

3. DESIGN CHANGES BEING WORKED._._ _n_c-_7_3_-_8_9_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

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4. PERIODIC TEST PERFORMED 6 (4) PT-34 (1) PT-23.1 (1) PT-27

UNIT NO. 2 ELECTRICAL MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 DECEl!BER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED CAUSE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

12-1-76 CLS BFD 445 Relay . Coil failed. None Replaced defective relay. MR-S2-13543 EMP-C-RT-24 4 hrs.

12-1-76 Heat Tracing Panel 8 Heat tape failed. None Replaced 10 ft. heat tape. t!R,-S 2-136 35 EMP-C-HT-20 6 hrs.

Circuit 5 12-~-76 Heat Tracing Panel 10 & Valve leaked, causing None Replaced 44 ft. heat tape. 11R-S2-13636 EMP-C-HT-20 10 hrs.

11, Circuit 1 heat tape failure.

12-17-76 Heat Tracing for line Valve leaked, causing None Replaced 1 ft. heat tape. MR-S2-13793 EMP-C-HT-20 hrs.

2 2-CH-358 heat tape failure.

12-28-76 Heat Tracing Panel 8 &9, Heat tape failed. None Replaced 17 ft. heat tape. MR-S2-13434 EMP-C-HT-20 6 hrs.

Circuit 21D 12-28-76 Heat Tracing on Emergency Leak in line, caused None P..eplaced 12 ft. heat tape. MR-S2-l 3689 EMP-C-HT-20 8 hrs.

I Borate Line heat tape failure.

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°'I T.E-:-;'lICH£~LECTRlCAL MA NTENANCE

INSTRUMENT MAINTENANCE SURRY POWER STATION UNIT NO, 1 JANU_ARY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

1-20-76 Steam Flow Multiplier Electronic component Caused an error in steam flow Replaced module with a spare Placed channel in Test. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Divider FM-1-485 failure of~ 32,000 LB/HR. unit, calibrated to proper Used approved procedure I values and returned to service, Redundant instruments N

_p.. normal, I

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IllSTRmmUT MAINTE11AlmE (Other Safety Related Systems and l1ajor Items)

}iARCH 1976 UNIT NO. 1 PAGE 1 of 1 System or Component Results and Effect Precautions Taken for Time Require::

!late Involved Cause of the Malfunction on Safe Operation Corrective Action Taken Reactor Safety for !-!.air:t.

I 03-15-76 Containment Inst. Bl & B2 Pressure switche, Safe operation Adjusted pressure switches to proper Reactor at cold shutdown. 2 hrs.

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.p.. Air Compressors had slipped setpoint not adversely setpoint. Checked for proper operatipn. Used approved procedures.

(X)

I affected. Returned to service.

3-16-76 Residual Heat Removal Element failure Safe operation Replaced RTD with one from spare parts. Reactor at cold shutdown. 2 hrs.

System RHR Pump Disch. not adversely Checked for .proper operation. Returned Used approved procedures.

Temp. RTD. T-1-604. affected. to service.

3-22-76 "B" Feedwater Reg. Positioner Feedback Would have causec Replaced linkage Maintained steady state 1 hr.

Valve FCV-1488 Linkage became discon- reactor trip on conditions during repair.

nected from valve due S/G.if unit con- Alerted shift supervisor to vibration. ditions had cal- and reactor operator of led for a change conditions.

in valve positior.

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D1STRU?IBUT MAINTEllANCE (Other Safety Related Systems and I1ajor Items)

. APRIL, 1976 UNIT 1 PAGE 1 of 1 System or Co~ponent Results and Effect Precautions Taken for T:il:le RequireC:

!late Involved Cause of the ?1alfunction on Safe Operation Corrective Action Taken Reactor Safety for :l-!aint.

I N 4-2-76 Incore Moveable Flux Detector failed Reactor Safety Replaced detectors with spare units. Used approved procedures. 5 hrs,

.i:- Detectors D& E internally

• not affected.

'°I 4-5-76 I Reactor Coolant Temp Electronic failure Reactor Safety 'Replaced Low Level Amplifier with Used approved procedures. 1 hr, Control Loop "B" output failed low. not affected. spare unit. Calibrated and returned Redundant channels normal.

TM-l-421A Low Level to service.

Amplifier.

4-12-76 Feedwater Control Suspect dirty contacts Reactor Safety Submitted M.O. Sl-007540 to Elect.rical Reactor at shutdown con- 2 hrs Transmitter Selector or internal switch not affected. Dept. Switch was replaced 4-30-76. ditions during switch Switch 1/FM-1/498B defect. Switch caused replacement on 4-30-76.

Defective. mismatch between actual flow and flow error signal when se1ecting the alternate flow transmitter.

4-15-76 N-44 Overpower Trip Electronic Drift, Reactor Safety Adjusted to proper trip and reset Used approved procedures; l ilr, Bistable S.P. 1% high. not impaired. setpoint~ 107% and 105% respectively *. 3 redundant. channels.in 2/4 required for service and operating Reactor trip, normally.

• 4-29-76 N-44 Overpower Trip Electronic Drift. Reactor Safety Replaced bistable card with spare unit Used approved procedures, 1 hr, Bistable S. P. drifted not impaired. adjusted to proper setpoint and re- 3 redundant channels in 1.5% high. 2/4 required for turned to service. service and operating Reactor trip. normally,

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lllSTRUllE!JT MAUITEllAHCE (Othr.r Snfety !!<'lnted Systems and YlajClr Iter.is)

JUNE, 1976

• UlUT HO. 1 Pae 1 of 1 Syste~ or Co~ponent Results and Effect Precautions Taken for Tioe Re~ui

Oato Involved Cause of the J!alfunction on Safe Operation Corrective Action Taken Reactor Safety for }'.ai I

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I 6-10-76 1{-42 High Range and Electronic Drift The high range Replaced both bistable printed circuit Used approved procedures. 1 hi; Overpower Rod Stop trip and overpower cards, calibrated. Checked for proper Placed channel in test.

Bistable P.C. 's rod stop would operation and returned to service. Redundant instruments in have operated at service & operating the proper set- normally.

point, but both were capable of immediate reset rather than the normal 2%

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UISTRIDIEUT MADITEUAHCE (Other Safety TIPlated Systems end ltejor !terns}

UNIT NO. 1 JULY, 1976 Syste::i or Co::iponent Results and Effect Precautions Taken for Tir.c: Rc:c;:.:i *

!:ivolved Cause of the I!alfunction on Safe Operation Corrective Action Taken Reactor Safety for }!a.1 I

N7-ll-7E Rx Protection Relay Electrical Coil failure Partial Rx Trip Relay was replaced by Electrical Dept, Rx Protection Train "B" 5:-1/2 hrs.

l..n signal r' 272XP Bypass breaker was inserted I during replacement of relay and returned to normal following repairs.

Used approved procedures.

7-15-71 NIS (P-6) Bistable Electronic Drift Would have ener- Adjusted to proper trip and reset.points. Placed channel in test. 1/2 hr, card. N-35 detector gized source ran- Returned to service. Used approved procedures.

ge detectors .05 decade early at

, 5.5x10-ll rather than 5x10-11.

7-16-71 N-42 High Voltage Electronic Drift Causing bistable Replaced power* supply with station spare Channel in test. Used 3 hrs, Power Supply and Electrical noise. setpointe to unit, Checked for proper alignment & approved procedures.

drift. operation. Returned to service Redundant channels operating normally.

7-17-Jt F-962 Safety Injection Electronic Component Indicating flow Replaced P.C. board with spare unit, Cold Leg Flow Loop "B" failure *. with no flow co~- Caibrated transmitter and returned Used approved procedures. 2 hrs.

ditions. to service. Rx at cold shutdown conditions.

AUGUST 2 1976

• INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS Mm MAJOR ITEMS)

PAGE 1 of 1 UNIT NO. 1 DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D I?-.'VOLVED CAUSE OF THE MALFUNCTION ON:SAFE OPERATION CORRECTIVE ACTION TAKEN

• FOR REACTOR SAFETY FOR MAINT.

Z-16-76 i.US Setpoint too close*to Uoved setpoint away Completed SP-76-7. Changed Low Reactor shutdown. Used 2 hrs, Tech. Specs. from T.S in conserva- Level Trip from 25% to 23%, approved procedures.

tive direction.

8-18-76 NIS -Dropped rod bistable Allows larger changes Completed DC-76-8. Changed time Reactor shutdown. Used 4 hrs.

tripping during load in load with respect constant in rod drop circuit from approved procedures.

{ changes. to time without trip- 5 seconds to 2 seconds.

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l...!1 ping dropped rod 1  !

bistable, a-JJ-76 RWST Level Tr811!Smitter Electronic drift. Redundant instruments Calibrated transmitter and checked Used approved procedures. 2 hrs.

LT-CS-lOOB did not agree. for proper operation. Redundant instrument

~ LT-CS-lOOB was read- operating normally.

l ing 1.25% high, 8-31-76 Ul Emergency Diesel Hi Temp Alarm set to Sporadic alarms. Reset Hi Temp Alarm from 200°F to Insured both 02 & D3 6 hrs.

high. 190°F. (Eng. Study 76-09). diesels *are operational and in service.

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UNIT NO. 1 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 SEPTEtIBER, 1976 DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS '!'AKEN TIME REQ 1 D INVOLVED CAUSE OF THE MALFUNCTION ON :SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

9-11-76 Reactor Protection Logic Coil failure Had one channel of Assisted Electrical Dept. in re- Placed reactor trip 4 hrs.

Reactor Coolant Pump "B" reactor trip locked placing relay. Completed PT. & bypass breaker in service undervoltage relay. in. returned to service, while replacing relay, 9-23-76 Reactor Coolant Temp. Electronic Drift Out of calibration. Replaced comparator, checked for Placed channel in test. 1 hr.

Temp. Comparator TC-l-412B 25UV in conservative proper operation and returned to Used approved procedure.

I Output ;/2 O.P. Rod Stop. direction, service. Redundant channels opera-N ting normally.

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I 9-23-76 Reactor Coolant Temp. Electronic Drift Received one channel Replaced*comparator, checked for Placed channel in test. 1 hr.

Comparator TC-l-412B of delta T, proper operation, Returned to Used approved procedures.

Output #1 failed to Reactor trip.

• service. Redundant channels de-enereized state. operating normally.

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• I' UMIT NO. 1 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

Page 1 of 1 OCTOBER, 1976 DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D U.'VOLVED CAUSE OF TUE MALFUNCTION ON -SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

10-4-76 eves Boric Acid Tank Level Electronic Drift Indicated level was Calibrated transmitter, checked for Used approved procedures. 1 hr.

Transmitter LT-1-161 Tank 5.63% high. proper operation & returned to Redundant channel in "A" Channel II service. service, 10-4-76 eves Boric Acid Tank Level Electronic Drift Indicated level was Calibrated transmitter, checked for Used approved procedure& l hr.

Transmitter LT-1-108 Tank 2.63,( high. proper operation & returned to I "B" Channel I service, N

V1 f 10-17-71 First Stage Press, Trans- Electronic Drift Would have energized Calibrated transmitter. Checked loop Used approved procedures 1 hr.

mitter PT-1-446 Channel turbine runback 1% for proper operation, Returned to Reactor at refueling III. early. (conservative) service, shutdown.

10-18-71 Steam Header Press, Trans- Electronic Drift Transmitter output Calibrated transmitter, Checked loop_ Used approved procedures 1 hr; mitter PT-1-464 Channel was 1. 25,( high, for proper operation, Returned to Reactor at refueling IV (conservative) service. shutdown.

10-18-71 Steam Line Press. Trans- Electronic Drift Transmitter output Calibrated tvansmitter, Checked for Used approved procedures 1 hr, mitter PT-1-474 Channel was 1% low (conserva- proper operation. Returned to ser- Reactor at refueling II tive) vice, shutdown.

10-18-7* Steam Line Press, Trans- Electronic Drift Transmitter output Calibrated transmitter, Checked Used approved procedures l hr.

mitter PT-1-494 Channel 2.5% low (conserva- loop for proper operation, Returned Reactor at refueling II tive) to service. shutdown.

Electronic Drift Transmitter output Calibrated transmitter. Checked Used approved procedures 2 hrs, 10-21-71 Steam Generator Level Transmitter Channel II 1% low (conservative loop for proper operation, Returned Redundant transmitters LT-1-475 on Low Level Trip), to service. operating normally.

Unconservative on Reactor at refueling High Level Trip, shutdown.

UNIT NO. 1 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MA.lO!l ITEMS)

NOVEMBER, 1976

-~*=="P"'A"'GaaaE,==l=co"-f"'l.,._.~=~=~~~~~'l""'=~-==~-~~~~.,.,,,====~======;===~==~=""-"==~~==-=~~~=,p~=-~~~~-~=~~--~=-~~=

SYSTEM OR COMPONENT RESULTS AL~D EFFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE INVOLVED CAUSE OF THE MALFUNCTION ON :SAFE OPERATION CORRECTIVE ACTION TAKEN

• FOR REACTOR' SAFETY FOR MAINT.

11-1-76 Rx Coolant Temp Protection Electronic Failure Channel 3 OTL'iT Replaced power supply capacitors, Placed Channel in test. 2 hrs.

Temp. Comparator (dual) reactor trip and bench checked for proper operation, Used approved procedures.

TC-l-432C would not trip. OTL'iT Rod Stop/Turbine installed in system, calibrated and Redundant Channels in Runbock were rendered checked for proper operation. service and operating inoperable. properly. ,

Reactor at refueling shutdown.

• 11-11-76 Pressurizer Level Electronic Drift High level Rx trip Calibrated transmitter for proper Placed channel in test. 2 hrs.

Transmitter L-460 reading channel 2 would have output, checked for proper operation, Used approved procedure1

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• 575% low. occunred .075% high- returned to service

• Redundant channels in

~ er than the redundant service and normal.

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1, channels. Reactor at refueling \*

shutdown.

HONTHLY OPERATING SUPPLEMENT SHEET INSTRU11ENT MAINTENANCE DECEUJ3ER, 1976

1. MAINTENANCE ORDERS COMPLETED MAJOR OR SAFETY RELATED ITEMS 6 MONTHLY TOTAL 101 2, DESIGN CHANGES BEING WORKED DC-73-23 (Accumulator Level) DC-76-31 (S/G Blowdown)

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I SUPERVISOR  !

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UNIT NO. 1 INSTRUMENT Mi\INTENANCE (OTIIER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

DECEMBER, 1976 SYSTDI OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ'D DATE INVOLVED ICAUSE OF THE HALFUNCTION ON :SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

• 1 2-20-76 Reactor Coolant Temp. Electronic spiking Erroneous 6T Replaced module with spare & Reactor at refueling 1 hr.

Low Level Amplifier indication returned to service following shutdown. Placed TM-l-412H. calibration. channel in test.

Used approved procedures 12-29-76 Radiation Monitoring Power failure to filter Filter paper would not Replaced lead between TB-1 and K-3 Used approved procedures 1 hr.

Particulate Detector advance mechanism due to advance. advance timer. Checked for proper Reactor at refueling.

R.L'IS-159 broken wire. operation. Returned to service. shutdown.

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INSTRill1ENT HAINTENANCE SURRY POWER STATION

.JANUARY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'd Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maine. .

1-14-76 Power Range Neutron High v*oltage Power Power supply failure caused Replaced high voltage power Placed channel in test. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Detector N-43 Supply failed low. nuclear signal to drop to zero, supply with a new unit. Used approved procedures.

I exceeding the rate of change Redundant channels in N

Vl bistable which initiated a service and normal co turbine runback.

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INSTRUMENT MAINTENANCE SURRY POWER STATION UNIT NO, 2 FZBRUARY, 1976 Precautions Taken To Date System or Component Cause of the Results and Effect Corrective Action Taken Provide for Reactor Time Req'J Involved Malfunction On Safe Operation To Prevent Repetition Safety During Repair For Maint.

2-4-76 Steam Flow Multiplier Electronic Drift Low Steam Flow Indication 'on Replaced module with spare unit. Placed Channel in test. 1 hr, I Divider FM-2-494 180 MV Low Channel 3 Protection'in the Calibrated and returned to Used approved procedures.

N V, Amount of 198,000 PPH service. Redundant Instruments

\D Performing Normally I

2-18-76 O,T,S.P, Drifted Electronic Drift 9.07% Drift in unconservative ,Replaced Summator with a Spare Placed Channel in Test, 1 hr, 1 High, TM-2-432F direction would have initiated Module. Calibrated &*returned Used approved procedures, Overtemperature an Overtemp, Trip Signal la.te, to Service, Redundant Instruments Setpoint SullllDator .. Performing Normally

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IUSTRUllE!IT MAINTE!1AHCE (Other Safety Related Systems and Uajor Items)

MARCH 1976 UNIT NO. 2 PAGE 1 of 2 System or Compo~ent Results and Effect Precautions Taken for Time Requirec

!late Involved Cause of the ?talfunction on Safe Operation Corrective Action Taken Reactor Safety for !fair.:.

3-6-76 R.C. Temp Test Switch Excessive contact. Would have gener- Replaced switch with a spare. Checked Reactor at shutdown con- 2 hrs.

I N CT-2-432H. Th Test Resistance, causing O.T. ated Rx O.T. TriF for proper operation, dition, Used approved Q'\ Switch S.P. to read= 1% high. Signal 1% late, procedures. Redundant 0

I channels normal.

3-25-76 Protection Channel IV Electronic drift 26 HV Would have causec Calibrated summator, checked for proper Used approved procedures. 1 hr.

First Stage Pressure in unconservative direc- Iii Steam Flow operation and returned to service. Channel in test.

Summator PM-2-447-B tion. Comparators to trip .15% late.

3-30-76 N-42 Overpower Rod Electronic drift set- Would have gener Calibrated bistable to proper setpoint Channel in test. Used 1/2 hr.

Stop Setpoint, point was tripping and ated overpower checked for proper operation and re- approved procedures, resetting ,5% high, rod stop signal turned to service. Redundant channels normal.

.5% late *.

3-:-30-76 P-2-484 Steam Line Electronic Drift. 36 l!V Would have cause1 Calibrated transmitter. Channel in teat. Used 1/2 hr.

Pressure Transmitter. Low. reactor trip sig- approved procedures, nal at 90.PSI rather than 100 PSI 3-30-76 P-2-485 Steam Line Electronic drift. Zero Would have cause< Calibrated transmitter. Channel in test, Used 1/2 hr, Pressure Transmitter was 25 MV,low, span:.l~ reactor t*rip sig approved procedures.

MV low. nal at 96 PSI rather than 100 .

PSI.

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IllSTRtn!EUT MAINTEltA?mE (Other Safety Related Systems and Hajor Items)

MARCH, 1976 UNIT NO, 2 PAGE 2 of 2 System or Component Results and Effect Precautions Taken for Time RequireC:

!late Involved Cause of the Ualfunction on Safe Operation Corrective Action Taken Reactor Safety for :i.:aint.

3-30-76 P-2-496 Steam Line Electronic Drift , Zero Would have caused Calibrated transmitter, Channel in test, Used 1/-2 hr.

I Pressure Transmitter 87 MV low, span 18MV Rx trip si~nal approved procedures, low, at 78,3 rather than 100 PSI.

I P-2-476 Steam Line Electronic drift 36 Would have caused Calibrated transmitter. Channel in test. Used 1/2 hr. '

3-30-76 Pressure Transmitter MV low zero, Rx trip signal at appr*oved procedures. l.

90 rather than 100 PSI, 3-30-76 P-2-486 Steam Line Electronie .drift 43 MV Would.have caused Calibrated transmitter

• Channel in teat, Used 1/2 hr.

Pressure Transmitter low zero. Rx trip signal at approved procedures.

89 rather than 100 PSI.

3-30-76 P-2-447 First Stage Electronic drift 27 P > would_ have Calibrated transmitter Channel in test. -Used 1/2 hr.

Pressure Transmitter MV low zero tripped at 10,6% approved procedures, rather than 10%

and turbine run-back would trip I

at 70.5% rather than 70%. I i

I?lSTRUME!lT MAINTENAUCE (Safety !telnte<l Systemd during Outaee or !I.educed Power Periods.)

MARCH, 1976 UNIT NO. 2 PAGE 1 of 1

System or Component Results and Effect Precautions Taken for Time Required

_ ._,c_e~-r'~~~~I_n_v_o_l_v_e_d~~~~-t-C_a_u_s_e~o_f~t_h_e~l_1a_l~fu_n~c_t_i_o_ni-o_n~S_a_f_e~O~p~e_r_a_t_i_o_n...;_-t-~~~~~C=o=r=r=e=c=t=i~v=e::....:A~c::.:.ti~o~n:.:....~T~a=k~e~n:......~~~~l--~R::.:.ea:..::.c=t=o=r...:::S=a~f=e=t~y~~~~~-+-~--=f=o~r_.:N~ai=n~t~.:__-

\ Channel in test, Used 6 hrs.

3-lu-76 Reactor Coolant Flow. Plugging of tubes in Low flow in- Restored unit operation, lowered Rx 1 Transmitters F-434, "C" Steam Generator dication resultec trip SP to 90% from conservative approved procedures.

I

.N & 436, resulted in loss of in reactor trip. sctpoint of 92%. Returned to 100% flow O"I

.N D.P. at 100% RC flow conditions, measured actual D.P.,

I conditions. calculated new 120% D.P. compared with original flow data to insure minimum PPH coolant flow calculations had not been exceeded, Calibrated transmittere, returned to service.

Returned Rx flow trip S.P. to con-servative 92%. .\

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IIISTRtnlE!IT MAUITEIIAHCE (Other Sn fety '.!C'lnted Systems nnd Jlnjc>T Iter.1s)

UNIT 2 MAY 1976 PAGE 1 of 2 Systen or Co::iponent Results and Effect Precautions Taken for !ir.c: Rc:~*.;i:

~ata Involved Cause of the l!alfunction on Safe Operation Corrective Action Taken Reactor Safety for ~'.ai

• I N

O'\ 5-1-76 "A" Steam Gen. Level Electronic Drift Indicated level Calibrated Transmitter & returned to Used approved procedures. 1 hr.

~ Xmtr. LT 474 1. 75% low !lervice. Reactor at Cold Shutdown.

5-1-76 "A" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transmitter & returned to Used approved procedures. 1 hr.

Xmtr. LT 475 2.5% Low service. Reactor at Cold Shutdown.

5-1-76 "A" Steam Gen. Level Electronic Drift Indicated Level Caiibrated Transmitter & returned to Used approved procedures. l hr.

Xmtr. LT-476 3.8% high service. Reactor at Cold Shutdown.

5-1-76 "B" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transmitter .. & 111eturned to _Used approved procedures. 1 hr.

Xmtr. LT-484 5.4% Low service. Reactor at Cold Shutdown.

5-1-76 "B" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transmitter & returned to Used approved procedures. 1 hr.

Xmtr *. LT-485 9.9% Low service. Re~ctor at Cold Shutdown.

5-1-76 "B" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transcitter & returned to Used approved procedures. 1 hr.

Xmtr. LT-486 7 .1~1 Low service. Reactor at Cold Shutdown.

5-1-76 "C" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transmitter & returned to Used approved procedures. 1 hr, Xmtr. LT-494 2.3% Low service. Reactor at Cold Shutdown.

5-1-76 "C" Steam Gen. Level Electronic Drift Indicate4 Level Calibrated Transmitter & returned to Used approved procedures. 1 hr.

Xmtr. LT-495 5.45% Low service. Reactor at Cold Shutdown.

5-1-76 "c" Steam Gen. Level Electronic Drift Indicated Level Calibrated Transmitter & returned to Used approved procedures. 1 hr.

Xmtr *. LT-496 2.5% Low service. Reactor at Cold Shutdown.

-, I . ' - ... . -. ~

• I' I!ISTRU?m!IT MAUJTEIIAHCE (Other Snfety :':.c*lated Sylltems and llajor Itel!ls)

MAY, 1976 PAGE 2 of 2 Sys:e::i or Co::r;:,or.ent Results and Effect Precautions Taken for !be' Rec;:;:

~ata Involved Cause of the 11.ilfunction on Safe Operation Corrective Action Taken Reactor Safety for ~:ai I

N 5-1-76 "B" Steam Flow Electronic Drift Indicated steam Calibrated transmitter & returned to Used approved procedures, ihr:

Cl'\

+" Xmtr. FT-484 flow 1% high service, Reactor at Cold Shutdown, I

5-4-76 Pressurizer Level Electronic Drift Indicated level Calibrated transmitter & returned to Used approved procedures. 1 hr,* ..

Xmtr. LT-2-459 3.4% Low service; Reactor at Cold Shutdown.

5-4-76 Pressurizer Level Electronic Drift Indicated level Calibrated transmitter & returned to Used approved procedures. 1 hr, ,...

Xmtr. LT-2-460 2% Low service, Reactor at Cold Shutdown, I 5-4-76 Pressurizer Level Electronic Drift Indicated Level Calibrated transmitter & returned to Used approved procedures, 1 hr, Xmtr. LT-2-461 2.7% Low service, Reactor at Cold Shutdown, 5-8-76 Protection Channel I Electronic Drift Indicated Level Calibrated transmitter & returned to Used approved procedures. 1 hr, Pressurizer Press, 1.2% High service. Reactor at Cold Shutdown, PT-455 5-10-7) Safety Injection Press. Electronic Drift Indicated Press, Calibrated transmitter & returned to Used approved procedures, 1 hr, Xmtr. PT-923 was 7.8 lb High. service, Reactor at Cold Shutdown.

5-10-7 Safety Injection Press Electronic Drift Indicated Press, Calibrated transmitter & returned to Used approved procedures, 1 hr.

Xmtr. PT-925 was 9.6 lb Low service, Reactor at Cold.Shutdown.

lllSTRtnlE!IT MAUITEllAHCE (Other Safety '.':c*lated Systems and !lajor lteris)

JillIB, 1976 UHIT HO. 2 S::ste::i o?: Co:;iponent Results and Effect Precautions Taken for Tioe Re~:.::

Involved Cause of the llalfunction on Safe Operation Corrective Action Taken Reactor Safety for !-~i I

N

~ 6-29-761 Reactor Coolant Electronic Drift Alarm was being Calibrated comparator to proper tr~p Used approved procedures. 1 hr.

I Temperature high Delta T actuated 1.4% low point. Checked for proper operation Placed channel in test.

Alarm Comparator at 100.6 rather and returned to service.

TC-2-432A than norI'.181 102% Submitted lfil-S2-012840, requesting (conservative) an increase in ventilation to the process protection relay room.

• ,;,. L

1!1STRtnffillT MAI?lTEUAlfCE (Other Safety rrelated Systems and !fajor Items)

UNIT NO. 2 JULY, 1976 Syste:'.I or Co::iponent

~.3to I Involved Results and Effect Cause of the !lalfunction on Safe Operation Corrective Action Taken Precautions Taken for Reactor Safety

~i:::le Rec;:u::

for !-~!

Pressure switch for Mechanical failure of Caused motor on Replaced defective switch.with a spare Used approved procedures. .1 hr.

U2 Emergency Diesel switch air compressor unit. Adjusted to proper operation. Redundant diesel operating Pneumatic start air to relay out on Returned to service. normally.

System thermal overload because of contact chatter at start setpoint

• .~

NIS N43A Overpower Electronic Noise. None, card was Replaced card Uo. 636 with spare unit Used approved procedures. 2 hrs.

Rod Stop Bistable still functional. No. 0541, Checked for proper operation Placed channel in test.

Card NC 302 and returned to service.

7-27-7 Pressure switch for Mechanical failure. Caused motor on Replaced defective switch with a spare Used approved procedures. 1 hr.

U3 Emergency Diesel of switch. Air Compressor unit, Adjusted to proper setpoints Redundant diesel operating Pneumatic Start Air to relay out on checked for proper operation. Returned noX'!llally, System, thenaal overload to service, because of contac chatter at start setpoint.

7-30-7 N-32 Source Range Electronic failure. Only one oper- Replaced defective power supply with . Used approved procedures. hrs.

Nuclear Detector able source new unit. Calibrated detector and Placed channel in test.

High Voltage Power range detector. returned to service. Redundant instruments Supply failed, operating normally.

AUGUST, 1976 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 UNIT NO. 2

.~

DATE SYSTEM OR COMPONENT RESULTS AND EFli'ECT PRECAUTIONS TAKEN TIME REQ'D INVOLVED CAUSE OF THE MALFUNCTION ON :SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAIN'I.

. 7-31-76 rns Setpoint too close to Hoved setpoint away Completed SP-76-7, Changed Low Reactor shutdown. 2 hrs.

Tech. Spec, limit. from T.S. limit in Level Trip from 25% to 23%. Used approved procedures,

'. conservative direc-tion.

I N

O"\

-..J I

1, t

i I

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i I

l I*

• • \ . I' tnUT NO. 2 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

SEPTfilIBER, 1976 PAGE 1 of 1 DATE SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ I D INVOLVED CAUSE OF THE MALFUNCTION ON :SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT.

":'-=-===='1'~=~==~=======+===~====~===+===========+=-=======""""""==-~~=~~=l=a~.-:..;:;:.,;,:.;.;..~.:,:,:;;.:..-J..:;.::~:.:=~=,.

9-3-76 OP OT ~T Protection Delta Electronic drift. Caused channel 2 Replaced summator with spare unit. Placed channel in test, 1 hr.

T Flux Summator. OP ~T Setpoint to be Calibrated, checked for proper Used approved procedures. .

Output erratic. penalized, operation and returned to service.

tU-32 Source and Inter- Source range detector Unit at cold shutdown Replaced source and intermediate Placed channel in test. '; 8 hrs, 9-23-76 mediate Range Detector fatigue resulted in low safety not compromi- detector assembly. Calibrated Used approved procedures.

reading. sed, and returned to service. Redundant channel I operating properly.

N 0\

co I

• I' IDUT No. 2 INSTRUMENT MAINTENANCE (OTHER SAFETY RELATED SYSTEMS AND MAJOR ITEMS)

PAGE 1 of 1 OCTOBER, 1976 SYSTEM OR COMPONENT RESULTS AND EFFECT PRECAUTIONS TAKEN TIME REQ 1 D DATE FOR REACTOR SAFETY FOR MAINT.

INVOLVED CAUSE OF THE MALFUNCTION ON '.SAFE OPERATION CORRECTIVE ACTION TAKEN 10-11-76 Feedwater flow Prot. Electronic failure Ho FH < SF Trip Repaired multiplier/divider module. Used approved procedureE 2 hrs.

Channel III Multiplier/ resulted in rendering. would have been Checked for prop~r operation. Redundant channel normal Divider. FM-2-477 FW < SF comparator generated from Returned to service.

FC-2-467B inoperative. Channel III.

Electronic component Combined error of Replaced both modules with system Used approved procedurm 2 hrs.

10-17-76 Reactor Coolant Temp.

I Function Generator failure in TM-2-432F & the two modules re- spares. Calibrated, checked for Redundant channels

~* NM-2-432-C and Summator NM-2-432C sulted in OTSP being proper operation & returned to normal.

1.0 Til-2-432F

• 02); high. Out of service.

I spec. unconservative

UNIT NO, 2 (OTHER SAFETY RELATED SYSTENS AND }L\.:,:!l ITEMS)

DECEMBER, 1976 SYSTEM OR cm!P~--1~*=-====*========;e===RE=,=s=u=L=TS=Af=.=m=E=F=F=,r:=.c=T==r=====================P=R=E=CA=U=T=I=O=N=S=TAK=E=N====T=r.=,m=R=E=Q='=D==

DATE n,VllLV!*:D C,\USE OF THE MALFUNCTION ON SAFE OPERATION CORRECTIVE ACTION TAKEN FOR REACTOR SAFETY FOR MAINT,

l===========-=-=l=-*-~-~=~-=--~--=-====**---+-*=========f================~=========='==

As per Hestinghouse Engineering Reactor at cold shut- 2 hrs.

12-2-76 Rod Control System fuses No malfunction None Change No. 0268027 all Chase Shomot down.

A25Xl0 10 amp fuses were changed to Bussman fuse No. 2432B59.

Replaced detector #768 with Det. No. Reactor at cold shut- 2 hrs.

RHS 261 Containment l!echanical failure of None 12-6-76 397 calibrated and placed in service. down.

H/R Gamma check sour ce.

Replaced Ser. No. 011002-44 with Placed channel in test. 1 hr.

N-42 Power Range Detector Electronic failure False indication Used approved procedures 12-17-76 spare power supply Ser. No. 210028-44

.25 V power supply. " 8% on N-42. Adjusted for proper output and re- Unit in shutdown turned to service. condition.

Rescaled transmitters to new 120% Used approved procedures 3 hrs.

Reactor Coolant Flow Incorrect 100% flow DP Low Flow Indication Reactor at *Hot Shut-

.12-11-76 DP based on 100% Flow D.P. readings.

I Transmitters due to S.G Tube Plugg- down condition, N

-.J ing Operations.

0 I

OTHER EVEt!TS OF INTEREST

• 1.

~.

')

Cheniica 1 Releases To The Cooling Water Jnstanc(~s Where Thermal D.ischargp Limits Were Exceeded 3.

Results of Analysis of Non-Radiological Environment Monitoring Program

4. Fuel Handling

5. Fuel Characteristics

6. Effluent Releases

7. Single Releases of Radioactivity or Radiation Exposure Associated With Outages

-271-

CHEMICAL RELEASES TO THE COOLING WATER

-272-

SURRY POWER STATION i

CHEMISTRY REPORT

. JANUARY---,-1-9:_'.7-6--------. ----_- --* - - - - - --~-.--------~

• T.S. 6.6.A.ll PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 4.21E-l 2.90E-l 3.52E-l 2.48E-l 1. 92E-.3 .1. 56E-l Suspended Solids, ppm o.o o.o o.o 0.1 o.o 0.1 Gross Tritium, µCi/ml 1. 05E-l 2o73E-2 7.57E-2 9.56E-2 2.91E-2 5.15E-2 Iodine-131, µCi/ml 9.17E-2. 8.lOE-3 1. 68E-2 2.02E-2 1.19E-2 . l.68E-2 I-131/I-133 0.86 o.* 35 0.62 0.67 0.31 0.49 Hydrogen, cc/kg 23.1 15.3 19.6 33.6 o. Q;'< 14.4 Lithium, ppm 0.95 0.68 0.85 0~71 0.32 0.50 Boron-IO, ppm+ 177. 4 152.9 165.6 255.4 85.8 160.9 Oxygen-16, ppm 0 0 b 0 0 0 Chloride, ppm 0.07 0.05 o.os 0.09 0.05 0.06 pH@ 25°C 6.82 6.50* 6.63 6.89 5.99 6.52

+Boron-IO= Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate o.o Boron 697.4 Sulfate 1390 Chromate 0.14

• Unit Shutdown Remarks=-------------------------,------------,-----

• -273-(

SURRY POWER STATION

• • CHEMISTRY REPORT February ,19~

T.S. 6.6.A.ll PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIHU:f HINIHUN AVER.A.GE MAXIHUH MINIHUM AVERAGE Gross Radioact., µCi/ml l J,JF-1 1. 70E-l'

f. OJ E l 2.70E-l 3.35E-l 2. 74t-l Suspended Solids, PPGl 0.00 0. 00 0.0()

0.01 0.00 0.01 Gross Tritiu::a, µCi/ml 1.4JE-l B.l4E-2 3. 70E-2 6. OGI*:-2

l. 5 7E-1 l.37E-l Iodine-131, µCi/ml 1. 70!:-2 4.87E-3 1.. l 3E-2 3.23E-2 6.2.JE-3 LSOE-2 I-131/I-133 0.8280 0.1664 0.5391. 0.5104 0.1.639 0.3532' Hydrogen, cc/kg 36.4 1.5.3 22. lf 30.0 8. (J 21 . 7 Lithiun, ppm 0.50 1. 03 0.9] 0.20 *'*

0.88 0.46 Boron-10, ppr::!+ 1.55 139 .H3 296 -;': 75 154 O-,.;:ygen-16, 0.000 0.000 0.000 5. 700~: 0.000 0.660 ppm

• Chloride, pp:n 0.08 0.05 0.05 *0.09 0.05 0. 05 pH @ 25°C 6.82 6.50 6.59 6.87 6.05 6.43

+ Boron-10 = Total Boron x 0;196 NON-RADIOACTIVE CHEMICAL.

RELEASES, POUNDS T.S. ,*. 13.A.8 Phosphate 0 Boron 1.483.4 Sulfate 556 Chromate~ .03 Remarks: *'* Unit 2 at cold shutdown

• -274-

---~--------*-

SURRY POHER STATION

---

-PRIBArrTer1w*rs1:w AND cHEMICAL RELEAsEs TO CIRCULATING WATER HAR_C_l_i_ _ , 19~

r PRIHAJW COOL@T I ANALYSIS MAXIHUN UNIT NO. 1 AVERAGE NAxnm:-1 UNIT NO. 2 MINIHUH HINIM!J<*I AVER.4.GE Gross Radioact., µCi/ml 3.93E-l 4.70E-2 2.StlE-1 2.4JE-1 4.05E-2 1. GSE-1 f Suspended Solids, ppm 0.0 0.1 0.2 (). 0 0.1 r

0.3 Gross Tritium, µCi/ml 1. 87E-l S.67E-3 3.73E-2 1. 52E-l 4.03E-2 8.61E-2 I

l Iodine-131, µCi/ml 3. 77E-2 J.12E-2 2. 72E-2 2.03E-2 8.30E-3 1. 58E-2 II I-131/I-133 Hydrogen, cc/kg

o. 7344 24.8 0.4381

2. 8"'

0 . .5630 12.6 0.6304 26.l 0.2030 3 .o,*,

O. l,650 17.9 t_I J. . J.* ~1...

1-,J:.em, ppm 1. 00 0.34 0.65 0.75 o. 25 0.4]

j* Boron-10, ppm+ 271"' 105 185 264"' 61 130 r-

!j er..::ygen-16, ppm 5. 000"' 0.000 0.339* 3. 300'°' 0.000 0.233 Chloride, ppm 0.10 0.05 0.05 0.07 0.05 0.050 pH@ 25°C 6. 72 6.02 6.40 6.80 6.15 6.58

+ Boron-10 Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 10 Boron 1411. 8 Sulfate 1397 Chromate 0.07 Remarks:

• Unit Shutdown

• -275-

SURRY POWER ~rATION

• CHEMISTRY REPORT

~A_P_R_I_L~~'l9-2..§_

T.S. 6.6.A.ll PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 9.61E-2 l. 53E-l 4.00E-1 2. 77E-l 2. 37E-l 4.09E-3 Suspended Solids, ppm 0.01 CJ. 00 0.01 0.02 0.00 0.01 Gross Tritium, µCi/ml l.2HE-l 5.97E-2 9.02E-2 l.13E-l 2.40E-2 7.SlE-2 Iodine-131, µCi/ml 2.64E-2 l.29E-2 l. 6h-2 2.16£-2 1. 3L1E-2 l.68E-2 I-131/1-133 0.9789 0.4074 0. 5718 .0. 8518 0.3057 0.5871 Hydrogen, cc/kg (1) (2) 33.0 2.2 16.5 25.2 0.0 14. 3 (2)

Lithium, ppm 0.60 0.33 0.49 0.41 0.00 0.29 (l) (2)

Boron-10, ppm+ 315.0 109.2 166.2 422.2 49.4 230.9 tl)

(2) (£)

Oxygen-16, ppm 0.000 (1) 0.842 0.200 0.074 4.100 0.000 Cliloride, ppm 0.09 0.05 0.05 0.07 0.05 0.05 (2) pH@ 25°C 6.70 6.13 6.45 6.80 5.10 6.40

+ Boron-10 Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 10 Boron 497 Sulfate (4) 1126 Chromate ~~~0_._0_6~ ~ ~ ~ -

Remarks: (1) Unit at Cold Shutdown I

(2) Unit at Refueling Shutdown

• -276-

SURRY POHER STATIO~!

CHEMISTRY REPORT T.S. 6.6.A.ll PRHlaL"R.Y COOLANT UNIT NO. 1 UNIT NO. 2 A.t'l'ALYSIS MAXIHillf HINTI-fUM AVERAGE MAXrnu:1 MINHfUH AVERAGE Gross Radioact., µCi/ml 1. 78E-2 2.lOE-1 3.12E-2 1. 24E-3 l.06E~

2.89E-l Susp2nded Solids, ppm o.o 0,1 b.33 o.o 0.1 O"l Gross Tritium, µCi/ml l.19E-l 5.06E-2

• 8.89E-2 2. 24 E-2 1. 22E-2 L 73E-2 Icdine-131, µCi/ml 5. 96E-2 2. 41E-3 1. 75E-2 ,': "i':

I-131/I-133 0.7414 0.1424 0.5494 *k (1) (1)

Hydrogen, cc/kg 28.3 2.2 19.2 7.2 o.o 0.2 ( 1)

Lithiura, ppm (1) 1.85 0.73 1.45 1.12 0.10 0.41

. (1) (1) (1 ( 1)

Boron-10, ppm+ 500.6 230.3 449.6 255 .. 4 91.5 150.3 (1) (1) (1) (l (l)

Oxygen-16, ppm 5_.600 0.000 0 .. 283 Sc.ODO 0.,000 1.50 m

Chloride, ppm 0.36 0.05 0.08 o'. 30 (1) 0.05 I 0.09 pH@ 25°C 6,95 5.40 6,64 5. 95 . 4.70 I 5.41

\

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 0 Boron 1256.,9 Sulfate 834 50% NaOH ~--"1~0~5~0'-------

Remarks; _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

• Test not performed, unit down for Refueling (1) Unit Shutdown

• -277- cffemistry Supervisor

SURRY POWER STATION CHEMISTRY REPORT

• _J_u_n_e_ _ , 19~

T.S. 6.6.A.ll I

PRIHARY COOLANT UNIT NO. 1 UNIT NO. 2 A.NALYSIS MAXIHmr MINTI1UM AVER.~GE MAXDITI'.1 MINIBUM AVERA.GE 1

Gross Radioac t., µCi/ml 2.67E-l 1. 40E-l 2.27E-l 1. 27E-l 2.52E-4 6.66E-2 Suspended Solids, ppm 0.01 0.00 0.01 0.02 0.00 0.01 Gross Tritium, µC.i/ml 2.59E-l 1. 38E-l 1. 78E-l 2.67E-l 9.73E-3 9.35E-2 I Iodine-131, µCi/ml 6.36E-2 7.60E-3 2.19E-2 1. 02E-2 L46E-3 4.27E-3 I-131/I-133 0.9360 0.3639" 0.6570 0. 7611 0.1766 0.4450 13.3 30.0

- 20.9 Hydrogen, cc/kg 20.2 11. 0 7.3 I Lithiu::i, pp;:i 1. 65 1.10 1.40 34.7 2.70 237.7 0.68 1.53 199.1 rBoroo-10, ppm+ . 92.9 77.0 159.7 Cr...cygen-16, ppm 0.000 0.000 0.000 0.080 0.000 0.003 I Chlorid<:, ppm 0.07 0.05 0.05 0.10 0.05 0.06 pH@ 2:)°C 7.07 6.80 6.94 6.81 5.92 6.62

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 0 Boron 1510. 6 Sulfate 1946 Chromate 1.63 50% NaOH 2450 Remarks: (1) Ion Exchanger put in service to lower Lithium back to specifications.

• -278- . Chemistry Supervisor

SURRY POWER STATION CHEMISTRY REPORT

• _J_U_L_Y_ _ _ , 19-2.§_

T.S. 6.6.A.ll PRHL~Y COOLANT

.ANALYSIS UNIT NO. 1 UNIT NO. 2 I MAXIHill! MINiliill1 .AVER.AGE MAXIlllil1 MINIMUM AVERAGE Gross Radioact., µCi/ml 3,83E-l 3,39E-2 2.lOE-1 l.20E-l 3.00E-2 9.15_~

Suspended Solids, ppm 0.05 0.00 0.01 0.01 o.oo 0.01 Gross Tritiura, µCi/ml 1. 48E-l 9.50E-2 L. 23E-l 2.64E-l 1:70E-l 2.07E-1 Iodine-131, µCi/al 5.53E-2 4.88E-3 .2. 27E-2 2, 02E-2 1;57E-3 5.59E-3 I-131/I-133 o. 8418 0.3272 0.5186 1,0340 o*. 1060 0.5425 Hydrogen, cc/kg 16ol 0.01,

• 10.3 31.8 10.0 21,4 Litr..i.UIJ, ppI:1 1.40 0.26 0.85 2. 25 (1) 1.76 2.09 Boron-10, ppm + - 313.0 63.1 157.8 262.8 137 ,6 175,2 O-..::ygen-16, ppm 6.000* 0.000 0,.650"' OcOOO 0.000 0.000 Chloride, ppu.1 0.10 0.05 0.06 0,07 0.05 0.0.5 pH@ 2s c0 7o00 5.70 6.46 6 ,80. 6.32 6, 71

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL RELEASES, POl.Jt'lvS T.S. 4.13.A.8 Phosphate OoO Boron 1617.7 Sulfate 1390 Chromate ___o_.~l._7_ _ _ _ __

50% NaOH 1750 Ret::1arks: _ _.:.:."':. !,Ul!!nc!i1at~S.!!h.!c!.u~td~o!..!!t:::'. !vn1___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(1) Lithium found to be high, ion exchanger used to ,lower the concentration *

• -279-

, /. j/

Chemistry Supervisor

{'

/( . fl' -.//.,'. * - 1 *p I

SURRY POWER STATION CHEMISTRY REPORT

=AU~G~,Uc...:cS...;;;T_ _ , 19--2§_

T.S. 6.6.A.ll I ---

PRIMA.RY COOLANT UNIT NO. l UNIT NO. 2 ANALYSIS MAXUrtm MINIMUM AVERAGE MAXIH1l}1 MINIHUH AVERAGE Gross Radioact., µCi/ml 2.95E-l 5.54E-2 2. J 8E-l l.49E-l 3.58E-2 l.07E-l,.__ ,_

Susp2nded Solids, ppm 0.2 0.0 0.1 o*. 1 0.0 0.1 l

I Gross Tritium, µCi/ml 1. llE-1 9.28E-2 l .OlE-1 l. 75E-l 9.69E-2 1. 29E-l

~dine-131, vci/ml 2. 62E-2 3.99E-3 1.56E-2 9. 6 7E-3 L 25E-3 4.00E-3 I-131/I-,-133 0.7339 0.3793 0.5369 0. 7798 0.1780 0.4083 Hydrogen, cc/kg 0.01, 22.9 11. 3 26.7 12.4 19.9 Lithium, ppm 2.10 0.30 0.66 1.9.5 LOO 1. 62 Boron-10, ppm+ . 257.9'~ 114.5 153.7 300. 71, 51.2 llO

! O-...:ygen-16, ppm 1. 8001, 0.000 0.319 0.000 0.000 0.000 I ChloridE:, ppm 0.09 0.05 0.06 o."06 0.05 0.05 iI pH @ 25°C 6.80 6.20 6.64 6.86 6.20 6.64

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 0 Boron 1141.9 Sulfate 1946 Chromate 0.08 50% NaOH ~--24~5~0~~~~~~

• -280-

,::I"

, ,.//' . /

_., / :, ... ;:-*-

Che~i~try Supervisor

SURRY POWER STATION CHEMISTRY REPORT T.S.6.6.A.ll r --

PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MA.XIHU}I MINIMUM AVERAGE Gross Radioact., pCi/ml 3. 68E-l 4. 70E-2 1.40E-l 5.06E-3 6.85E-2 2.35E-l (1)

Suspended Solids, ppm 0.3 0.0 8.2 0.0 0.8 0.1 Gross Tritium, µCi/ml 1.78E-l 7.80E-2 1. 24E-l 5.09E-l 2.95E-2 2.08E-l Iotline-131, pCi/ml 1. 24E-1 2.43E-2 7.84E-2 4.61E-2 1. 75E-4 6.98E-3 I-131/I-.133 1.1600 0.3573 0.8879 0.5956 0.0743 0.3349

( 1) (1)

Hydrogen, cc/kg 18. 3 0.0 9.5 20.0 0.0 8.1 Lithium, ppm 0.40 0.31 U.34 2.20 1.48 1.88 (1) (1)

Boron-10, ppm+ 234 32 102 272 llO 211 (1) (1)

Oxygen-16, ppm 6.60 0.000 0.279 0.100 O;OOO 0.008 (1) (1)

Chloride, ppm 0.13 0.05 0.06 0.17 0.05 0.08 pH@ 25°c 6.86 6.18 6.63 6.96 6.28 6.56

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE* CHEMICAL RELEASES, POUNDS T.S. l1.13.A.8 Phosphate 16 Boron 2685 Sulfate ll22 Chromate 1.03 5 0% NaOU _--=.14...:..0=-0c...__ _ _ __

Remarks: (1) Unit at Cold Shutdown

• -281- l.,i_; * ;I. .Jf J L~

/;,1.,fy,.-,-, '{-c')'

CflbMLS I'R'i' SlJP ,,.

• on_------

SURRY POWER STATiml

• CHEMISTRY REPORT

_ _ .19~

_o_c_T_O_B_ER T.S. 6.6.A.ll PRIHARY COOLfuiT UNIT NO. 1 UNIT NO. 2 Ai~ALYSIS

• MAxnrmr HINTI-fUM AVERAGE ViA..XIHffi1 MINIHUH AVERAGE Cross R.adioact., µCi/ml 3.74E-l l.45E-3 1. 84E-l 3.17E-2 4 .64E-3 l.60E-2 Susp,mded Solids, ppm 7.8 ( J.) 0.0 0.6 1.1 0.0 0.2 I' Gross Tritiuu1., µCi/ml 1. 06E-l l.17E-2 4.34E-2 2.84E-2 1. 21E-2 1. 96E-2 I

I I

Iodine-131, µCi/ml 2.63E-2 4.99E-3 .. J.,75E-2 *

• ii'>.

I-131/I-133 o. 5610 0.2534 o. 3968 *;*,

17.8 0. 0 , (1) 5.4 -~  ;':

Hydrogen, cc/kg

• LithiUD, ppm 0.40 0.53 ,~ ii'~

0. 71 Boron-10, ppm+ - 481.0 (1) 24.5 3 36. 2" 352.6 248.7 278.7 I

Oxygen-16, ppm 4.000 (1) 0.000 1.593 >O .100 >0.100 >0.100 Chloride, ppm 0.15 (2) 0.05 0.07 0.14 0.05 0.07 pH@ 25°C 7.30 4. 72 5.78 6.02 5.68 5.92

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE .CHEMICAL RELEASES, P0u~1JS T.S. 4.13.A.8 Phosphate 35 Boron 2770 Sulfate 1415 Chromate _ _ _o_._7_2_;___ _ _~

50% NaOH R,emar.:s:

t _ _,., _Unit

_ _2_shutdown

_____ for_entire

____ _ _ of month __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

October.

(1) Unit l a t refueling shutdown.

I (2) At cold shutdown conditions; new mix bed ion exchanger placed in service, two

• ~ - - - - - - - h__o_u_r_s_a_f_te_r_i_*n_i_t_i_a_1_s_am_pl_e_o_f_o_._1_5_P_P_m_,_a_n_*o_t_h_e_r_s_a_m_p_l-'-e_s_h_o_w_e_d_o_*~-~-2_P_P..,...m_.- - - - - -

1

/ / .' **, ....\_:*//.

/ ,. ~--*.,, '.'~...

,~z.*/

themistry Supervisor

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• SURRY POWER STATION CHEMISTRY REPORT NOVEMBER , 19~

T.S. 6.6.A.11 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 9.32xl0- 3 4.92xl0- 4 2. 59x10- 3 8. 95x10- 3 5.45xl0- 4 3.10x10- 3 Suspended Solids, ppm 0.7 0.2 0.8 0 .o 0.2 0.0 Gross Tritium, µCi/ml 9 .98xl0- 5 8. 26xl0- 3 9.17xl0- 3 9. 04xl0- 3 5. 60xl0- 3 7.57x10- 3 (1) (1) (1) (2) (2) (2)

Iodine-131, µCi/ml (1) (1) (1) (2) (2) (2)

I-131/I-133 (lJ (1) (1) (L) Cl) (ZJ Hydrogen, cc/kg o.o o.o 0.0 o.o 0.0 o.o

( 1) (1) (1) (L)

Lithium, ppm 2.45 0.0 1. 42 UJ (1) (1) en TZJ (2)

Boron-10, ppm+ 537 ~72 488 385 309 359 Oxygen-16, ppm 2.0 lTJ (1) (1) 6.50 Cl) 0.00

-(2) m-kl. 7 1.0 2. 76 Chloride, ppm 0.09 0.05 0.05 0.15 0.05

• 0.08 pH@ 25°C ,5. 47 14.62 5.31 6.22

• 4. 73 5.56

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 45 Boron 781 Sulfate 54 Chromate ~~o_._3_4_~~-~~

50% lfaOH _ _ _4.:____ _ _ __ Chlorine _ _O_.O_ _~ - - ~

Remarks: (1) Unit 1 at Refueling shutdown (2) Unit 2 at Cold shutdown

• -283-

. CHEMISTRY SUPERVISOR

SURRY POWER STATION CHEMISTRY REPORT DECEMBER ,19~

• T.S. 6.6.A.ll PRIM.i\RY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIHill! MINIMUM AVERAGE MAXINffi1 MINIHUH AVERAGE 3 1 4 2 Gross R.adioact., µCi/ml 1. 05xl0

-2

4. 88xl0-4 3.25xl0- 1. 93x10- 3.67xl0- 4.32xl0-Suspended Solids, ppm 0.1 0.0 0.08 0.3* 0.0 0.1 7.03xl0 -

3 ' 3 Gross Tritium, µc°i/ml 6.95x10- 3 5.74xl0-3 6.34xl0-3 l.18xl0..:.. 2 4 .13xl0-Iodine-131, µCi/ml (1) (1) CL) (2) (2).

(2)

I-131/I-,.133 (1) (1) (1) (2) (2) (2)

Hydrogen, cc/kg (1) (1) . (1) 16.3 0.56 6.87 Li thium. 2 ppm (1) (1) (1) 1.09 0.70 0.83 Boron-10, ppm+ . 485 546 330 1.09 210 583 Oxygen-16, ppm 2.400 ci: 0.050 (1) 0.410 (1) 7.000 (2) 0.000 0.280 Chloride, ppm 0.27 (1 0.05 0.12 <.05 0.06 0.09 pH@ 25°C 5.49 4.20 6.70 5.30 6.05 4.95

+ Boron-10 = Total Boron x 0~196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate 24 Boron 642 1414 Chromate 0.20 Sulfate ----------

50% NaOH 877 Chlorine 0.0 (1) Unit at Cold Shutdown (2) Unit at Cold Shutdown or unstable power entire month.

-284-

~II tJ '"'-1{,,"ii;e, Cemistrv SnnPr",c:nr

nJSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED

-285-

INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED

• The temperature limitations on condenser cooling water discharge found in Technical Specification 4.14 apply to heat added to the water passing through the turbine steam condensers and the heat added to the river by the heated water discharged from the condensers. In the following instances the thermal dis-charge limits delineated in the Teclinical Specifications were exceeded.

Notification letters to the Nuclear Regulatory Commission were sent for each occasion.

DATE EVENT TECHNICAL SPECIFICATION 2-15-76 Exceeded 15°F b.T 4.14.A.2 2-28-76 Exceeded 15°F 6.T 4.14.A.2 3-22-76 Exceeded 15°F f.,.T 4.14.A.2 3-23-76 Exceeded 15°F b.T 4.14.A.2 3-26-76 Exceeded 15°F b.T 4.14.A.2 4-12-76 Exceeded 15°F b.T 4 .14 .A. 2 6-25-76 Exceeded 15°F b.T 4.14.A.2 12-20-76 Exceeded 3°F/Hr Temperature 4.14.A.3 Increase 12-26-76 Exceeded 3°F/Hr Temperature 4.14.A.3 Increase

• -286-

RADIOLOGICAL ENVIRONMENTAL MONITORING

-287-

-=--

• • ENVIRO:'.\HENTAL MONITORING REPORT Ji\:/UARY 1 - DECEMBER 31, 1976 SURRY POWER STATION VIRGTIUA ELECTRIC AND POWER COMPANY SOUTHEASTERN FACILITY EBERLINE INSTRUMENT CORPORATION WEST COLUMBIA, SOUTH CAROLINA I *

-288-

TABLE OF CONTENTS PAGE INTRODUCTION. .01

SUMMARY

..... . .08 Air Particulate Samples. .08 Ambient Thermoluminescent Dosimetry *..*................. 11 Precipitation Samples *.........*.. ~ ..................... 12 Milk Samples ...... . 12 Well Water Samples. 14 Surface Water Samples. 15 James River Water Samples. 15 Silt Samples ... ..... 17 Oyster Samples ..

• e * * * * * * * * * * * * * * * * * * * * * * * .* * * * * *

• 18 Clam Samples. 19 Crab Samples.

• e * * * * * * * * * * * *

• a e

• e * * * *

• e * *

• e * * * * *

• o * * * * * *

• 21 Fish Samples. .21 Soil Samples. .......................................... .21 Food Crop Samples. ................................. . . . . . 22 Fowl Samples. .23 Conclusion. o 8 ***************************** ***.. 23 ANALYTICAL PROCEDURES **............*........... .25 EQUIPMENT ......*......* 0 e Cl

• 8 e e e O e e e 8 e e e e 8 e 8 0 9 9 e O e 9 e e e e e 9 9 9 e e .29

SUMMARY

OF SAMPLE DATA * . . . . .... . . . . ... . . . . . . . . . . . . ... . . . . . . . . .32

• -289-

• INTRODUCTION The Surry Station of the Virginia Electric and Power Company is located on a peninsula in the James River approximately 25 miles upstream of the junction of the river with Chesapeake Bay. The site*

is on the west bank of the river in Surry County, Virginia. Two pressurized water reactors, are located at the site with a design output of 788 Mwe (net) per unit. Cooling water for the condensers is taken in downstream of the site and discharged 5.7 miles upstream*

of the intake. The flow of the river at the site is complex,*

influenced by the amount of fresh-water run-off, and the back-and-forth flow of the tide, upstream flow of more saline water near the bottom, and downstream flow of less saline water near the top.

During plant operation, low levels of radioactivity are released with the cooling water to the James River and with ventilation air to the atmosphere. Tbese reieases are limited to "as low as reasonably achievable" and are measured to assure compliance with the NRC Regula_tions. and the. Surry Power Station Technical. Specifications.

The-environmental monitoring program provides confirmatory surveillance.

The low levels of radionuclides released to the air and water from Surry Station contribute to the radiation background through both external and internal exposure. The primary modes of external exposure include immersion in a cloud of radioactive gaseous effluent, submersion in water containing radioactive effluent, and exposure from contaminated land surface. The primary modes of potential internal deposition include inhalation of air and ingestion of milk, fish, and shellfish.

Dose via the ingestion pathway is somewhat limited because the locale

/

-290-

• constitutes a very limited milk shed, and the saline river water is not used for drinking water.

Table I shows the manner in which the.elements of the Surry surveillance program fit together -to monitor any radiological impact as a result of operations .

• ,*i

-291- I

• TABLE I .

Relationship of Sampling and Measurements to Elements of the Radiation Dose Paths Sample and Measurements Radiatiort Dose P~th (Supportive Data)

Air Immersion Thermoluminescent Do.simetry (Air Sampling)

Inhalation Air Sampling (Precipitation, Crop Soil and Milk Sampling)

Land Surface Thermoluminescent Dosimetry, Crop and Soil Sampling (Air and Milk Sampling)

Ingestion Fish and Shellfish Fish, Oysters, Clam, and Crab Sampling (Water and Silt Sampling)

Water Well, Surface Water, and Precipitation Sampling (River Water and Silt Sampling)

Milk Milk Sampling (Air, Water, Soil, and Crop Sampling)

Water Submersion Water Sampling (Silt Sampling)

• : -292-

TABLE II

~onitoring or Sampling Locations and Frequencies Air Ambient Particulate Well Surface Radiation Precipitation Milk Water Water Soil Surry Station BW Q. M Hog Island Res. BW SA A Q SA Bacon's Cast le BW Q M(2 ea)

Chippokes Creek SA A SA Alliance BW I I' Colonial Parkway BW Q

Q M A

A N,

I.O

(..,J Williamsburg I

Jamestown SA Q SA Dow BW Q Fort Eustis BW Q A A

Newport News BW Q M SA Scotland Q Leehall Q M Routes10-676 Q Smithfield Q SA

• .James *.

Fowl River Crops Water Silt Oyster Clams Fish Crab Bacon's Gastle A.(3)

Hog Island Res. SA

.Jamestown BM Newport News BM SA BM  :

Chickahominy BM SA BM Station Di~charge BM SA BM  :

Hog Island Pt. BM SA B?:I .

Station Intake BM SA SA SM Lawnes Creek BM

,N , . peep Water Shoals BM

\.0

.i:,,.

I Point of Shoals " SA BM BW-Bi-weekly M-Monthly BM-Bi-monthly Q-Quarterly SA-Semi-annually A-Annually A(3)-Annually corn, peanuts, and soybeans SM-Summer Months (two sampling*s: July - September)

TABLE III Environmental Measurement

• Type Sample Air Particulate Frequency Bi-weekly and Sample Analysis Program Analysis Gross Beta (1)

Quarterly Gamma Isotopic (2)

James River Water Bi-monthly Gamma Isotopic (Salt Water) Semi-annual Tritium Well Water Semi-annual Gross Alpha, Gross Beta, and Tritium Surface Water Semi-annual Gross Alpha, Gross Beta, (Fresh Water) and Tritium Precipitation Quarterly Gross Beta (3) and Enriched Tritium TLD Quarterly mRem Crops Annually Gamma Isotopic and Sr-90 Fowl Semi-annual Gamma Isotopic (4)

Fish Semi-annual Gamma Isotopic Oyster & Clam Bi"".monthly Gamma Isotopic (4)

Crab Summer months Gamma Isotopic Silt Semi-annuli! Gamma Isotopic Soil Annually Gamma Isotopic Milk Monthly Sr-89, 90, *calcium, Gamma Isotopic, and I-131

• -295-

NOTES TO TABLE III

• (1) Gamma isotopic analysis if gross beta exceeds 10 pCi/M 3 *

(2) Quarterly composites of bi-weekly air particulate samples will be analyzed for gamma emitters in three groups as follows:

Stations 1 & 2 analyzed as one sample.

Stations 3,5,6,9, & 10 analyzed as one sample.

Station 11 analyzed as one sample.

Strontium-90 determined radiochemically if* significant amounts of fission products attributable to the Station are detected by the gamma isotopic analysis.

(3) Perform gamma isotopic analysis if gross beta exceeds 15 nCi/M 3 *

(4) Entire sample analyzed fot gamma emitters. Sr-90 to be deter-mined if a significant amount of fisston products attributable to the Station are noted in the gamma analysis .

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SUMMARY

~ Air Particulate Samples Air particulate samples showed the arrival of widely reported fallout associated with a nuclear test conducted by the Peoples Republic.of China. The chronology of gross beta concentrations shows the exten~ and duration of the elevated activity. Tqe average of all air sampling locations, for the period of interest showed:

Date Collected Gross Beta (pCi/M 3 )

10-06-76 4o2 E-02 10-21-76 2.3 E-01 11-02-76 2.2 E-01

• 11-.17-76 7.3 E-02 11-21-76 1. 3 E-01 11-30-76 8.4 E-02 12-14-76 7.2 E-02 12-27-76. 4.4 E-02 The chronological averages of gross beta concentrations rapged from 1. 9 to 4. 6 E-02 pCi/M 3 during the first half of 1976. A similar comparison for the second half of the year, but ex~lusive of those noted above, ranged from 2.2 to 3.4 E-02 pCi/M 3

• The 197 5 average concentrations generally ranged from 1. 6 to 5. 7. E-02

. pCi/M 3 with the exception of a period during late winter apd early spring. This latter period, with concent'I'.ations ranging up to

1. 6 E-01 pCi/M 3 , indicated the arrival of older fallout which had been expected due to previous experience. The upper atmosphere inventory of fallout has sufficiently decreased so that no elevated concentrations were observed during the winter/spring of 1976.

Gross alpha concentrations on air particulate samples collected, during 1976, were quantitated by VEPCo. No trend was noted and

~ .expected low level concentrations, on the order of 10- 3 to 10- 4

.-:-297-

pCi/M 3 , were documented. The single highest coricentration was

• noted at Newport News on 9-7-76 with 1.52 +/- 0.25 E-02 pCi/M 3

• This location is most remote from Surry Station and no plant contribution is indicated.

Gamma spectrometry of quarterly composites showed fission and activation products. Those measured throughout the year, and which are exclusive of the new fallout, included cobalts 58 and 60, and cesium-137. Those data are summarized below:

Bacon's Castle, Alliance, Surry Station & Colonial Pkwy., Dow, Newport Hog Island Reserve & Fort Eustis News Cobalt-SB 1st Qtr. 5.8 + 2.8 fCi/M 3 4.1 + 2.1 £Ci/M 3 <6.6 fCi/M 3 2nd Qtr. 23 + 4 2.6 + 1.4 3.6 + 2.0 3rd Qtr. 1.8 + 1.1 2.1 + 0.7 <5. 3-*

4th Qtr. 30 + 5 3.4 + 1.2 <9.6 Cobalt-60 1st Qtr. 3 . 0 + 1. 9 f Ci /M 3 1.8 + 1.5 fCi/M 3 <4.7 fCi/M 3 2nd Qtr. 6.9 + 2.4 <l. 7- <4.8 3rd Qtr. 3.2 + 1.4 2. 4 + 0.8 <2.9 4th,Qtr. . 16 + 4 4. 1 + 1. 4 <11 Cesium-137 1st Qtr. 4.9 + 1.9 fCi/M 3 3.5 + 1.7 fCi/M 3 4. 5 + 3.4 fCi/M:j 2nd Qtr. 5.8 + 2~2 <1.8- <4.2 i 3rd Qtr. 5.5 + 1.4 2.1 + 0.7 3.2 + 1.8 4th Qtr. 10 + 3 3.3 + 1.2 3.8 + 2.9 In addition to those above, other fission and activation

• products, due to the. Chinese fallout, were quantitated.

Bacon's Castle, Alliance, Surry Station & Colonial Pkwy. , Dow,. Newport Hog Island Reserve & Fort Eustis News Cobalt-57 4th Qtr. 19 +/- 14 fCi/M 3 <6.7 fCi/M 3 <36 fCi/M 3 Zirconium-95 4th Qtr .. 15 + 4 14 + 2 31 + 7 Niobium-95 4th Qtr. 17 + 4 17 + 2 32 + 7

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Bacon's Castle, Alliance, Surry Station & Colonial Pkwy., Dow, Newport Hog Island Reserve & Fort Eustis News Ruthenium-103 4th Qtr~ 14 + 3 fCi/M 3 10 +/-2 fCi/M 3 8.3 +/- 4.4 fCi/M 3 Cesium-134

• 4th Qtr. 3.4 +/- 2.7 <1. 3 <6.9 Cerium-141 4th Qtr. 19 + 5 28 + 5 31 + 8 Cerium-144 4th Qtr. 21 + 15 18 + 12 38 + 22 This same period yielded indications of barium-lanthanum-140 however the precise concentration in time cannot be given due to the relatively short half life of the parent and compared to the composite period.

Other radionuclides, likely to be attributed to Surry Plant effluent, were observed in single instances. All were noted in the first quarter composite and were:

• . Chromium-51 3.3 + 3.2 fCi/M 3 Newport News Manganese-54 2.3 + 1.6 SS & HIR Cesium-134 2.9 + 1.8 SS & HIR One can .presume the cobalts-SB and 60 are due to Surry Plant effluen_t. One can presume much of the cesium-137 is present due to old fallout since its concentration is relatively uniform during.the period and comparable to historical data. Further, one would expect cesium-134 concentrations to be apparent with significant plant contribution of cesium-137. Thts apparently was the case with the Surry Station and Hog Island Reserve fourth quarter composite.

An es-timate of the dose connnittment, through inhalation close in the Surry Plant, can be given by presuming the following concentrations*and.periods .

.:-.;.,.299-

Manganese-54 2.3 fCi/M 3 1st Qtr. (single composite)

Cobalt-58 15 year (average of 4 qtrs.)

• Cobalt-60 Cesium-137 Cesium-134

• 7.3 6.6 3.1 year 4th Qtr.

2 Qtrs.

(average of 4 qtrs.)

(difference between 4th qtr. composite and average of all composites at other locations)

(average of 2 qtrs.)

Using the model and assumptions given in Regulatory Guide

l. 109, and presuming an adult is in res.idence in the area of the composite sample analysis, the dose committment becomes:

Bone 9.9 E-04 mrem Kidney 5.3 E-04 mrem Liver 1. 6 E-03 Lung 2.4 E-02 Total Body 1.3 E-03 GI-LLI 3~4 E-'03 Ambient Thermoluminescent Dosimetry Environmental dosimetry data are summarized below, based*

upon the average f~r all four quarters less the c6ntrol do~imeter dose. Where the control dosimeter was missing or wh~re the control dosimeter dose was higher than the field dosimeters, the lowest field measurement was subtracted as an alternate to subtracting the control dosimeter indication.

Bacon's Castle 0. 4 mR/wk Smithfield 0.8 mR/wk Surry Station* 6.8 Scot. Wharf 0.3 Hog Island Reserve 0.4 Jamestown 0.1*

Alliance 0.4 Lee Hall . 0.6 Colonian Parkway 0.3 Rts. 10 & 676 0.2**

Fort Eustis 0.4 Dow 0.6 Newport News 0.6

• Single value - two missing, one net= 0.

• • Tw6 values - one missing, one net= 0.

The elevated measurement at Surry Station had been observed in the past and is indicative of on-site dose only. The other single highest location was at Smithfield. Due to its distance from the

• plant, relative to other locations, plant contribution is not expected. In the past, Alliance had indicated highest ambient

-300-

background while Bacon's Castle was also consistently relatively

• elevated. Other than the Surry Station on~site measurement, no other data showed significant noble gas effluent contribution.

The Chinese fallout was not sufficient to result in measurable gamma dose in excess of background.

Precipitation Samples The fourth quarter precipitation composite showed a relatively elevated tritium concentration at Newport News with 340 + 180 nCi/M 2

• This is the highest concentration observed in any precipitat~on sample.* Other concentrations averaged 87 nCi/M 2 and ranged from 39 + 14 to 150 + 30 nCi/M 2

• Gross beta concentrations can be summarized by:

.Average Maximum Minimum Surry Station 4.3 nCi/M 2 6. 0 + 1. 3 nCi/M 2 3. 2 + 1. 0 nCi/M 2 Newport.News 3.3 6.0+1.2 1.3+0.7 The Chinese fallout was not discernible through gross beta concen-trations in precipitation.

Milk Samples The previously mentioned Chinese fallout did show measurable concentrations in milk samples. There was no measurable iodine-131 until October 5th and the distribution is summarized below:

Date Lee Hall Colonial Pkwy.

~

Collected Judkins p 1) (pCi/1) (pCi/ l) * (pCi/ l) 10-05-76 2.0.+ 0.1 2.6 + 0.2 10-19-76 0.38 + 0.23 <0.2 10-21-76 0.57 + 0.20 0.60 + 0.16 11-02-76 3.4 + 0.9 11-18-76 <0.1 <0.1 0.42 + 0.14 11-30-76

. -301-

Samples collected on 12-14-76, and later, showed no measurable iodine-131. No contribution from Surry Station effluent is presumed.

Gannna spectrometry of milk samples showed cesium-137 in eleven of the fifty-six samples analyzed. There was no trend in time or distribution of the concentrations. These cesium-137 levels averaged 16 pCi/1 and ranged from 11 + 11 to 31 + 16 pCi/1.

There was no observable increase during the Chinese fallout.

Other isotopes were observed as a result of the fallout.

Iodine-131 was visualized, but the radiochemical procedure is much more precise than the gannna spectrometry. For example, *the Epp's sample collected on 10-05-76 showed 20 + 20 pCi/1 as opposed to the radiochemical 2~0 + 0.1 pCi/1. This same Epp'~

sample did show cerium-144 with 200 +/- 140 pCi/1 and lanthanum-140 indicated 26 + 24 pCi/1; barium-140 was less than 65 pCi/1.

Other isotopes were potentially present through gannna spectrometry:

Zr-95 Lee Hall 1-15-76 17 + 13 Co-60 Judkins 3-24-76 18 + 11.

Gwaltney 4-21-76 17 + 11 Colonial Parkway 7-30-76 13 + 13 Co-57 Gwaltney 4-21-76 20 + 18 Lee Hall 6-03-76 18 + 18 Cr-51 Colonial Parkway 4-06-76 140 + 140 The error terms associated with the above concentrations show that the analytical sensitivity is challenged. Some may be statistical artifacts however the large error term indicates that, at worst, actual concentrations were much lower than those indicated.

Radiostrontium analyses of the milk samples yielded measurable strontium-90 concentrations in forty-one of the fifty-six samples .

• Concentrations averaged 5.0 pCi/1 with a range of from 1.4 to 14 pCi/1. While no contribution from Surry Station was indicated, I

i

.,I

...:.302-

the appearance of strontium-89 in several samples.showed potential

• relationship to the Chinese fallout.

Location Lee Hall Date 10-19-76 10-21-76 9.4 + 2.4 3.5 + 2.2 Those samples were:

Sr-89 (pCi/1) Sr-90 (pCi/1) 0.0 + 2.3 3.9 + 1. 7 Judkins 11-02-76 12 + 3 4.3 + 1. 8 Colonial Pkwy. 11-18-76 3.6 + 1. 8 3.0 + 1. 8 Well Water Samples Well water samples were collected from the four locations on April 21, and November 2, 1976 and analyzed for gross alpha and beta concentrations as well as tritium. Gross alpha was below analytica,1 sensitivity in all samples. The two closest in samples, at Surry Station and Hog Island, showed no measurable beta activity, but both Jamestown and Bacon's Castle indicated activity.

Date Bacon's Castle Jamestown 4-21-76 12 +/- 5 pCi/1 7.8 + 5.3 pCi/1 11-02-76 2.4 + 1.4 2.7+1.6 The results mimic closely the 1975 determinations in location and concentration. No plant contribution is expected and the activity is presumed to be from naturally occuring radionuclides.

Tritium determinations in these same samples showed three of the eight measurements above detection limits:

4-21-76 Surry Station 270 + 120 pCi/1 Bacon's Castle 350 + 110 11-02-76 Bacon's Castle 150 + 100 This also is expected based upon sampling history. Bacon's Castle has been consist~ntly elevated with 1975 concentrations as high as 410 + 100 pCi/lo No contribution from Surry operations is expected and contribution from more recent precipitation (or

• • surface water intrusion) is expected .

-303-*

Surface Water Samples*

• Surface water.sampling, during April and November, showed no measurable gross alpha concentrations. The April sampling showed measu.rable beta activity in only the Newport News sample with

7. 0 +/- 5. 0 pCi/1. Samples collected on 11-02-76 all showed beta activity and may be indicative of the previously discussed Chinese fallout although concentrations were relatively low. The average of the four was 3.6 pCi/1 with a range of from 2.2 + 1.5 pCi/1 (Chippokes Creek) to 6.7 + 1.8 pCi/1 (Smithfield).

Tritium concentrations in the November samples were less than 300 pCi/1 with the exception of Smithfield which indicated 310 +

260 pCi/1. During April, tritium concentrations averaged 520 pCi/1 and ranged from 290 +/- 80 (Williamsburg) to 960 +/- 100 (Newport News) .

. No plant related activity was apparent in the surface water samples.

James River Water Samples Ganuna spectrometry of the bi-monthly samples showed expected concentrations of naturally occuring radionuclides with low levels of Cs-137 detected in four of the 33 samples. These were:

Location Date Cesium-137.

Station Intake 1...:30-76 4.6 + 4.1 pCi/1 3-15-76 4.6 + 4.1 Newport News 5-21-76 4.6 + 4.1 Chickahominy 9-23-76 5.4 + 4.3 Both cobalt-58 and chromium-51 were individually detected.

Location Date Cobalt-58 Hog Island Point 3-11-76 5.0 + 5.0 pCi/1 Station Discharge 3-11-76 4.8 + 4.4

-304-

Location Date Chromium-51

• Station Discharge Newport News 5-21-76 10-29-76 81 + 43 pCi/1 52 + 41 While the cesium-137 observations are typical and are most likely due to old fallout, the low levels of cobalt-58 and chromium-51 could be due 'to Surry ,effluent in both the Discharge samples and the Hog Island Point sample. Given the associated error terms, the concentrations were extremely low and, in single instances, constitute essentially no dose to man. This would be true even if the James River were used for drinking water, which it i~ not.

Subsequent portions of this report discuss accumulation in the river and accumulation in shellfish.

Tritium.levels, through semi-annual composites, showed:

Chickahominy Newport News.

First Half '76 200 + 100 570 + 200 Second Half '76 210 + 100 330 + 110 The higher numbers, more remote to Surry, help one to conclude that no appreciable plant effluent levels are detected. Concen-trations are typical for surface water and comparable to the 1975 data.

Two special samples were collected directly at the Discharge Canal to permit more direct measurement before dilution in the James River. Isotopes of interest were:

7-06-76 10-19-76 Mn-54 8.5 + 5.1 --------

Co-58 27 + 9 --------

Co-60 36 + 11 19 + 8 Cs-134 10 + 9 15 + 6 Cs-137 36 + 11 29 + 8

<370 500 + 150 Tritium Gross Beta (not requested) 59 + 12

, ;:::c:305-

Silt Samples

• Semi-annual silt collections occurred on March 15th and on September 23rd or October 29th. As in the past, the accumulation gave a .number of fission and activation products due to Surry Station liquid effluent. These radionuclides can be sutmnarized.

Mn-54 (pCi/kg) 9-23-76 Station Discharge 410 + 160 10-29-76 Station Intake 110 + 100 Co-58 (pCi/kg) 3-5-76 Point of Shoals 120 + 100 9-23-76 Station Discharge 940 + 200*

Co-60 (pCi/kg) 3-15-76 Point of Shoals 180 + 100 9-23-76 Station Discharge 2soo*+ 300 Cs-134 (pCi/kg) 3..;15-76. Station Intake*. 650 + 100 Point of Shoals 230 + 90 Station Discharge 180 + 110 Chickahominy 140 + 100 9-23-76 Station Discharge 1000 + 200 10-29-76 Station Intake 140 + 90 Cs-137 (pCi/kg) 3-15-76 Point of Shoals 1000 + 200 Newport News 340 + 100 Station Discharge 200 + 130 Chickahominy 450 + 170 9,-23-76 Station Discharge 3300 + 300 Chickahominy . 1100 + 200 10-29-76 Station.Intake 650 + 160 Newport News 560 + 160 Ce-141 (pCi/kg) 10 76 Station.Intake 560+ 320 A significant increase is noted at .the Station Discharge for the expected fission and activation products. The March, 1976 concen-

• trations were lower than those of March, 1975.

-306-Some activity.was "washed" down river with accumulation occurring again during 1976.

I

Oyster Samples

• Gamma spectrometry showed five expected fission and activation products in the quarterly oyster samples. Cobalt-58 was observed most frequently and a representation of the distribution and concentration of the total effluent can be given through this specific isotope.

Cobalt-58 (pCi/kg wet) 1-26-76 Newport News 38 + 21 Point of Shoals 40 + 22 Deep Water Shoals <35-3-11-76 Naseway Shoals 67 + 20 3-iS-76 Deep Water Shoal~ 46 + 36 Point of Shoals 30 + 23 5-11-76 Newport News <39-Point of Shoals 22 + 18 Deep Water Shoals 54 + 37 Samples collected in July, September, and November did not suggest the presence of cobalt-58. This indicates that radiological decay

~nd/or washout removed the isotope more rapidly than the oysters accununulated the activity. Neither the Chinese fallout nor the increase in sediment activity were reflected in analysis of the oyster samples. Any delay in the path from sediment to oysters would result in increasing concentrations during 1977.

The gamma spectrometry data can be used to fabricate a conservatively "typical oyster" by averaging the concentrations of the specific is~topes that could be attributed to Surry effluent.

Such an exercise yields:

Mn-54 32 pCi/kg Ru-103 22 pCi/kg Co-58 44 Ag-llOm 47 Co-60 24 Cs-137 40 An estimate of dose connnittment through one years consumption of these oysters can be made utilizing the model and assumptions of

• Regulatory Guide 1.109.

-397-

Dose Committment (mrem)

• Bone Liver Total Body 3.2 E-03 4.6 E-03 3.1 E-03 Kidney Lung GI-LL!

1. 6 E-03 4.9 E-04 5.4 E-03 The dose committments are low even though an appreciable fraction of the dose is attributable to cesium-137. Much, if not all, the cesium-137 is due to old fallout and not as an impact of Surry operations.

Clam Samples Gamma spectrometry yielded various concentrations of ten different fission and activation products. The three isotopes observed most frequently were cobalts-58 and 60 and cesium-137.

Cobalt-58 (pCi/kg) 1-13..:76 Lawnes Creek 24 + 14 Station Discharge 130 + 30 3'"'.15-76 Jamestown 62 + 24 Station Discharge Lawnes Creek* 190 + 40.

42 + 41 Hog Island Poiht Chickahominy 320 + 80 5-21-76 Chickahominy .

220 + 40 Hog Island Point 30 + 12 r 76 Station Discharge 97 + 36 Lawnes Creek

• 74 + 46 9-09-76 Jamestown 71 + 43 11-19-76 Lawnes Creek 32 + 25 42 + 27 Hog Island Point 34 + 33 Station Discharge 81 + 28 Cobalt-60 (pCi/kg) 1-13-76 Station Discharge 3-15--76 Station Discharge 68 + 22 7-22-76 45 + 36 Hog Island Point Station Discharge 100 + 50 Lawnes Creek 74 + 46 Jamestown 52 + 36 9-09-76 Station Discharge 40 + 29 81 + 48 Hog Island Point 42 + 38 11-19-76 Station. Discharge 88 + 30

-308-

Cesium-137 {J2Ci/kg}

• 1-13-76 3-15-76 Chickahominy Jamestown Station Discharge Jamestown Station Discharge Hog Island Point 19 17 26 19 29 71

+ 18

+ 16

+ 24

+ 18

+ 25

+ 45 Chickahominy 86 + 30 5-21-76 Chickahominy 25 + 14 Jamestown 26 + 21 Hog Island Point 30 + 28 Lawnes Creek 31 + 26 9-09-76 Lawnes Creek 40 + 31 Cobalt-58 and*cesium-137 levels appeared to be somewhat higher in the March samples. Three samples, from that same month, showed iodine-131 levels.

Station Discharge 28 +*26 Lawnes Creek 27 + 35 Hog Island Point 79 + 68 The only potential.indication of the Chinese fallout was the presence of zirconium-niobium-95 at 49 + 32 and 39 + 33 pCi/kg respectively.

To permit an ingestion dose estimate, one can proceed to construct a hypo_thetical clam using the same basis for the oyster dose estimate. Such a construction yields:

Mn-54 22 pCi/kg I-131 48 pCi/kg Co 97 Cs-134 33 Co-'60 66 Cs-137 35 Ag-llOm 37 Ce-144 100 The dose committment, based upon a one year adult consumption of such clams is given below. To temper the iodine-131 estimate, due to its short half life, that concentration was presumed constant for a two month period.

Dose Committment (mrem)

Bone* 4.9 E-03 Kidney 3.0 E-03

• Liver 9.1 E-03 Lung 9.5 E-04

Total Body 7.0 E-03 GI-LLI 2.3 E-02

• Thyroid Crab Samples

1. 6 E-02 Crab samples were collected near Surry Station intake during the season (July, August, and September). Cobalts-58 and 60 were measurable in the July and August samples.

Date Co-58 (pCi/kg) Date Co-60 (pCi/kg) 7-29-76 45 + 24 7 76 32 + 21 8-09-76 100 + 40 8-09-76 39 + 33

\

Annual consumption of a kilogram of crabs having an average*of the two concentrations given above, would yield a dose committment of:

Liver 1. 3 E- 04 mrem Total Body 2.8 E-04

.GI-LLI 2.5 E-03 Fish Samples The annual fish sampling occured on March 1st. The bottom feeder had manganese-54 with 200 + 110 pCi/kg. The free swimmer had cesium-137 with 78 +/- 57 pCi/kg. Extrapolation to an annual dose committment is tenuous however these single concentrations yield:

Bone 4.3 E-02 mrem Kidney 2.2 E-02 rnrern Liver 6.5 E-02 Lung 6.6 E-03 Total Body 3.9 E-02 GI-LLI 2.0 E-02 Soil Samples The annual soil sampling occured at the air sampling locations on August-24th. Naturally occuring radionuclides were observed and while several fission and activation products were suggested,

..... 310-

only cesium-137 was present in measurable concentrations .

• Surry Station Bacon's Castle Alliance pesium-137 (pCi/kg) 95 + 93 Hog Island Reserve 180 + 100 2400 + 300 280 + 90 Colonial Parkway Dow Fort Eustis Newport News

.1500 + 200 190 + 130 1800 + 200 200 + 120 Some non-specific fraction may have been deposited through gaseous effluent from Surry however the two closest in locations were comparably low. Bacon's Castle, Colonial Parkway, and Fort Eustis are clearly higher than the two other locations. This variation in cesium-137 concentrations from old fallout could be a result of a number of factors. In addition to the potential for non-uniform distribution on a local basis, construction may have removed initially deposited old fallout. Also, heavily vegetated locations t~nd to retain cesium-137 t~rough uptake within the plant including new growth nourished by dead and decayed vegetation.

Radiostrontium levels in the soil showed a single measurable strontium-89 level which was in the .Surry Station sample with 73 +/- 48 pCi/kg. Due to the relatively short half life and the relative abundance of strontium-89 expected in the effluent, one presumes the deposition was from the plant. Strontium-90 concentra-tions averaged 235 pCi/kg and ranged from 93 + 69 to. 720 + 60 pCi/kg ..

The latter sample was from Newport News which is most remote to the plant relative to the other sampling locations .

. Food Crop Samples

• Crops collected for analysis included corn(2 samples), peanuts, and soybeans. The only fission product observed through gannna spectrometry was cesium-137 in soybeans with 69 + 59 pCi/kg.

Since other samples, indicative of the gaseous effluent path, showed no

. -311-

significant contribution from Surry, one can presume that the above

• concentration is due to old fallout.

in the soybeans with 14 to be from old fallout.

+/- 12 pCi/kg.

Strontium-90 was detected Again, this can be presumed One corn sample, collected on 10-11-76, showed strontium-89

• at 48 +/- 26 pCi/kg. A corn sample collected on the following day, at the same farm, did not show strontium-89 and the sensitivity\.

of that particular analysis was 27 pCi/kg~ The strontium-89 may have been a component of the current Chinese fallout since air samples collected from 10-06-76 to 11-12-76 showed clearly elevated gross befa ac~ivity due to this fallo~t.

Fowl Samples The semi-annual fowl samples from the Hog Island Reserve included a goose *collected on 6-03-76 and a Blue Heron on 12-01-76.

Analysis of the goose showed only naturally occuring potassium-40.

The heron showed cesium-137 with 64 + 45 pCi/kg and barely detectable zirconium and nicobium-95 with respective concentrations of 75 + 74and less than 110 pCi/kg. No plant contribution is indicated.

Conclusion The radiological environmental surveillance program for Surry Power Station continued to pe.rmit documentation which included naturally occuring radionuclides, old and new fallout, and also plant contributed activation and fission products in various

• ~

environmental components.

Environmental dosimetry could not distinguish expected noble gas inmersion dose from the plant from ambient naturaf level. Net

exposure, compared to control dosimeter measurements, showed a

• total of 20.8 mR/yr at Hog Island Reserve(close in to the plant).

• The highest apparent exposure was at Smithfield with 41.6 mR/yr on the same basis relative to controls.

A number of analyses yielded sufficient information to permit conservative estimates of dose committment to man through Surry effluent. The sum of those reported in each of the previous sections of this report yields:

Dose Committment (mrem)

Bone 5.2 E-02 Kidney 2. 7 E-02 Liver. 8.0 E-02 Lu~g 3.2 E-02 Total Body 5.1 E-02 GI-LLI 5.4 E-02 Thyroid 1. 6 E-02

ANALYTICAL PROCEDURES

• Air Particulate Gross alpha and gross beta radioactivity measurements are made utilizing a Beckman Widebeta II low background (anti-coincidence proportional) counter. The minimum detectable levels (99.7% confidence) are approximately 0. 24 pCi p_er sample for alpha emitters and 0. 80 pCi per sample for beta emitters.

Air particulate samples are mounted in two inch planchets and counted directly.

Gannna spectrum analysis utilizes a lithium-drifted germanium

.detector with a sensitive volume of 55 cm 3 and a thin aluminium window. The detector is housed in a graded lead shield with an internal volume of eight ft 3 ; six inches of lead are at the bottom with four inches of lead on all sides and on top. The analyzer system is a Nuclear Data 4420 and ND812 computer housing a 20K memory for acquisition, storage, and manipulation of spectra and computer programs. The overall system has a resolution of 2.2 kev for the 1170 kev peak of cobalt-60 with a peak to compton ratio of 32:1.

Air particulate composites are fitted into a Petri dish and analyzed directly.

Ambient Radiation Thermoluminescent dosimeters of lith'ium flouride (TLD-100) are used to indicate*ambient background radiation as well as noble gases such as xenon. The chips are preselected by laboratory irradiation and measurement with criterion of+/- 4%. At low dose levels subsequent response can vary with + 6% typi_cal and with a

• range.of less than+ 10%. A standard annealing cycle is used with one hour at 400° C. Calibration of the overall system includes use

-314-

of* ionization chambers as directly received from calibration by the

• National Bureau of Standards.

for quality control comparison.

Each ~nnealing batch includes a packet The dose reported is that received between annealing and reading unless otherwise directed.

Well Water and Surface Water These water samples are treated identically as the precipitation samples. The major factor influencing the data is the fraction of the total sample analyzed.

Fowl The single coot samJ)le analyzed semi-annually is analyzed by high resolution gamma spectrometry on the Ge-Li system. Following separation of the flesh from feathers, bone and other organs, the sample is ground and dried. The minimum detectable activities are essentially equal to those of other dried organic materials.

Silt and Soil Samples Soil and silt samples are'analyzed in an identical manner. Samples are dried and seived through a number 11 U.S.A. Standard Testing Seive to remove pebbl.es and other foreign matter. The samples are tumbled to provide uniform mixing and aliquots of approximat~ly 100g are analyzed by high resolution gamma spectrometry. Representative sensitivities for various isotopes are:

zr..:95 0.1 pCi/g Nb-95 0.1 pCi/g Cs-137 0.1 pCi/g

. Pb-214 *1.0 pCi/g

• Bi.:.214 Ra-2.26

1. 0 pCi/g 9.0 pCi/g

• -* -315-

James River Water

• Water samples are analyzed by high resolution gannna spectrometry and also by an enrichment procedure for tritium. The gannna spectrometry is performed by slowly drying a one liter aliquot and counting the residue. The tritium aliquot is electrolytically enriched before liquid scintillation counting and has a sensitivity of 120 pCi/1. This sensitivity is more than adequate to document equilibrium concentration due to world-wide environmental inventories.

Aquatic and Marine Organisms Oysters and ~lams are analyzed by high resolution gamma spectrometry following grinding and drying~ Only the edible portion of the mollusks are analyzed. Fish entrails are removed and the remainder submitted to pressurized steam to.allow segregation of bone and flesh. The resultant sample weights are on the order of 10-20 grams. Typical resultant sensitivities are:

Zr-95 . 0. 8 pCi/g Nb-95 o.a pCi/g Sb-125 1.1 pCi/g Cs-137 0.4 pCi/g

• Ce-144 5.0 pCi/g Ra-226 10.0 pCi/g Precipitation An aliquot of the composite is counted directly for tritium activity via liquid scintillation. The minimum detectable activity is 1.0 pCi/ml. Gross beta analysis is performed by drying an aliquot, in a planche~. The dried planchet is counted directly in the Widebeta

• II. with a minimum detectable activity of 0.58 pCi per planchet.

-316-

• The fractions of the samples analyzed are then related to the

• total precipitation collected and the area of the sample collector with units reported as nCi/M 2

• Milk Samples Milk samples are analyzed for gamma emitters by high resolution gamma spectrometry. Minimum detectable activities are identical to those for water *samples. Samples are also analyzed for Sr-89, 90 and' calcium.

The strontium procedure includes separation by ion exchange with subsequent dried eluant counted on the Widebeta II system. An initial count with ari additional count several days later, identifies the Y-90 in-growth. The sensitivity for Sr-89 and 90 is approximately 2 pCi/1.

Stable calcium is measured

. . by a standard titration with a. sensitivity of 1 mg/1 for dosimetric techniques.

Milk samples are_analyzed for low concentrations of I-131 through

• • radiochemical analysis; sensitivity is approximately 0.25 pCi/1. Iodide carrier is added to the raw milk and ion exchange is used for the first step of purification. Sodium hypochlorite leached solution is treated

• with nitric acid and hydroxylamine. An organic extraction is effected and Ag! is precipitated. The precipitate is washed, dried, and the tared filter is counted on a low background proportional beta particle counter.* Recovery is based upon iodide carrier recovery .

• "\- -317-

EQUIPMENT

• Gross alpha, gross beta, Sr-89 and Sr-90 measurements are made using a low background Beckman Widebeta II equipped with shielding and anti-coincidence electronic to obtain very low background counting rates. Automatic absorber measurements are also available.

Tritium enrichment analysis has a minimum detectable concentration of tritium in water on the order of 0.10 pCi/ml. Tritium is determined using a Beckman Model LS-200 liquid scintillation counter with 5 ml of water in.Insta-Gel.scintillator. The MDA for this system without enrichment is. 0.6 pCi/ml based on a 100-minutes counting time,* but the practical reporting level is 1 pCi/ml. When values below 1 pCi/ml are required, the sample is electrolytically enriched (HASL procedure) prior to liquid scintillation counting.

The gamma spectrometry system utilizes a high resolution detection with efficiency and resolution suitable for counting environmental samples. The analyzer system is a Nuclear Data 4420 with ND-812 Computer with 20K memory for acquisition, storage, manipulation of spectra and programs. The Ge-Li detector is a right circular cylinder with a 40 mm diameter, drifted coaxially with an open end. The "P" core diameter is 6 nun and "N" layer thickness of 0.5 mm. An active area of 12.3 cm 2 faces the thin.aluminum window which permits analysts of photon energies a low a 35 kev. The resolution is 2.2 kev for the 1170 kev peak of Co-60 and the peak-to-compton ratio is 32:1 for Co-60

.gamma. The minimum detectable activities (MDA), based upon typcial samples for the type indicated are listed in Table IV. The reporting level is a function of spectrum complexity, detector resolution, and peak-to-compton ratio. One reason this particular system was selected for environmental samples was the excellent resolution and peak-to-

-  :..)18-

- 7.

compton ratio. The detector resides in a graded shield with eight 3

• ft interior and with four inches of lead on top.and sides and six inches on the bottom.

/

• -3*19-

• TABLE IV Typical Minimum Detectable Concentrations Ge-Li Gamma Spectrometry Air Samples cs~l34 1.6 X 10- 2 pCi/M 3 Cs-137 1. 6 X 10- 2 pCi/M 3 Ba-t40 5.2 X 10- 2 pCi/M.3 La-140 3.2 X 10- 2 pCi/M 3 .

Other Expected 1. 2 X 10- 2 to Gamma Emitters 1. 2 X 10- l pCi/M 3 Water Samples Cr-51 80 pCi/ 1 Co-58 8 pCi/1 Co-60 8 pCi/1 Mn-54 8 pCi/1 Cs-134 9 pCi/1 Cs-137 9 pCi/1 Ba-140 30 pCi/1 La-140 . 20 pCi/1

.Other Expected. 8 to Gamma Emitters 80 pCi/1

-Soil and Bottom Sediments Cs-134 35 pCi/kg (dry)

Cs-137 35 pCi/kg (dry) cr~51 280 pCi/kg (dry)

Co-58 30 pCi/kg (dry).

Co-60 30 pCi/kg (dry)

Mn-54 30 pCi/kg (dry)

Other Expected 30 to Gamma Emitters 300 pCi/kg (dry)

Fish, Benthus, and Aquatic Vegetation I-131 . 13 pCi/kg (wet)

Cs-134 14 pCi/kg (wet)

Cs-137 13 pCi/kg (wet)

Cr-51 110 pCi/kg (wet)

Co-58 12 pCi/kg (wet) co..:60 13 pCi/kg (wet)

Mn:..54 12 pCi/kg (wet)

. Other Expected 1 to Gamma Emitters* 120 pCi/kg (wet)

-320-

SUMMARY

OF SAMPLE DATA

• KEY INFORMATION FOR TABLES . . . . . .

'AIR PARTICULATE SAMPLES ....

. ........................... . . 35 PAGE

.33 Gross Beta Concentrations. . ......................... . . 35 Gross Alpha Concentrations ............... . . . . . . . . . . . .. . . 53 Gamma Spectrometry - Quarterly Composites * . . . . . . . . . . . . . . 61 AMBIENT THERMOLUMINESCENT DOSIMETRY . . . . . . . . . . . . . . . . . . . . . . . . . . 69 PRECIPITATION SAMPLES *...................... . .......... . . 73 MILK S.AMPLES . ................................. . . .......... . . 75 WELL WATER SAMPLES. .. . . . . . .................................. . . 112 SURFACE WATER SAMPLES. . .............................. . .114 JAMES RIVER WATER SAMPLES .. . . . . . . ........................ . . 116 SPECIAL WATER SAMPLES *.. . . . . . . . . . .. . . . ................... . . 137 SILT SAMPLES ... ......................................... . . 139 OYSTER SAMPLES. ............................................. .145 CLAM SAMPLES . . . . .

. . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 156 CRAB SAMPLES . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 174 FISH SAMPLES .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 177 SO IL SAMPLES .. .178 FOOD CROP SAMPLES *. .182 FOWL SAMPLES. . ......................... . . ........ 186

• -:..321-

KEY INFORMATION FOR TABLES

1. Where data can range over several orders of magnitude, concentrations are expressed as powers of ten using E notation. For example E-03 is 10- 3 *

2. Error terms are expressed as two standard deviations (95% confidence) for EIC data; zero values have three standard deviation error terms (99. 7% confidence).

3. Where shown, averages are based upon measurable data, that is where two standard deviations are smaller than the calculated value.

These averages should be used only as presented; averages *among different sampling locations only,present a basis for relative variability. The sequence in time is also an important factor.

4. The exact minimum detectable concentrations are variable dependent upon many factors such as complexity of a spectrum, quantity of the sample, etc. In order to maximize the value of the analysis, certain concentrations are reported as less than a given value. These data are reported through two methods.

a. Frequently the analyses present information, such as a gannna spectrum peak, where the calculation error term at 95% confidence is larger than the calculated value.

One can discern a very finite probability for the presence of that isotope. In these cases, the error term is increased to permit 99.7% confidence and the result is divided by sample size to yield concentration.

b. One can expect certain isotopes to be present in a sample due to the nature of that sample. This is especially

• true when a member of a class of samples has definite data, but other members of the class do not exhibit the same information. Likewise, one can observe a small

-322-

concentration of one member of a parent-daughter pair without observing the other member which is obviously present. In these cases (always represented by the lowest "less than" concentrations) the value reported is based upon _three standard deviations (99.7% confidence) of the instrument background with a blank sample in the counting geometry .

• . ***-*- .-::323-

AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

• - Date Collected

~'i 76 Volume/

Cu. M.

238 Surry Station Gross Beta

0. 0 + 4. 7. E-03 1-27-76 322 5.7 +0.6 E-02 2-10-76 302 1. 6 + 0. 4 E-02 2-24-76 302 8.0 +/- 3.9 E-03 3-10-76 302 5 .. 6 + 0. 6 E-02 3-23-76 262 6.0 + 0.6 E-02 4-.5- 76 251 8.8 + 0.9 E-02 4-20-76 313 1.2 + 0.1 E-01 5-4-76 302.4 5.3 + 0.7 E-02 5-18-76 282 l.O+O.lE-01 6-3-76 345 4.3 + 0.5 E-02 6-15-76 259 l.2+0.lE-01 6-30-76 324 4.4 + 0.5 E-02 Average 6.4 E-02 Maximum 1.2 + 0.1 E-01 Minimum 8.0 + 3.9 E-03

• -324-

• AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Surry Station Date Volume/ Gross Collected Cu. M. Beta 7-13-76 280.8 4. 7 + 0.5 E-02 7-27-76 302.4 5.9 + 0.5 E-02 8-10-76 302.4 4.0 + 0.4 E-02 8-24-76 302.4 4. 7 + 0.5 E-02 9-07-76 302.4 6. 7 + 0.5 E--02 9-22-76 324 6.4 + 0.5 E-02 10-06-76 324 7.6 + 0.6 E-02 10-21-76 324 5.0 + 0.1 E-01 11-02-76 259.2 3.5 + 0.1 E-01 11-17-76 *k 5.3 + 0.1 E+Ol 11-21-76 86.4 3. 0 + 1.1 E-02 11-30-76 . 194.4 1. 5 + 0.1 E-01 12-14-76 302.4 1. 3 + 0 .1 E-01 12-27-76 *( 1. 3 + 0.1 E+O 1 Average 1. 3 E-01 Maximum 5.0 + 0.1 E-01 Minimum 3. 0 + 1. 1 E-02

• N, volume given; results in picocuries per sample

• *'°' !:,ampler malfunction; results in picocuries per sample

-325-

AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

• Date Collected 1-13-76 Volume/

Cu. M.

246 Hog Island Gross Beta 1.4+0.5 E-02 1-27-76 282 3.2 + 0.5 E-02 2-10-76 282 2.2 + 0.5 E-02 2-24-76 302 8.3 + 3.9 E-03 3-10-76 202 0.0 + 5.5 E-03 3-23-76 262 9.1 + 4.4 E-03 4-5-76 Sampler Malfunction 4-20-76 127 5.8 + 1.3 E-02 5-4-76 221. 8 0. 0 + 4. 8 F- ')3 5-18-76 222 5. 4  :+: 4 . 6 .*>

1 03 6-3-76 31~5 7.9 + 3.4 E-03 6-15-76 207 2.0 + 0.6 E-02 6-30-76 3?4 1.6+0.4E-02 A\ eragc 1. 9 E-02

?-fr ximum 5. 8 + 1. 3 E-02 Mjnimum 5.4 + 4.6 E-03

• -32(-

• AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Hog Island Date *volume/ Gross Collected Cu. M. Beta 7-13-76 280.8 1.8 + 0.4 E-02 7-27-76 302.4 2.8 + 0.4 E-02 8-10-76 302.4 1.9 + 0.4 E-02 8-24-76 . 241. 9 2.0 + 0.4 E-02 9-07-76 221. 7 3.3 + 0.5 E-02 9-22-76 216 3.7 + 0.6.E-02 10-06-76 324 5.7 + 0.5 E-02 10-21-76 216 1. 2 + 0. 1 E-01 11-02-76 172.8 1. 2 + 0.1 E-01 11-17-76 216

• 1. 0 + 0. 1 E-01 11-21-76 57-. 6 2.5 + 0.3 E-01

.11-30-76 155.52 5.9 + o.-8 E-02 12-14-76 241.92 4.6 + 0.6 E-02 12,-27-76 187.2 3.4 + 0.6 E-02 Average 6.7 E-02 Maximum 2.5 + 0.3 E-01 Minimum 1. 8 + 0. 4 E-02

-327-

VEPCo AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Alliance I Dat~ Volume/ Gross Col.Lected Cu. M. Beta 1-13-76 222 "1.6+0.6 E-02 1-27-76 242 1.3 + 0.5 E-02 2-10-76 282 4.3 + 0.6 E-07.

2-2l1.-76 282 4.5 + 0.6 E- ,,*.~

3-10-76 302 3.8 + 3.6 E-03 3-23-76 262 2.9 + 0.5 E-02 4-5-76 262 3o4 + 0. 7 E-02 4-20-76 281 7.9 + 0.8 E-02 5-4-76 222 4.9 + 0.8 E-02 5-18-76 222 5.6 + 0.7 E-02 6-3-76 323 4.5 + 0.6 E-02 6-15-76 242 6.5 + 0.7 E-02 6-30-76 324 3.5 + 0.5 E.:.02 Average 3.9 E-02 Maximum 7.9 + 0.8 E-02 Minimum 3.8 + 3.6 E-03

• -328-

• AIR PARTJ :ULATE ,.AMPLES GROSS I '.TA At*: i,YSIS (picocuries * *er c, * ; c meter)

. AJ ianc*

Date Volume/ Grr-Collected Cu. M. Bet.

7-13-76 280.8 4. t~ *) . 9 E-03 7-27-76. 302.4 4.4 U.5 E-02 8-10-76 302.4 4.8 + 0.5 E-02 8-24-76 302.4 3.3 + 0.4 E-02 9-07-76 302.4 3.7 + 0.4 E-02 9-22-76 324 1. 9 + 0. 3 E-02 10-06-76 302 2.7 + 0.4 E-02 10-21-76 345. 6

• 1.4 + 0.1 E-01 1 i 76 259.2 11-17-76 2.7 + 0.1 E-01 324 . 1. 1 + 0. 1 E-01 J 1 76 11-30-76 86.4 194.. 4 1. 3 + 0. 2 E-01 6.4 + 0.7 E-02 12-14-76 302.4

• 1. 3 + 0. 3 E-02

. 12-27-76 271. 44 5.6 + 0.5 E-02 Average . 7 .1 E-02 Maximum 2.7 + 0.1 E~Ol MinimUID 4.4 + 2.9 E-03

-329-

VEPCo AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Bacon's Castle Date Volume/ Gross Collected Cu. M. Beta 1-13-76 262 0.0 + 4.2 E-03 1-27-76 262 0.0 + 4.2 E-03 2-10-76 282 0.0 + 3.9 E-03 2-24-76 242 0. 0 + 4 .. 6 E-03 3-10-76 302 1.0 + 0.4 E-02 3-23-76 281 4.2 + 0.6 E-02 4-5-76 281 2.1 + 0.6 E-02 4-20-76 324 4.6 + 0.6 E-02 5-4-76 302.4 0.0 + 4.3 E-03 5-18-76 302 0.0 + 3.3 E-03 6-3-76 323 0.0 + 3.1 E-03 6-15-76 259 0. 0 + 3. 8 E-03 6-30-76 378 1.5 + 0.3 E-02 Average 2.7 E-02 Maximum 4.6 + 0.6 E-02 Minimum 1.0 + 0.4 E-02

• -330-

AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS_

(picocuries per cubic meter)

• Date Collected Volume/

Cu. M.

Bacon's Castle Gross Be*ta 7-13-76 280.8 3.0 + 0.4 E-02 7-27-76 302.4 3.3 + 0.4 E-02 8-10-76 302.4 2.1 + 0.4 E-02 8-24-76 302.4 2.3 + 0.4 E-02 9-07-76 322.5 2.8 + 0.4 E-02 9-22-76 324 2.8 + 0.4 E-02 10-06-, 76 302 2.8 + 0.4 E-02 10-21-76 345.6 1.8 + 0.1 E-01 11-02-76 259.2 2.0 + 0.1 E-01 11-17-76 324 - 3.3 + 0.4 E-02 11-21-76 86..4 1. 4 + 0. 2 E-01 11-30-76 181. 44 8.2 + 0.8 E-02 12-14-76 282.24 6.6 + 0.6 E-02 12-27-76 299.52 4.1 + 0.5 E-02 Average 6.7 E-02 Maximum 2.0 + 0.1 E-01 Minimum 2.1 + 0.4 E-02

• -332-

AIR PhRTI<.ULATE SAMPLES GRo:;s BETA ANALYSIS

. Date Collected (picocuries per cubic meter)

Volume/

Cu. M.

Colonial Parkwar Gross Beta 1-13-76 190 2.7 + 0.7 E-02 1-27-76 262 o.o.+ 4.2 E-03 2-10-76 282 0.0 + 3.9 E-03 2-24-76 282 0.0 + 3.9 E-03 3-10-76 282 l.7+0.5E-02 3-23-76 262 1.9 + 0.5 E-02

!+ 76 262 9.2 + 5.9 E-03

\-20-76 281 7.6 + 4.8 E-03 i-4-76 242 0.0 + 5.3 E-03 j-18-76 222 0.0 + 4.5 E-03 6-3-76 323 0.0 + 4.0 E-03 6 76 173 0.0 + 5.8 E-03 6-3'0-76 378 2.0 + 0.4 E-02 Average 1. 7 E-02 Maximum 2.7 + 0.7 E-02 Minimum 7.6 + 4.8 E-03

• -333-

• AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Colonial Parkway Date Volume/ Gross Collected Cu. M. Beta

\

7-13-76 327.6 2.2 + 0.4 E-02 7-27-76 302.4 3.2 + 0.4 E-02 8-10-76 302.4 2.2 + 0.4 E-02 8-24-76 302.4 2.6 + 0.4 E-02 9-07-76 282.2 3.0 + 0.4 E-02 9-22-76 324 4.0 + 0.4 E-02 10-06-76 302 3.3 + 0.4 E-02 10-21-76 345.6 1.6+0.lE-01 11-02-76 345.6 2.4 + 0.1 E-01 11-17-76 432

• 9.0 + 0.5 E-02 11-21-76 11S.. 2 1.6 + 0.1 E-01 11-30-76 259.2 9.9 + 0.7 E-02 12-14-76 403.2 1.1 + 0.6 E-01 12-27-76 308.88 Ll + 0.3 E-02 Average 7. 7 E-02 Maximum 2.4 + 0.1 E-01 Minimum 1. 1 + 0. 3 E-02

-334-.

VE;PCo AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS

• Date Collected (picocuries per c~bic meter)

Volume/

Cu. M.

Dow Gross Beta 1-13-76 222 1. 7 + 0. 6 E-02 1-27-76 242 2.2 *+ 0.5 E-02 2-10-76 282 1.7 + 0.4 E-02 2-24-76 302 1.1 + 0.4 E-02 3,;,10:... 76 282 9.8 + 4.2 E-03 3"."23- 76 299 7.4 + 3.9 E-03 4-5-76 Sampler Malfunction.

4-20-76 259 8. 4 + 5. 2 E- (; 1 5-4-76 221. 7 0.0 + 5.8 E- ~ 1 5-18-76 202 o. o + 4. 9 r-- : ,

6-3-76 345 6.0 + 3.9 E-03 6-15-76 259 6.8 + 4.0 E-03 6-30-76 324 1.2 + 0.4 E-02 Average 1. 2 E-02 Maximum 2.2 + 0.5 E-02 Minimum 6.0 + 3.9 E-03

-335-

• • i

\

AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Dow Date Volume/ Gross

, Collected Cu. M. Beta 7-13-76 280 *, 8 1.4 + 0.4 E-02 7-27-76 302.4 1. 9 + 0. 4 E-02 8-10-76 302.4 1. 8 + 0. 4 E-02 8-24-76 302.4 2.6 + 0.4 E-02 9-07-76 302.4 3. 1 + 0. 4 E-02

• I 9 76 3?\ 3.0 + 0.4 E-02 10-06-76 2 i~2 3.8 + 0.5 E-02 10-21-76 3115. 6 1.4 + 0.1 E-01 11-02-76 259.2 2.2 + 0.1 E-01 11-17-76 321+ 1.0 + 0.1 E-01.

11-21-76 86.4 1.5 + 0.2 E-01 11-30-76 19!,. 4 8.3 + 0.8 E-02 12-14-76 30 *'., 8.0 + o.6 E-02 12-i7-76 2 7 1.* t14 4.7 + 0.5 E-02 I

Average 7.1 E-02 I' Maximum 2.2 + o.*1 E-01

• Minimum 1.4 +/- 0.4 E-02 I .

' II

-336-

VEPCo AIR PARTICULATE SAMPLES.

GROSS BETA ANALYSIS

• Date Collected (picocuries per cubic meter)

Volume/

Cu. M.

Fort Eustis Gross Beta r

1-13-76 158 2.1 + 0.8 E-02 1-27-76 222 0.0 + 5.0 E-03 2-10-76 202 0.0 + 5.5 E-03 2-24-76 342 5.9 + 3.3 E-03 3-10-76 403 3.1 + 0.4 E-02 3-23-76 355 2.8 + 0.4 E-02 4-5-76 262 2.7 + 0.7 E-02 4-20-7~ 281 4.1 + 0.6 E-02 5-4-76 262 2.2 + 0.6 E-02 5-18-76 202 5.3 + 5.0 E-03 6-3-76 345 0.0 + 3.8 E*03 6-15-76 242 1.4 + 0.5 E-02 6-30-76 324 2.7 + 0.4 E-02 Average 2.2 E-02 Maximum 4.1 + 0.6 E-02 Minimum 5.3 + 5.0 E-03.

-337-

• AIR PARTICULATE SAMPLES GRoss* BETA ANALYSIS (picocuries per cubic meter)

Fort Eustis Date Volume/ Gross Collected Cu. M. Beta 7-13-76 280.8 1.5 + 0.4 E-02 7-27-:-76 302.4 2.1 + 0.4 E-02 8-10-76 302.4 2.2 + 0.4 E-02 8-24-76 '~ 1.1 + 0.8 E+OO 9-07-76 322.5 2.1 + 0.4 E-02 9-22-76 324 3.1 + 0.4 E-02 10-06-76 302 3.4 + 0.4 E-02 10-21-76 403.2 l.3+0.lE-01 11-02-76 259.2 9.6 + 0. 7 E-02

• 11-17-76 324 *2.1 + 0.4 E-02 ll"'.'21-76 86-. 4 3.5+1.lE-02 11-30-76 194.4 6.6 + 0. 7 E-02 12-14-76 302.4 6.6 + 0.6 E-02 12-27-76 336.96 + 0.4. E-02 5.0 .- '

Average_ 4.7 E-02 Maximum l.3+0.lE-01 Minimum 1. 5 + 0. 4 E-02

• *Per Sample - *sampler out.

-338-

• VEPCo AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Ne!!Eort News Date Volume/ Gross Collected Cu. M Beta 1-13-76 206 2.5 + 0.6 E-02 1-27-76 262 0.0.+ 4.2 E-03 2-10-76 282 0.0 + 3.9 E-03 2-24-76 300 3.6 + 0.5 E-02 3-10-76 282 3.8 + 0.5 E-02 3-23-76 279 3.8 + 0.5 E-02 4-5-76 255 0.0 + 5.9 E-03 4-20-76 324 9.3 + 4.3 E-03 5 76

• 302.4 5.4 + 3. 7 E-03 5-18-76 363 1.0+0.3.E-02 6-3-76 345 1.6 + 0.4 E-02 6-15-76 130 2.0 + 0.8 E-02 6-30-76 130 0.0 + 7.7 E-03 Average 2.2 E-02 Maximum 3.8 + 0.5 E-02 Minimum 5.4 + 3.7 E-03

• -339-

• AIR PARTJ :ULATE SAMPLES GROSS J ~TA ANALYSIS (picocuries per cubic meter)

New, ,ort News Date Volume/ Gross Collected Cu. M. Beta 7-13-76 280.8 2.6 + 0.4 E-02 7-27-76 302.4 3.1 + 0.4 E-02 8-10-76 302.4 2.8 + 0.4 E-02 8-24-76 282.2 2.0 + 0.4 E-02 9-07-76 302.4 1.7 + 0.4 E-02 9-22-76 324 2.5 + 0.4 E-02 10-06-76 262 4.3 + 0.5 E-02 10-21-76 3L~5. 6 5.1 + 0.1 E-01 11-02-76 259.2 2.3 + 0.1 E-01 11-17-76 324 5.3 + 0.5 E-02 11-21-76 86.4 1. 2 + 0. 2 E-01 11-30-76 191+. 4 6.6 + 0. 7 E-02 12-14-76 302.4 6.8 + 0.6 E-02 12-27-76 262.08 6.6 + 0.6 E-02 Average 9.3 E-02 M2ximurn 5.1 + 0.1 E-01 Minimum 1.7 + 0.4 E-02

• -.340-

AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Average of All Stations Date Collected 1-13-76 2.0 E-02 (6/8 Stations Detectable) 1-27-76 3.1 E-02 (4/8) 2 76 2.4 E-02 (4/8) 2-24-76 1. 9 E-02 (6/ 8) 3"".10-76 2.4 E-02 (7 / 8) 3-23-76 2.9 E-02 (8/8) 4-5-76 . 3. 6 E-02 (5/ 8) 4-20-76 4.6 E-02 (8/ 8) 5-4-76 3.2 E-02 (4/ 8) 5-18-76 3.4 E-02 (5/ 8) 6-3-76 2 . 4 E-02 (5/ 8) 6-15-76 4.1 E-02 (6/ 8) 6-30-76 2.L~ E--02 (7 / 8)

Average 2.9 E-02 Maximum Aver ::1ge 4.6 E-02 Minimum Average 1. 9 E-02

-341~

• AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS (picocuries per cubic meter)

Average of All Stations Date Collected 7-- LI- 76 2.2 E-02 7-2* 1 -76 3.3 E-02 8-1 l-76 2.7 E-02 8-2 1-76 2.8 E-02 9-07-76 3.3 E-02 9-2'.-76 3.4 E-02 10- '6-76 4.2 E-02 10- 1-76 2.3 E-01 11-(12-76 2.2E-Ql*

11-17-76 7.3 E-02 11-21-76 1. 3 E-01 11-30-76 8.4 E-02 12-14-76 7.2 E-02 12-27-7.6 4.4 E-02 Average 7.6 E-02 Maximum 2.3 E-01 Minimum 2.2 E-02

-342-

• AIR PA1 TICULATE SAMPLES GROSS ALPHA ANALYSIS (picocuri, s per cubic meter)

Surry Station Date Volume/ Gross Collected Cu. M. Alpha 1 76 238 1.51 + 0.94 E-03 1-27-76 322 4. 18 + 1. 30 E-03 2-10-76 302.4 6.92 + 7.13 E-04 2-24-76 302 5.94 + 7.40 E-04 3-10-76 302.4 2.87 + 1.06 E-03 3-23-76 262 2.17 + 1.12 E-03 4-05-76 281 8.51 + 9.02 E-04 4-20-76 313 1. 34 + 0. 97 E-03 5-04-76 302.4 . 1.28 + 1.06 E-03 5-18-76 282 2.23 + 0.97 E-03 6-03-76 345 1. 04 + 0. 65 E--03 6-15-76 259 3. 12 + l. 20 l,>03 6-30-76 324 2.03 + 0.[37 E-03 7-13-76 230.8 1.06 + 0.95 E-03 7~27-76 30'.'. 4 9.83 + 6.25 E-04\

8-10-76 JO':.\ 1.68 + 0.81 E-03 8-24-76 J () '.' . '1 3. 76 + 1.22 E-03 9-07-76 3 () . 11 1. 98 + 2. 79 E-04 9-22-76 ') *')

._),.. 1. 94 + 8. 45 E-04 10-06-76 3. 33 + 1. 22 E-03 10-21-76 2. 49 + 1. 09 E- 03 11-02-76 2'.5::1 21 1. 50 + 1. 06 E-03 11-17,-76 32L1. 2.12 + 0.92 E-03 11-21-76 86.4 3.45 + 11.98 E-04 11-30-76 194.4 3.38 + 1.51 E-03 12-14-76 302.4 3.46 + 1.20 E-03 i2-27-76 SAMPLER NOT WORKING

-JL13-

• AIR PARTICULATE SAMPLES GROSS ALPHA ANALYSIS (picocuries per cubic meter)

Hog Island Date Volume/ Gross.

Collet ed Cu. M. Alpha 1 7G 246 3.10 + 1.27 E-03 1-27-76 282 2.65 + 1.14 E-03 2 76 282 Less than 5.51 E-04 2 76 302 2.97 + 6.56 E-04 3 76 201.6 5.93 + 5.93 E-04 3 76 262 1.14 + 0. 60 E-03 4:..05- 76 PUMP NOT OPERATING OVER SAr1PLING PERIOD 4 76 127 4.71 + 17.61 E-04 5.-04-- 76 221. 8 *Less than 1.14 E-03 5 76 222 5.38. + 5.38 E-04 6 76 323 3.70 + 4.53 E-04 6 76 207 2.89 + 4.08 E-04 6 76 324

• 6.46 + 4.88 E-04 7..:13- 76 280.8 5.32 + 8.24 E-04 7 76 302.4 1. 48 + 0. 77 E-03 8 76 302~4 1~28 + 0.71 E-03 8 76 . 241. 9 1. 73 + 0. 92 E-03 9 76. 221.7 4.04 + 4.67 E-04 9-22-76 216 2.91 + 1.27 E-03 10-06-76 324 1.20 + 0.85 E-03 10-21-76 216 1. 80 + 1. 27 E-03 11-02-76 172.81 0 + 9.78 E-04 11.:.17-76 216 6.92 + 7.32 E-04 11 76 57.6 4.66 + 3.44 E-03 11 76 155~52 1. 34 + 1. 15 E-03 12-14-76 241. 92 1. 85 + 1. 02 E-03 12-27-76 187.2 4.79 +/- 10.6 E-04

-344-:-

• AIR PARTICULATE SAMPLES GROSS ALPHA ANALYSIS (picocuries per cubic meter)

Alliance Da:te Volume/ Gross Collected Cu. M. Alpha 1-13-76 222 2.29 + 1.10 E-03 1-:27-76

• 242 7.41 + 7.81 E-04 .i 2-10-76 t82 3.76 + 1.38 E-03 2-24-76 282 3.18 + 1.31 E-03 3-10-76. 302.4 5.93 + 4.84 E-04 3-:-23-76* 262 5.02 + 1.61 E-03 4-5-76 262 1.48 + 1.09 E-03 4-20-76 . 281* 2.66 + 1.29 E-03

. 5-04-76 222 2.15 + 1.52 E-03 5-18-76 222 2. 56 +/- 1. 17 E-03 6-03-76 323 1.67 + 0.83 E-03 6-15-76 242 .* 3.21 + 1.25 E-03 6-30 324 1.01 + 6.11 E-03 7-13-76 280.8 Less than 7.14 E-04 7 76 302.4 1.48 + 0. 77 E-03 8~10-76 302.4 4.45 + 1.33 E-03 8-24-76 302.4 5.83 + 1.52 E-03 9 76 302~4 2.21 + o.~s E-03 9-22-76 324 4.61 + 4.12 E-04 10 76 302 2.98 + 6.56 E-04

• 10 76 345.6 1.47 + 0.86 E-03 ll"'.2-76 259.21 2.54 + 1.26 E-03 11-17..:.76 324 *1.20 + 0.71 E-03 11-21-76 86.4 1.73 + 1.83 E~03 11-30-76 194 .. 4 9.22 + 8.69 E-04 12-14"'. 76 302.4 2.37 + 1.01 E~03 12-27-76 271. 44 4.40 + 7*.62 E-04

- -345-

• AIR PARTICULATE SAMPLES GROSS ALPHA. ANALYSIS (picocuries per cubic meter)

Bacon's Castle Date Volume/

• Gross Collected Cu. M. Alpha 1-13-76 262 2.28 + 4.56 E-04 1.-27-76 262 0 + 3.23 E-04 2-10-76 282 1.06 + 5.61 E-04 2-24-76 242 0 + 6.99 E-04 3-10-76 302.4 3.95 + 3.95 E-04 3-23-76 281 2.87 + 1.22 E-03 4 76 281 9.57 + 9.27 E-04 4-20-76 324 1. 75 +*1.03 E-03 5-0 ',- 76 302.4 . Less than 8. 38 E-04 5-13-76 302 9.89 + 19.79 E-05 6-03-76 323 9.25 + 32.05 E-05 6-15-76 259 3.46 + 4.00 E-04 6-30-76 378 4~ 74 + 3.87 E-04 7 76 280.8 9.58 + 9.18 E-04 7"-27-76 302.4 6.92 + 5.22 E-04 s lo- 76 302.4 1.48 + 0.77 E-03 8 21~- 76 302.4 3.36 + 1.15 E-03.

9-IJ 7-76

• 322.5 3.61 + 1.16 E-03 9-* *-') 2---. 7* 6 324 1.84 + 2.61 E-04 10*-06-76 302 4.96 + 7.13 E-04 10-21-76 345.6 1.73 + 0.92 E-03 11-02-76 259.21 4.61 + 7.99 E-04 11-17-76 324 3.68 + 4.52 E-04 11---21-76

• 86.4 6.91 + 13.83 E-04 ll-]0-76 181. 44 9.88 + 9.32 E-04 12-14,-76 282.24 2.65 + 1.10 E-03 1.2 76 299.52 1.50 + 0.96 E~03

-346-

• AIR PARTICULATE SAMPLES GROSS ALPHA ANALYSIS.

(picocuries per cubic meter)

Colonial Parkwar Date Volume/ Gross Collected Cu. M. Alpha 1-13-76 190 4. 71 + 7.03 E-04 1-27-76 262 Less than 4.84 E-04 2-10-76 282 1. 06 + 5. 61 E-04 2-24-76 282 3.18 + 7.02 E-04 3-10-76 282.2 2.12 + 2.99 E-04 3-23-76 262 0 + 5.59 E-04 4-05-76 262 Less than 1.65 E-04 4-20-76" 281 Less than 9.58 E-05 5-04-76 242 . Less than 1.05 E-03.

5-18-76 222 4.04 + 4.66 E-04 I 6-03-76 323 L~ss than 2.78 E-04 6-15-76 173 3.45 + 4.89.E-04 6-30-'-76 378 6.32 + 4.47 E-04 7-13-76 327.6 5.47 + 7.29 E-04 7-27-76 302.4 1.58 + 0.79 E-03 8-10-76 302.4 1.19 + 0.68 E-03 8-24-76 302.4

• 3.26 + 1.14 E-03 9-07-76 282.2 2.54 + 1.04 E-03 9-22-76 SAMPLER FAILED 10 76 302 9.90 + 8.39 E-04 10~21- 76

• 345.6 1.12 ! 0.79 E-03 11-02-76 345.61 1. 73 + 5.47 E-04 11-17-76 432 1.31 + 0.63 E-03 11-21-76 . 115. 2 2.33 + 1.72 E-03 11 76

• 259. 2 1. 27 +/- O. 83 E-03 12-14-76 403.2 9.63 + 5.74 E-04 12-27-76 308.88 Less than 1.74 E-03

-347-

• . AIR PARTI LATE SAMPLES GROSS AL, '\ ANALYSIS (picocuries p ,* cubic meter)

Dow Date Volume/ Gross Collected Cu. M. Alpha 1 76 222 2.15 + 1.14 E-03 1-27-76 242 1.98 + 1.10 E-03 2-10-76 282 2.12 + 1.08 E-03 2-24-76 302 8.91 + 8.16 E-04 ~

3-10-76 282.2 7.41 + 5.60 E-04 3-23-76 299 0 + 4.90 E-04 4-05-76 SAMPLER FAILED 4-20-76 259 Less than 9.58 E-05 5 76 221.8 Less than 1.14 E-03 5-18-76 202 4.44 + 5.12 E-04 6-03-76 345 3.46 + 4.24 E-04 6-15-76 259 6.92 + 5.65 E-04 6 76 324 3.69 + 3.69 E-04 7-'13-76 280.8 5.32 + 69 E-05 7-27-76 302.4 7.91 + 5.59 E-04 8-10-76 302.4 1.58 + 0. 79 E-03 8-24-76 302.4 4.05 + 1.27 E-03 9-07-76 302.4 2.96 + 1.08 E-03 9-22-76 DATA DROPPED 10-05-76 282 2.13 + 6.70 E-04 10-21-76 345.6 9.51 + 7.54 E-04 11-02-76 259.21 2.07 + 1.18 E-03 11-17-76 324 2.03 + 0.90 E-03 11-21-76 .86.4 1.38 + 1.69 E-03 11-30-76 194.4 . 1.23 + 0.97 E-03 12-14-76 302.4 1.38 + 0.79 E-03 12-27-76 271.44 5.50 + 7.94 E-04

-348-

• AIR PARTICULATE SAMPLES GROSS ALPHA ANALYSIS (picocuries per cubic meter)

Fort Eustis Date Volume/ Gross Collected Cu. M. Alpha la..13- 76 158 1.89 + 1~31 E-03 l-2f-76 221. 7 1~35 + 6.03 E-04 2-10-76 201. 6 1.48 + 7.84 E-04 2-24-76 342 5.24 + 6.54 E-04 3-10-76 403.2 2.97 + 2.96 E-04 3-23-76 355 5.05 + 5.83 E-04 4.:.05-76 262 Less than 7.65 E-04 4-20-76 281 1.17 + 1.02 E-03 5-04-76 262 Less than 9.68 E-04 5-18-76 20~ 2.96 + 4.18 E-04 6-03-76 345. 2.60 + 3.87 E-04 6 76 242 6.64 + 6.53 E-04 6-30-76 324 9.22 + 5.83 E-04 7-13-76 280.8 Less than 7~14 E-04 7-27-76 302.4 1.48 + 0.77 E-03 8 76

• 8-24-76

• 302.4 1. 58 +/- 0. 79. E-03 SAMPLER FAILED 9-07-76 322.5 3. 89 + 1. 2 E-03 9-22-76 324 1.75 + 0.80 E-03 10-05-76 302 2.98 + 6.56 E-04 10-21-76 403.2 9.63 + 6.79 E-04 11-02-.76 259.21 1.38 + 1.03 E-03 11-17-76 324 9.22 + 31.95 E-05 11-21"'."76 86.4 2.07 + 1.96 E-03 11-30-76 194.4 6.15 + 7.53 E-04 12-14-*76 302.4 9.88 + 34.2 E-05 12-27-76 336.96 5.32 + 6.64 E-04

-349-

• AIR PARTICULATE SAMPLES GROSS ALPHA ANALYSIS (picocuries per cubic meter)

Newport News Date Volume/ Gross Collected Cu. M . . AlphB:

1-13-76 206 1.16 *+ 0.92 E-03 1-27-76 262

• 4.56 + 6.45 E-04 2-10-76 282 0 + 5.19 E-04 2-24-76 300 3.49 + 1.31 E-03 3-10-76 282.2 1.80 + 0.87 E-03 3-23-76 279 1.50 + 0.96 E-03 4-05-76 255 9.37 + 9.94 E-04 4-' 76 324 Less than 9.58 E-05 5-04-76 302.4 Less than 8.38 E-04 5-18-76 363. 4.94 + 4.03 E-04 6-03-76 345 2.60 + 3.87 E-04 6-15-76 130 3.68 + 1.84 E-03 6-30-76 130 9.19 + 9.19 E-04 7-13-76 280.8 5.32 + 8.24 E-04.

7-27-76 302.4 7.91 + 5.59 E-04 8-10-76 302.4 7.91 + 5.59 E-04 8-24-76 282.2 2. 54 + 1. 04 E-03 9-07-76 302.4 1.52 + 0~25 E-02 9-22-76 324 1.66 + 0.78 E-03 10-05-76 262 1.14 + 0.97 E-03 10-21-76 345.6 1.64 + 0.90 E-03 11-02-76 259.21 1.96 + 1.15 E-03 11~17-76 324 1.01 + 0.67 E-03 11-21-76 86.4 1.04 + 1.55 E-03 11-30-76 194.4 2.61 +/- 1.34 E-03 12-14-76 302.4 1.78 + 0.88 E-03 12-27-76 262.08 6.84 + .8.53 E-04

--350-

VEPCo AIR PARTICULATE SAMPLES (picocuries per cubic meter)

FIRST QUARTER, 1976 COMPOSITES Bacon's Castle, Alliance Hog Island Reserve Colonial Parkway, Dow Surry Station Fort Eustis Volume 3555 Cu. M.. 9161 Cu. M.

Gamma Eeectrometry Be-7 3. 7 + L 8 E-02 3. 7 +.1.5 E-02 K-40 Less than 3.1 E-02 Less than 1. 2 E-02 Cr-51 Less than 2.5 E-02 Less than 9.7 E-03 Mn-Sli 2.3 + 1.6 E-03 Less than 6.2 E-04 Co-58 5.8 + 2.8 E-03 4.1 + 2.1 E-03 Co-60 3.0 + 1.9 E-03 1. 8 + 1. 5 E-03 Sb-125 Less than 9ol E-03 Less than 3.5 E-03 Cs-134 2.9 + 1.8 E-03 Less than 2.7 E-03 Cs-137 4.9 + 1.9 E-03 3.5+1.7E-03 Ce-144 Less than 3ol E-02 Less than 1. 2 E-02 Tl-208 Less than 1. 0 E-02 Less than 2.7 E-03 Pb-212 Less than 6.9 E-03 Less than 6.6 E-03 Pb-214 Less than 8.1 E-03 Less than 3.1 E-03 Bi-214 Less than 8.0 E-03 Less than 3..1 E-03 Ra-226 Less than 7.5 E-02 Less than 7.2 E-02

VEPCo AIR PARTICULATE SAMPLES (picocuries per cubic meter)

FIRST QUARTER, 1976 COMPOSITES Newport News Volume 1866 Cu. M.

Gamma S:eectrometry Be-7 Less than 1.1 E-01 K-40 Less than 5.9 E-02 Cr-51 3.3 + 3.2 E-02 Mn-54 Less than 3.0 E-03 Co-58 Less than 6.6 E-03 Co-60 Less than 4. 7 E-03 Sb-125 Less than 1. 7 E-02 Cs-134 Less than 1. 3 E-02 Cs-137 4.5 + 3.4 E-03 Ce-144 Less than 5.9 E-02 Tl-208 Less than 6.5 E-03 Pb-212 Less than 1. 6 E-02 Pb-214 Less than 1. 5 E-02 Bi-214 Less than 1. 5 E-02 Ra-226 Less than 1. 5 E-01

• . -352-

VEPCo AIR PARTICULATE SAMPLES (picocuries per cubic meter)

• SECOND QUARTER, 1976 COMPOSITES Hog Island Reserve Surry Station Bacon's Castle, Alliance Colonial Parkway, Dow, Fort Eustis Volume 3250 Cu. M. 8388 Cu. M.

Gamma Spectrometry Be-7 1. 2 + 0.2 E-01 5. 4 + 1. 6 E-02 K-40 2.5 + 2.3 E-02 1.6 + 1.4 E-02 Mn-54 Less than 3.3 E-03 Less than 1. 3 E-03 Co-58 2.3 + 0.4 E-02 2.6 + 1.4 E~03 Co-60 6.9 + 2.4 E-03 Less than 1. 7 E-03 Cs-137 5.8 + 2.2 E-03 Less than 1. 8 E-03 Pb-212 Less than 7.5 E-03 Less than 2.9 E-03 Bi-214 Less than 9.3 E-03 Less than 3.6 E-03 Pb-214 Less than 9.3 E-03 Less than 6.9 E-03 Ra-226 Less than 8.2 E-02 Less than 3.2 E-02

-.353-

VEPCo f.

AIR PARTICULATE SAMPLES (picocuries per cubic r.,ete:r)

SECOND QUARTER, 1976 COMPOSITES New2ort New~

Volume 1594 Cu. M.

Gamma Spectrometry Be-7 3.8 + 2.8 E-02 K-40 Less than 6.5 E-02 Mn-54 Less than 6. 7 E-03 Co-58 3.6 + 2.0 E-03 Co-60 Less than 4.8 E-03 Cs-137 Less than 4.2 E-03 Pb-212 Less than 1. 5 E-02 Bi-214 Less than 1. 9 E-02 Pb-214 Less than 1. 9 E-02

,T

\ Ra-226 Less than 1. 5 E-01

-354-

• • AH. 'i\RTI CULATE SAMPLES (picoc .*ies per cubic meter)

THIRD QUARTET.-'.. 1976 COMPOSITES Bacon's Castle, Alliance, Hog Island Reserve, Colonial Parkway, Dow, Surry Station Fort.Eustis Volume 4027.6 Cu. M. 10326.4 Cu. M.

Gannna Spectrometry Be-7 7.2 +.1.3 E-02 4.8 + 0.9 E-02 K-40 1. 2 + 1. 2 E-02 Less than 1. 2 E-02 Co-58 1. 8 + 1.1 E-03 2.1 + 0.7 E-03 Co-60 3. 2 +/- 1. 4 E-03 . 2.4 + 0.8 E-03 Nb-95 Less than 1. 8 E-03 Less than 1.1 E-03 Zr-95 Less than 2.2 E-03 8.0 + 6.7 E-04 Ru-103 Less than 1. 9 E-03 7.5 + _4.9 E-04

• I-131 Less than 2.0 E-03 Less than 7.8 E-04 Cs-137 5.5 +/- 1.4 E-03 2.1 + 0.7 E-03 Ce-141 Less than 3.6 E-03 Less than 1. 4 E-03 Tl-208 Less than 2.6 E-03 Less than 1. 0 E-03 Pb.:.212 Less than 4.1 E-03 Less than 3.5 E-03 Pb-214 Less than 5.1 E-03 Less than 2.0 E-03

.Ra-226 Less than 4.4 E-02 Less than 1. 7 E-02

• -355-

• AIR PARTICULATE SAMPLES (picocuries µ*er cubic meter)

THIRD QUARTER, 1976 COMPOSITES

• Newport News Volume 2056.2 Cu. M.

Gamma Spectrometry Be-7 4.9 + L 8 E-02 K-40 Less than 6.0 E-02 Co-58 Less than 5.3 E-03 Co-60 Less than 2.9 E-03 Nb-95 Less than 5.5 E-03 Zr-95 Less than 4.3E-03 Ru-103 Less than 3.7 E-03 I-131 Less than 3.9 E-03 Cs-137 3.2 + 1.8 E-03 Ce-141 Less than 7.0 E-03 Tl-208

• Less than 5.0 E-03 Pb-212 Less than 7.7 E-03 Pb-214 Less than 1. 0 E-02 Rct-226 Less than 8.4 E-02

-356-

• AlR PARTICULATE SAMPLES (picocuries per cubic meter)

FOURTH QUARTER, 1976 COMPOSITES Bacon's Castle, Alliance, Hog Island Reserve, Colonial Parkway, Dow, Surry Station Fort Eustis Volume 3018.24 9461.52 Gannna S:eectrometry Be-7 8.7 + 2.6 E-02 8.2+1.7E-02 K-40 Less than 4.1 E-02 Less than 1. 3 E-02 Co-5) 1. 9 +- 1.4 E-02 Less than 6.7 E-03 Co-58 3.0 + - Oo5 E-02 3.4 + 1.2 E-03 Co-60 1. 6 +- 0.4 E-02 4.1 + - 1.4 E-03 Nb-95 1. 7 +- 0.4 E-02 1. 7 -+ 0.2 E-02 Zr-95 1. 5 +- 0.4 E-02 l. l} + 0.2 E-02 Ru-103 1.1, +

- 0.3 E-02 1.0 + 0.2 E-02 Cs-134 3.4 + - 2.7 E-03 Less than 1. 3 E-03 Cs-137 1. 0 +-- 0.3 E-02 3. 3 + 1. 2 E-03 Ba-140 Less tb*m 1. 4 E-02 Less than 4.5 E-03 La-140 8.8 .+- 4.6 E-03 Less than 2.2 E-03 Ce-141 1. 9 +- 0.5 E-02 2.8 + 0.5 E-02 Ce-144 2.1 +- LS E-02 1. 8 + 1. 2 E-02 Tl-208 Les.> than 3.7 E-03 Less than 1. 2 E-03 Pb-212 Less than 8.4 E-03 Less than 5.6 E-03 Pb-214 Less than 1.1 E-02 Less than 3.4 E-03 Ra-226 Less than 8.6 E-02 Less than 6.4 E-02

-357-

• AIR PARTICULATE SAMPLES (picocuries per cubic meter)

FOURTH QUARTER, 1976 COMPOSITES Newport News volume 1774.08 Gamma Spectrometry Be.- 7 8. 5 + 3.8 E-02 K-40 Less than 7.0 E-02 Co-57 Less than 3.6 E-02 Co-58 Less than 9.6 E-03 co-60 Less than 1.1 E-02 Nl)-9 5 3.2 + Oo7 E-02 zr-95 3.1.+ 0.7 E-02 Ru-103 8.3 + 4o4 E-03 cs-134 Less than 6.9 E-03 Cs-137 308 + 2.9 E-03 Ba-140 Less than 2.4 E-02 La-= 140 Less than 1. 2 E-02 Ce-141 3.1 + 0.8 E-02 Ce-144 3.8 + 2.2 E-02

'1'1- 208 Less than 6.3 E-03 Pb-212 Less than L4 E-02 Pb-214 Less than 1. 8 E-02 Ra-226 Less than 3.4 E-01

-.lS8-

/

• VEPCo AMBIENT THERMOLUMINESCENT DOSIMETRY FIRST QUARTER, 1976 Date Annealed: 12-18-76 Date Returned: 4-8-76 Date Issued: 12-18-76 Date Read: 4-8-76 Net mrern 1st 2nd 3rd 4th 5th Average*+/- 2 Sigma mrem/wk Control 13 12 13 14 13 17.0 1. 8 1.1 Bacon's Castle 21 19 19

• 20 19 25.6. 2.3 1. 6 Surry Station 149 140 141

• 153 138 188.5 16.9 11. 7 Hog Island 23 22 26 20 21 24.3 5.0 1. 5 Reserve Alliance 18 18 19 19 21 24.8 2.3 1.6 Colonial Parkway 21 19 21 29 29 26.4 2.2 1. 6 Ft. Eustis Missing Newport News 29 25 27 25 26 34.5 4.3 2.1 Smithfield 27 30

• 30 26 28 36.8 4.7 2.3 Scotland Wharf Missing Jamestown Missing Lee Hall Missing Rt. 10 & 676 Missing Dow 24 24 23 23 25 31.1 2.2 1. 9

• Calibration Factor Applied

-359-

VEPCo AMBIE .ff THERMOLUMINESCENT DOSIMETRY SECOND QUARTER, 1976 Date Annealed: 3-29-76 Date Returned: 7-16-76 Date Issued: 3-29-76 Date Read:* 7-16-76

• Net *mrem 1st 2nd 3rd 4th 5th Averagec' + 2 Sigma mrem/wk Control 7 8 4 D D 6.1 3.9 0.4 Bacon's Castle 16 16 15 15 15 14.8 1. 0 0.9 Surry Station 122 124 128 129 126 121.0 5.5 7.7 Hog Island 22 17 D 18 14 17.0 6.3 1.1 Reserve Alliance 14 D 10 9 11 10.S 4.1 0."7 Colonial Parkway Missing Ft. Eustis 18 16 D 19 17 16.8 2.5 1.1 Newport News 21 21 D 19 19 19.2 2.2 1. 2 Smithfield 23 22 21 23 22 21. 3 1. 5 1.4 Scotland Wharf 17 D 17 17 17 16.3 0.0 1. 0 Jamestown Mis::;ing Lee Hall 18 21 22 19 20 19.2 2.9 1. 2 Rt. 10 & 676 12 13 14 12 12 13.1 1.9 0.8

. Dow 17 17 12 D 16 16.1 4.9 1. 0

• Calibration Factor Applied

• -360-

• • Date Annealed:

AMBIENT THERMOLUMINESCENT DOSIMETRY 7-8-76 THIRD QUARTER, 1976 Date Returned: 10-8-76 Date Issued: 7-8-76 Date Read: 10-8-76 Net mrem 1st 2nd 3rd 4th 5th Average*+/- 2 Sigma mrem/wk Control Missing Bacon's Castle 21 19 18 19 19 14.6 1. 6 1.1 Surry Station 109 75 87 90 92 69.7 18.7 5.3 Hog Island 26 23 23 29 23 18. 7 3.3 1. 4 Reserve Alliance 19 18 18 18 18 14.0 0.7 1.1 Colonial Parkway 19 20 21 19 21 15.4 1. 5 1. 2 Fort Eustis 2.4 19 25 25 23 17.8 3.7 1. 3 Newport News 23 23 22 24 23 17. 7 1.1 1. 3 Smithfield 26 22 25 25 24 19.9 2.4 1. 5 Scotland Wharf 20 19 20 21 21 16.5 1. 3 1. 2 Jamestown 21 21 20 17 19 16.0 2.7 1. 2 Lee Hall 24 23 23 26 24 19.6 L9 1. 5 Route 10 & 676 19 19 18 17 17 14.7 1. 6 1.1 i

Kingsmill 20 19 19 18 18 15.4 1. 3 1. 2 Budweiser 23

\

23 22 21 21 17.9 1. 6 1. 3 Dow 22 23 22 25 24 18.7 2.1 1.4

• *Ca lib.ration. Factor Applied

-361-

AMBIENT THERMOLUMINESCENT DOSIMETRY

• Date Annealed:

Date Issued:

FOURTH QUARTER, 1976 9-28-76 9-28-76 Net mrem Date Returned: 1-4-77 Date Read: 1-4-77 1st 2nd 3rd 4th 5th Average">\- +/-

2 Sigma mrem/wk Control 20 14 16 14 18 14.8 4. 7 1.1 1;c1con's Castle 13 18 D 15 15 13.8 3.7 0.9 Surry Station 87 101 91 97 82 83.1 13.8 6.0 Hog Island 18 17 19 Reserve 18 23 17o2 4.2 1. 2 Alliance 19 18 25 15 27 18.8 9.1 1. 3 Colonial Parkway 13 13 15 14 14 12.5 1.4 0.9 Fort Eustis 5 6 6 7 (Annealed 11-24-76) 8 6.2 2.2 1.1 NeFport News 18 18 16 18 17 15.8 1. 6 1.1 Smithfield 19 23 21 24 21 19.6 3.2 1.4 Scotland Wharf 15 15 16 16 14 13. 7 1.4 0.9 Jamestown 11 11 14 12 12 10.8 2.2 0.7 l,ee Hall 21 17 16 17 22 16.8 4~9 1. 2

~oute 10 & 676 13 10 14 15 12 11. 6 3.4 0.8

)ow 12 11 11 14 10 10.5 2.7 0.7

• :alibration Facotr AppJLied

-362-

VEPCo PRECIPITATION SAMPLES (nanocuries per square meter) .

• • Gross Beta FIRST QUARTER 1976 Newport News 6.0 + 1.2 E+OO

+/-

Surry Station

6. 0 .+ 1. 3 E+OO Tritium (En.) 4.7 1.3 E+Ol 3. 9 + 1. 4 E+Ol SECOND QUARTER 1976 Newport News Surry Station Gross Beta 3.4 + 1.6 E+OO 4.0 + 1.2 E+OO_

Tritium (En.) 1.5 + 0.3 E+02 1. 0 + 0 . 2 E+O 2

-363-

PRECIPITATION '.AMPLES

• (nanocuries per sq .are meter)

THIRD QUARTEF Surry Station 1

1976 Newport News Gross Beta 3.2 + 1.0 E+OO 1. 3 + 0. 7 E+OO Enr. Tritium 1.3 + 0.3 E+OZ 7.4 + 2.6 E+Ol FOURTH QUARTER, 1976 Surry Station Newport News Gross Beta 4.2 + 1.1 E+OO 2.5 + 0.9 E+OO

,Enr. Tritium 7.1 + 2.1 E+Ol 3. 4 + 1. 8 E+O 2

-364-

MIIK SANPLF.s (picocuries per liter)

Lee Hall Date Collected 1-15-76 Radiochemistry

. I-131 0.0 + 8.2 E-01 Sr-89 0.0 + 3.0 E+oO Sr-90 2.6 + 2.2 E+oO Ganma Spectrcxretty K-40 1.2 + 0.4 E-t03 Zr-95 1.7 + 1.3 E+ol Cs-137 Less than 1.8 E+ol Pb-214 Less than 9.2 E+ol Bi-214 Less than 6.8 E+ol Ra-226 Less than 9.4 E+o2 Note: Sample was received from U.S. Postal Service in damage condition. Sr-89,90 and Gamm Spectrometry aliquots were nonna.l; Iocline-131 aliquot was smaller than normal .

-365-

VEPCO MILK SAMPLES (picocuries per liter)

Colonial Pkwy. Dairy Date Collected 1-15-76 Radiochemistry I-131 0.0 +/- 6.2E-02 Calcium 0.8 g/1 Sr-89 0.0 +/- 4.6 E+OO Sr-90 7.1 +/- 3.4 E+OO Ganuna Spectrometry K-40 1.6 +/- 0.4 E+03 Zr-95 Less than 1.0 E+Ol Sb-125 Less than 7.6 E+Ol Cs-137 Less than 1. 8 E+Ol Bi-212 3.1 + l. E+02 Bi-214 Less than 6 .8 E+Ol Pb-214 Less than 9.2 E+Ol Ra-226 Less than 9.4 E+02

-366-

VEPCo ~

MILK S \MPLES

• Date Collected Radiochemistry (picocuries per liter)

Judkins Dairy 1-27-76 I-131 0.0 + 7.7 E-02 Calcium 1. 4 g/1 Sr-89 0.0 + 5.2 E+OO Sr-90 6.0 + 2.6 E+OO Gamma Spectrometry K-40 1. 3 + 0 . 4 E+O 3 Cs-137 Less than 1.5 E+Ol Bi-214 Less than 7.5 E+Ol Pb-214 Less than 8.9 E+Ol

-367-

VEPGo MILK SAMPLES (picocuries p~r liter)

Gwaltney Dairy Date Collected 1-28-76 Radiochemistry I-131 0.0 + 7.6 E-02 Calcium 0.9 g/1 Sr-89 0.0 + 2.6 E+OO Sr-90 4. 6 + 1. 6 E+OO Gamma Spectrometry K-40 L 2 + 0. 4 E+03 Cs-137 Less than 2.1 E+Ol Pb-212 *Less than 8.0 E+Ol Pb-214 Less than 7.9 E+Ol

-368-

MILK SAMPLES (picocuries per liter)

• Date Collected Radiochemistr:i Lee Hall Dairy 2-10-76 Colonial.

2-10-76 Pkwy D; i::!Y I-131 0.0 + 1.2 E-01 Calcium 1.1 g/1 o.o + 8.1 E-02 Sr-89 0.0 + 2. 7 E+OO 1. 4 g/1 0.0 + 3.9 E+OO Sr-90 2.5 + 1.6 E+OO 1.1 + 0.2 E+Ol Gamma Spectrometry K-40 1.5 + 0.4 E+03 1.4 + 0.4 E-1-03 Sb-125 Less than 7.8 E+Ol Less thnn 7.8 E+Ol Cs-137 Less than 1. 8 E+Ol Less than 1. 8 E+Ol Pb-212 Less than 7.9 E+Ol Less than 8.5 E+Ol Bi-214 Less than 1. 8 E+02 Less than 7.0 E+Ol Pb-214 Less* than 9.0 E+Ol 8.7 + 6.0 E+Ol

• -369-

VEPCo

• D:. te Cc,llected MILK SAMPLES (picocuries -~er liter)

A. Gwaltney Dairy Floyd B. Scott Dairy 2-25-76 2-25-76 R,diochemistry I-131 0.0 + 9.9 E-02 C;tlcium 0.0 + 9.3 E-02

1. 6 g/1 1. 6 g/1 S::~-89 0.0 + 3.1 E+OO 0.0 + 4.0 E+OO s*,*-9o 4. 4 + 1. 9 E+OO 7.6 + 2.4 E+OO G. rnma Spectrometry K 40 1. 2 + 0, 4 E+O 3 1. 5 + 0. 4 E+03

c. -13 7 Less than 1.9 E+Ol Less than 2.0 E+Ol T * - 208 Less than 2.6 E+Ol Less than 2.6 E+Ol I'i -212 Less than 7.9 E+Ol Less than 8.0 E+Ol Bi-214 Less than 6.5 E+Ol Less than 6.5 E+Ol Pb-214 Less* than 8.7 E+Ol Less than 9.0 E+Ol

• -370-

• vEPCo

.(. MILK SAMPLES (picocuries per liter)

Colonial Dairy Date Collected 3-10-76 Radiochemistry Sr-89 0.0 + 3.4 E+OO Sr-90 1. 4 + 0. 2 E+Ol I-131 0. 0 + 1. 5 E- 0 i Cal. (g/1) 1. 5 Gamma S:eectrometry K-40 1.4 + 0.4 E+03 Cs-137 1.1 + 1.1 E+Ol Pb-212 Less than 8.3 E+Ol Ra-226 Less than 9.0 E+02 Ac-228 Less than 1.9 E+02 I

\

-371-

VEPCo MILK SAMPLES (picocuries per liter)

Gwaltney Dairy Judkins Dairy Date Collected 3-24-76 3-24-76 Radiochemistry I-131 0.0 + 1.4 E-01 0.0 + 1.5 E-01 Calcium 1. 5 g/1 1. 6 g/1 Sr-89 0.0 + 3.0 E+OO 0.0 + 2.8 E+OO Sr-90 4.9 + 1.6 E+OO L 1 + 0. 2 E+Ol Gamma Spectrometry K-40 1.2 + 0.4 E+03 1. 4 + 0. 4 E+03 Co-60 Less than 1.6 E+Ol 1. 8 + 1. 1 E+Ol Cs-137 1. 3 + 1. 1 E+Ol Less than 2.1 E+Ol Pb-212 Less than 8.2 E+Ol Less than 8.2 E+Ol Pb-214 Less than 8.6 E+Ol Less than 8.6 E+Ol

-'17?-

VEPCo

• Date MILK SAMPLES (picocuries per liter)

Lee Hall Collected 3-25-76 Radiochemistry Sr-89 0.0 + 2.1 E+OO Sr-90 3 . 7 + 1. 4 E+OO Calcium 1. 6 g/1 I-131 0.0 + 2.7 E-01 Gamma Spectrometry K-40. 1.1 + 0.4 E+03 Cs-137 Less than 2.1 E+Ol Pb-212 Less than 8.5 E+Ol Bi-214 Less than 8.1 ~+01 Pb-214 7.5 + 6.3 E+Ol

-373-

VEPCo MILK SAMPLES (picocuries per liter)

Lee Hall Dairy Colonial Pkwy Dairy Date Collected 4-6-76 4-6-76 Radiochemistry I-131 0. 0 + 1. 3 E-01 0.0 + 1.4 E-01 Calcium Sr-89 0.0 + 2.5 E+OO 0.0 + 2.6 E+OO Sr-90 4. 2 + 1. 7 E+OO 3.4 + 1.7 E+OO Gamma SEectrometry K-40 1. 0 + 0. 4 E+03 1. 6 + 0. 4 E+03 Cr-51 Less than 2ol E+02 1.4 + 1.4 E+02 Cs-137 Less than 1. 8 E+Ol Less than 2.3 E+Ol Tl-208 Less than 2.4 E+Ol Less than 2.4 E+Ol Pb-212 Less than 8.3 E+Ol Less than 8.3 E+Ol Bi-214 4.5 + 4.2 E+Ol Less than 6.8 E+Ol Ra*-226 Less than 9.1 E+02 Less than 9.1 E+02

• * -374-

VEPCo MILK SAMPLES (picocuries per liter)

• Date Collected Radiochemistry Gwaltney Dairy 4-21-76 Judkins Dairy

. 4-21-76 I-131 O.*O + 6. 6 E-02 0.0 + 1.2 E-01 Calcium 1. 6 g/1 1. 7 g/1 Sr-89 0.0 + 3.8 E+OO 0.0 + 4.2 E+OO Sr-90 5.3 + 2.0 E+OO 5.2 + 2.2 E+OO Gamma Spectrometry K-40 1.2 + 0.3 E+03 .1.5 + 0.4 E+03 Co-57 2.0 + 1.8 E+Ol Less thari 2.7 E+Ol Co-60 1. 7 + 1. 1 E+Ol Less than 1.6 E+Ol Sb-125 . Less than 8.2 E+Ol Less than 8.2 E+Ol Cs-137 1. 6 + 1. 3 E+O 1 Less than 2.4 E+Ol Tl-208 Less than 2.4 E+Ol Less than 2.4 E+Ol Bi-212 Less than 2.4 E+02 1. 8 + 1. 6 E+02 Pb-212 Less than 8.1 E+Ol Less than 8.1 E+Ol Bi-214 Less than 6.5 E+Ol Less than 6.5 E+Ol Pb-214 Less than 8.9 E+Ol Less than 8. 5 E+Ol

• Ra-226 Less than 9.1 E+02 Less .than 9.1 E+02

• -375-

VEPCo MILK SAMPLES (picocuries per liter)

Lee Hall Dairy Colonial Pkwy. Dairy Date Collected 5-4-76 5-4-76 Radiochemistry I-131 0.0 + 1.0 E-01 0.0+ 2.0 E-01 Calcium 1. 5 g/1 1. 5 g/1 Sr-89 0.0 + 2.6 E+OO 0.0 + 5.0 E+OO Sr*-90 4~1 + 2.6 E+OO 5.5 + 3.3 E+OO*

Ga11ma Spectrometry K-lrO 1. 5 + 0. 4 E+03 2.2 + 0.5 E+03 Cr-51 Less than 3.1 E+02 Less than 3.1 E+02 Co- 58' Less than 2.7 E+Ol Less than 2.7 E+Ol Cs-137 Less than 2.8 E+Ol Less than 2.8 E+Ol Tl-208 3.2 + 2.4 E+Ol Less than 3.6E+Ol Bi-212 Less than 4.7 E+02 Less than 4.7_E+02 Pb-212 Less than 1.0 E+02 Less *than 1.0 E+02 Pb-214 Less than 9.5 E+Ol Less than 9.8 E+Ol Ra-226 Less than 1.0 E+03

• Less than 1.0 E+03

• -376-

VEPCo fILK SAMPLES (pico ::uries per liter)

Ep1 's D. &

Lee Hall )airy Ba* on's Castle Dairy Date Collected 5-20-76 s-* o-76 Radiochemistry I-131 0.0 + 3.2 E-01 0. ( + 1. 9 E-01 Calcium 2.1 g/1 1. I. g/1 Sr-89 0.0 + 1.3 E+Ol 0.0 + 1.0 E+Ol Sr-90 0.0 + 1.3 E+Ol 0.0 + 9.6 E+OO

. ~.* '

Gamma SEectrometry K-40 1.6 + 0.4 E+03 1.7+0.4 E+03 Sb-125 Less than 8.6 E+Ol Less than 8.6 E+Ol l-131 Less than 3.1 E+Ol Less than 3.1 E+Ol Cs-134 Less than 1. 6 E+Ol Less than 1. 6 E+Ol Cs-137 Less than 1. 7 E+Ol 1.9 + 1.1 E+Ol Hg-203 Less -than 2.8 E+Ol Less than 2.8 E+Ol Pb-212 Less than 7.7 E+Ol Less than 8.0 E+Ol Ra-226 Less than 9.0 E+02 *Less than 9.0 E+02 Ac-228 Less than 1. 9 E+02 Less than 1. 9 E+02 NOTE: Both samples received in poor condition - almost solid.

Poor Radiochemical Recoveries

• -378-

VEPCo MILK SAMPLES (picocuries per liter)

• Date Collected Radiochernis tr:..Y Judkins Dairy

.5-19-76 Gwaltney Dairy 5 76 I-131 0. 0 + 1. 8 E-01 0. 0 + 8. 9 E~ 02 .

Calcium 1. 5 g/1 1. 4 g/1 Sr-89 0.0 + 9.3 E+OO 0.0 + 7.3 E+OO Sr-90 0.0 + 8.9 E+OO 0.0 + 7~7 E+OO Gamma Spectrometry K-40 1. 9 + 0. 5 E+03 2.2 + 0.6 E+03 Mn-54 Less than 3.2 E+Ol Less than 3.2 E+Ol Cs-137 3 . 1 + 1. 6 E+O 1 2.2 + 2.0 E+Ol Hg-203 Less than 4.0 E+Ol Less than 4.0 E+Ol Tl-208 Less than 3.2 E+Ol Less than 3.6 E+Ol Pb-212 Less .than 1. 0 E+02 Less than 1. 0 E+02 Pb-214 Less than 9.7 E+Ol Less than 9. 7 E+o*1 Ra-226 Less than 1. 0 E+OJ Less than 1.0 E+03

-377-

VEPCo MILK SAMPLES (picocuries per liter)

Lee Hall Dairy Date Collected 6-3-76 Radiochemistry I-131 0.0 + 8.6 E-02 Calcium 1. 5 g/1 Sr-89 0.0 + 4.2 E+OO Sr-90 0.0 + 4.6 E+oO Gannna Spectrometry K-40 1. 7 + 0.4 E+03 Co-57 1. 8 + 1. 8 E+O 1 Cs-137 1. 3 + 1. 2 E+O 1 Pb-214 Less than 8.7 E+Ol

• -379-

VEPCo r *:1K SAMPLES (pico 1ries per liter)

• Date Collected Radiochemistry Colonial 6-7-76 tvy. Dairy I-131 OoO + 6.2 ,~-01 Calcium 1. 5 g/1 Sr-89 0.0 + 3.4 E+OO Sr-90 2. 4 + 1. 8 E+OO Gamma Spectrometry K-40 1. 3 + 0. 4 E+03 Tl-208 Less than 2.8 E+Ol Pb-212 Less than 803 E+Ol Pb-214 Less than 7.7 E+Ol

-380-

VEPCo

• • Date MILK SAMPLES (picocuries per liter)

Judkins Dairy Collected 6 76 Radiochemistry I-131 0.0 + 9.6 E-02 Calcium 1.4 g/1 Sr-89 0.0 + 2.0 E+OO Sr~90 2. 4 + 1. 5 E+OO Ganuna Spectrometry K-40 1. 2 + 0. 4 E+OJ Sb'.'"125 Less than 8.0 E+Ol Cs-137 Less than 2.1 E+Ol

-381-

VEPCo MILK SAMPLES (picocuries per liter)

• Date Collected Radiochemistrx Epp's Dairy 6-24-76 I-131 OoO + Ll E-01 Calcium 1. 5 g/1 Sr-89 0.0 + 5.6 E+OO Sr-90 8.6 + 3.5 E+OO Gannna SEectrometrx K-40 1.6 + 0.4 E+OJ Cs-137 Less than 2.1 E+Ol Pb-212 Less than 8.3 E+Ol Bi~214 Less than 6.5 E+Ol Ra-226 Less than 9.1 E+02

-382-

VEPCo MILK SAMPLES (picocuries per liter)

Colonial Pkwy. Dairy

.

• Date Collected 6-29-76 Radiochemistry I-131 a.a+ 9.7 E-a2 Calcium 1. 4 g/1 Sr-89 *a. a + 1. 3 E+a 1 Sr-9a a . a + 1. 3 E+O 1 Gamma Spectrometry K-40 1.5 + 0.4 E+03 Cs-137 Less than 1. 9 E+Ol Tl-208 Less than 3.1 E+Ol Pb-212 Less tha:n 8.0 E+Ol Bi-214 Less than 7.3 E+Ol Pb-214 6.0 +. 6.0 E+Ol Ra-226 Less than 9.4 E+02

• Low chemical recovery

-383-

• Date Collected MILK SAMPLES (picocuries per liter)

Lee Hall Dairy 7-2-76 Radiochemistry I-131 0.0 + LS E-01 Calcium 1.4 g/1 Sr-89 ~"l. 5 + 1. 0 E+Ol Sr-90 0.0 + 1.2 E+Ol Gamma Spectrometry K-40 1. 4 + 0 . 4 E+O 3 Cs-137 Less than 2.2 E+Ol Pb-212 Less than 8.4 E+Ol Bi-214 7.8 + 5.9 E+Ol Pb-214 Less than 9.6 E+Ol

-384-

• Date Collected MILK SAMPLES (picocuries per liter)

Judkins Dairy 7 76 Radiochemistry 1-131 0.0 + 1.3 E-01 Calcium 1. 4 g/1 Sr-89 0.0 + 4.1 E+OO Sr-90 5.0 + 3.0 E+OO Gamma Spectrometry K-40 1.2 + 0.3 E+03 Cs-137 Less than 2.6 E+Ol Pb-212 Less than 8 .. 6 E+Ol Bi-214 7.2 + 5.7 E+Ol Pb-2.14 1. 2 + 0 . 7 E+O 2 Ra-226 Less than 9.1 E+02

-385-

• Date Collected Epp's.Dairy 7-16-76 MILK SAMPLES (picocuries per liter)

Radiochemistry:

I-131 0.0 + 2.1 E-01 Calcium 1. 3 g/1 Sr-89 0.0 + 3.0 E+OO Sr-90 2.9 + 2.3 E+OO Gannna Spectrometry K-40 1. 6 + 0. 4 E+03 Co-57 Less than 2.8 E+Ol Cs-137 Less than 2.0 E+Ol Ce-141 Less than 7.8 E+Ol Pb-212 Les*s than 8.0 E+Ol Bi-214 Less than 7ol E+Ol Pb-214 Less than 9.0 E+Ol Ac-228 -Less than 1. 9 E+02

-386-

• Date

_ Collected 7-30-76 MILK SAMPLES (picocuries per liter)

Lee Hall.Dairy Colonial Pkwy. Dairy 7-30-76 Radiochemistry f-131 0. 0 + 1. 1 E-01 0.0 + 7.3 E-02 Calcium 1. 4 g/1 1. 4 g/1 Sr-89 0.0 + 5.2 E+OO 5.6 + 2.6 E+OO Sr-90 0.0 + 4.4 E+OO 0.0 + 3.6 E+OO Gamma Spectrometry K-40 1. 2 + 0. 4 E+03 1. 6 + 0 *. 4 E+O 3 Co-60 Less than 2.0 E+Ol 1. 3 + 1. 3 E+Ol Cs-137 Less than 2.3 E+Ol Less than 1. 8 E+Ol Pb-212 Less than 8.3 E+Ol Less than 8.3 E+Ol Bi-214 1.3. + 0.6 E+02 Less than 7.1 E+Ol Pb-214 2.2 + 0.7 E+02 7.6 + 5.8 E+Ol Ra-226 Less than**9.4 E+02 Less than 9.3 E+02

• -387-

• Date Collected 8-10-76 MILK SAMPLES (picocuries per liter)

Epp's Dairy Judkins Dairy 8-10-76 Radiochemistry I-131 0.0 + 9.4 E-02 0.0 +.1.1 E-01 Calcium 1. 5 g/1 1. 5 g/1 .

Sr-89 0.0 + 2.1 E+OO 0.0 + 3.0 E+OO Sr-90 4. 0 + 1. 6 E+OO 7.1 + 2.2 E+OO Gamma Spectrometry Be-7 Less than 1. 6 E+02 1.1 + 1.1 E+02 K-40 1. 5 + 0. 4 E+03 1. 6 + 0 . 4 E+O 3 Cs-137 *Less than 2.1 E+Ol Less than 2.2 E+Ol Ce-141 Less than 7.7 E+Ol Less than 7.7 E+Ol Bi-214 Less than 6.5 E+Ol Less than 6.5 E+Ol Pb-214 Less than 9.0 E+Ol Less than 9.0 E+Ol

-188-

• Date Collected 8-12-76 MILK SAMPLES (picocuries per liter)

Lee Hall Dairy E22's Dairy 8-12-76 Radiochemistry I-131 0.0 + 1.8 E-01 0.0 + 1.1 E-01 Calcium 1. 5 g/1 1. 3 g/1 Sr-89 0.0 + 4.7 E+OO 0.0 + 3.2 E+OO Sr-90 3.5 + 3.0 E+OO 3.2+1.7 E+OO Gannna S:eectrometry .

K-40 L 6 +/- 0. 4 E+03 1.5 + 0.4 E+03 Sb-125 Less than 8.5 E+Ol Less than 8.5 E+Ol Cs-137 Less than 2.2 E+Ol Less than 1. 9 E+Ol Tl-208 Less than 3.2 E+Ol Less than 3.2 E+Ol Bi-214 a.a*+/- 5.a E+o1 Less than 8.7 E+Ol Pb-214 Less than 9.5 E+Ol Less than 9.5 E+Ol

• -389-

• Date MILK SAMPLES (picocuries per liter)

(split sample)

Lee Hall Dairy Collected 8-12-76 Radiochemistry I-131 0.0 + 1.5 E-01 Calcium 1. 5 g/1 Sr-89 0.0 + 5.2 E+OO Sr-90 0.0 + 4. 7 E+OO Gamma Spectrometry K-40 8.2 + 3. 7 E+02 Cs-137 Less ,than 2.6 E+Ol Bi-214 Less than 6.9 E+Ol Pb-214 1.2+ 0.8 E+02

• -390-

• Date Collected MILK SAMPLES (picocuries per liter)

Colonial Pkwy. Dairy 8-24-76 Lee Hall Dairy 8-24-76 Radiochenistry I-131 0. 0 + LO E-01 0.0 + 8.8 E-02 Calcium 1. 3 g/1 1. 4 g/1 Sr-89 0.0 + 3.8 E+OO 0.0 + 2.4 E+OO Sr-90 4.0 + 2.1 E+OO 1. 4 + 1. 3 E+OO Garrma Spectrometry K-L,O 1. 2 + 0 4 E+03 o 1. 0 + 0. 4 E+03 Cs-137 1. 1 + 1. 0 E+O 1 . Less than 1. 6 E+Ol Pb-21? 4.0 + 0.5 E+02 Less than 8.0 E+Ol Bi:...211 Less than 6.7 E+Ol Less than 6.7 E+Ol Pb-211, Less than 8.8 E+Ol Less than 8.8 E+Ol Ra-22f, Less . than 8.8 E+02 Less than 8.8 E+02

• -391-

• Date Collected 9-7-76 MILK SAMPLES (picocuries per liter) 92Q' s Dairy Judkins Dairy 9-7-76 Radiochemistry I-131 0.0 + 6.3 E-02 Calcium 0.0 + 1.2 E-01 l.lg/1: 1. 0 g/1 Sr-89 0

• 0 + 6 o..4 E+OO 0. 0 + 5 . 1 E+OO Sr-90 0.0 + 5.0 E+OO 0.0 + 6.4 E+OO Gamma Spectrometry K-40 1. 4 + 0 4 E+O 3 o

1. 3 + 0 . 4 E+O 3 Cr-51 Less than 2.2 E+02 Less than 2.2 E+02 Cs-137 Less than 2.2 E+Ol Less than 1.7 E+Ol Tl-208 Less than 3.0 E+Ol Less than 3.0 E+Ol Pb-212 Less than 7.8 E+Ol Less than 7.5 E+Ol Bi-214 4.2 + 4.2 E+Ol Less than 6.3 E+Ol Pb-214 Less than 1.6 E+02 Less than 1.6 E+02 Ra-226 Less than 8.4 E+02 Less than 8.4 E+02

-392-

• Date Co lle.cted MILK SAMPLES (picocuries per liter)

Lee Hall Dairy 9-22-76 Colonial Pkwy. Dairy 9-22-76 Radiochemistry I-131 0.0 + 8.2 E-02 0.0 + 1.2 E-01 Calcium 1. 5 g/1 1. 4 g/1 Sr-89 0.0 + 3.5 E+OO 0.0 + 3.7 E+OO Sr-90 6 . 1 + 1. 9 E+OO 0.0 + 3.0 E+OO Gamma Spectrometry K-40 1.5 + 0.4 E+03 1. 7 + 0 . 5 E+O 3 Gs-137 Less than 2.3 E+Ol Less than 2.0 E+Ol Pb-212 Less than 7.9 E+Ol Less than 7.9 E+Ol Bi-214 *. Less than 6.9 E+Ol Less than 4.6 E+Ol Pb"."214 Less than 9.1 E+Ol Less than 9.1 E+Ol Ita-226 Less than 9.2 E+02 Less than 9.2 E+02

• -393-

• Date Epp Is MILK SAMPLES (picocuries per liter)

Dairy Judkins Dairy Collected 10-5-* 76 10-5-76 Radiochemistry I-131 2.0 + 0.1 E+OO 2. 6 + 0. 2 E+OO Calcium 1. 5 g/ 1 1. 5 g/1 Sr-89 . 0 . 0 + 6. 4 E+OO 0. 0 + 2 . 9 E+OO Sr-90 0.0 + 1.2 E+Ol 1. 4 + 0 . 6 E+O 1 Gamma Spectrometry K-40 1. 5 + 0. 4 E+03 1. 7 + 0. 4 E+O 3 Co-60 Less than 1.1 E+Ol Less than 1.1 E+Ol I-131 2.2 + 2.2 E+Ol 2.9 + 2.1 E+Ol Cs-137 Less than 2.2 E+Ol Less than 1. 8 E+Ol Ba-140 Less than 6.5 E+Ol Less than 6.5 E+Ol La- llfO 2.6 + 2.4 E+Ol Less than 3.6 E+Ol Ce-141 Less than 7.6 E+Ol Less than 7.5 E+Ol Ce-144 2.0 + L4 E+02 Less than 2.1 E+02 Pb-212 Less than 8.2 E+Ol Less than 8.2 E+Ol Pb-214 Less than 8.0 E+Ol Less than 8.0 E+Ol Ra-226 Less than 9.1 E+02 Less than 9.1 E+02

• -394-

• Date Collected 10-21-76 MILK SAMPLES (picocuries per liter)

Lee Hall Dairx . Epp Is Dairx 10-19-76 Radiochemistrx I-131 5.7 + 0.2 E-01 Calcium 1. 4 g/1 3.8 + 2.3 E-01 Sr-89 1. 4 g/1

'"3. 5 + 2. 2 E+OO 0.0 + 3.3 E+OO Sr-90 3. 9 +/- 1. 7 E+OO 4. 0 + 1. 9 E+OO Gamma Spectrometry K-40 1.6 + 0.4 E+03 1. 4 + 0 . 4 E+O 3 Cs-137 Less than 1.6 E+Ol . Less than 1. 2 E+Ol

• Pb-212 Less than 8.2 E+Ol Less than 8.1 E+Ol Pb...:214 Less than 8.9.E+Ol Less than 8.9 E+Ol Ra-226 Less than 9.4 E+02 Less than 9.4 E+02

,'rAt time of collection *

. (

-395-

• Date MILK SAMPLES (picoc_uries per liter)

Colonial Pkwy. Dairy Lee Hall Dairy Collected 10-21-76 10-19-76 Radiochemistry I-131 6.0 + 1.6 E-01 0.0 + 2.0 E-01 Calcium 1. 4 g/1 1. 5 g/1 Sr-89 0.0 + 2o2 E+OO *9.1 + 2.4 E+OO Sr-90 3 . 5 -+ 1. 4 E+OO 0.0 + 2.3 E+OO Gamin.a Spectrometry K-40 9.5 + 4o0 E+02 1. 4 + 0. 4 E+03 Cs-137 Less than 1. 9 E+Ol 1. 9 + 1. 1 E+Ol Pb-212 Less* than 8.1 E+Ol Less than 8.3 E+Ol Pb-214 Less *1:han 8.9 E+Ol Less than 8.9 E+Ol Ra-226 Less than 9.4 E+02 Less than 9.4 E+02

• At time of collection .

-396-.

• Date Collected*

MILK SAMPLI: S (picocuries per liter)

Judkins Dairy 11-2-76 Radiochemistry I-131 3.4 + 0.9 E+OO Calcium 1. 5 g/1 Sr-89 *1.2 + 0.3 E+Ol Sr-90 4. 3 + 1. 8 E+O 0 Extra Sample Collected for Gamma Spectrometry Date Collected 11-30-76 Gamma Spectrometry K-40 1. 6 + 0. 4 E+O 3 Cs-137 1. 2 + 0. 9 E+O 1 Bi-212 2*2 + 1. 6 E+O 2 Pb-212

• Less than 8.0 E+Ol

• At Time of Collection

-397-

• Date Collected 11-iB-76 MILK SAMPLES (picocuries per liter)

Lee Hall Dairy

• Colonial Pkwy. Dairy 11-18-76 Radiochemistry I-131 0. 0 + 1.1 E-01 0.0 + 8.7 E-02 Calcium 1. 5 g/1 1. 3 g/1 Sr-89 0. 0 + 1. 7 E+OO 3. 6 + 1. 8 E+OO Sr-90 3. 4 + 1. 6 E+OO 3. 0 + 1. 8 E+OO Gamma Spectrometry K-40 1.5 + 0.4 E+03 1. 7 + 0. 4 E+03 Sb-125 Less than 8.2 E+Ol Less than 8.2 E+Ol Cs-137 Less than 2.0 E+Ol Less than 1.7 E+Ol

. Pb-212 Less than 8.2 E+Ol Less than 7.9 E+Ol

-398-

• Date MILK SAMPLES (picocuries per liter)

Epp' s Dairy Collected 11-30-76 Radiochemistry I-131 4. 2 + 1.4 E-01 Calcium 1. 5 g/1 Sr-89 0 . 0 + 1. 8 E+OO Sr-90 2 . 5 + 1. 4 E+O.O Gamma Spectrometry K-40 1.4 + Oo4 E+03 Cs-137 Less than 2ol E+Ol Pb-212 Less than 7.9 E+Oi Ra-226 Less than 9.1 E+02

-399-

• Date Collected MILK SAMPLES (picocuries per liter)

Lee Hall Dairy Smith Brothers Dairy 12-14-76 12-14-76 Radiochemis I IT I-131 0.0 + 7.8 E-02 0.0 + 9.0 E-02 Calcium 1. 4 g/1 1. 4 g/1 Sr-89 0.0 + 2.2 E+OO 0.0 + 2.3 E+OO Sr-90 0.0 + 2.1 E+OO 3. 0 + 1. 4 E+OO Gamma SpectrJmetry K-40 1. 0 + 0. 3 E+03 1. 5 + 0 . 4 E+O 3 Ru-106 Less than 1.6 E+02 Less than 1.6 E+02 Sb-125 Less than 7.9 E+Ol Less than 7.9 E+Ol I-131 Less than 3.2 E+Ol Less than 3.2 E+Ol Cs-137 Less than 1.9 E+Ol Less than 2.1 E+Ol Pb-212 Less than 8.0 E+Ol Less than 8.0 E+Ol Ra-226 Less than 9.1 E+02 Less than 9.1 E+02

• -400-

• • MILK SAMPLES (picocuries per liter)

Lee Hall Dairy Colonial Pkwy. Dairy Date Collected 12-27-76 12-27-76 Radiochemistry I-131 0.0 + 1.2 E-01 0.0 + 7.4 E-02 Calcium 1. 4 g/1 1. 4 g/1 Sr-89 0.0 + 2.0 E+OO 0. 0 + 2 . 6 E+OO Sr-90 2.2 + 1. 2 E+OO 0.0 + 2.6 E+OO Gamma Spectrometry K-40 1. 4 + 0. 4 E+03 1. 7 + 0. 4 E+03 Cs-137 Less than 1.8 E+Ol 1. 2 + 1. 2 E+O 1 Pb-212 Less than 8.4 E+Ol Less than 8.0 E+Ol Pb-214 Less than 7.6 E+Ol Less than 7.6 E+Ol

-401-

VEPCo WELL WATER SAMPLES (picocuries per liter)

Surry Station Jamestown Date Collected 4-21-76 4-21-76 Radiochemistry Gross Alpha 0.0 + 2.4 E+OO o.o+ 2.8 E+OO Gross Beta 0.0 + 4.8 E+OO 7.8 + 5.3 E+OO Tritium (En.) 2.7 +/- 1.2 E+02 Less-than 1.2 E+02 Bacon's Castle Hog Island Reserve Date Collected 4-21-76 4-21-76 Radiochemsitry Gross Alpha 0.0 + 2.0 E+OO 0.0 + 2.3 E+OO Gross Beta 1 .. 2 + 0.5 E+Ol 0.0 + 4.8 E+OO Tritium (En.) 3. 5 + 1.1 E+02 Less-than 1.1 E+02 C

-402-

• Date Collected 11-2-76 WELL WATER SAMPLES (picocuries per liter)

Hog Island Surry Station 11-2-76 Radiochemistry Gross Alpha 0 . 0 + 1. 2 E+OO 0. 0 + 1. 2 E+OO Gross Beta 0 . 0 + 1. 5 E+OO 0. 0 + 1. 5 E+OO Enr. Tritium Less-than 1.5 E+02 Less-than 1.5 E+02 Jamestown Bacon's Castle Date Collected 11-2-76 11-2-76 Radiochemistry Gross Alpha 0. 0 + 1. 2 E+OO 0.0 + 7.4 E-01 Gross Beta 2 . 7. + 1. 6 E+OO 2. 4 + 1. 4 E+OO Enr. Tritium Less-than 1.5 E+02 1. 5 + 1. 0 E+02

-403-

VEPCo SURFACE WATER SAMPLES (picocuries per liter) 4-21-76 Gross Alpha Gross Beta Tritium (En.)

Chippokes Creek 0.0 + 2.0 E+OO 0.0 + 4.7 E+OO 4.5 + 0.9 E+02.

Newport News Reservoir 0. 0 + L 7 E+OO 7.0 + 5.0 E+OO 9.6 + 1. 0 E+02 Smithfield Reservoir 0.0 + 5.3 E+OO 0.0 + 9.2 E+OO 3.7 + 1. 0 E+02 Williamsburg Reservoir o.o + 1. 9 E+OO 0.0 + 4.7 E+OO 2.9 + 0.8 E+02

-401+-

• Date Collected 11-2-76 SURFACE WATER SAMPLES (picocuries per liter)

Chipokes Creek Newport News 11-2-76 Radiochemistry Gross Alpha 0.0 + 9.3 E-01 Gross Beta 0.0 + 7.0 E-01 2 . 2 + 1. 5 E+OO 3 . 2 + 1. 5 E+OO L.S. Tritium 3.1 + 2.6 E+02 Less-than 3.0 E+02 Smithfield Williamsburg Date Collected 11-2.-76 11-2-76 Radiochemistry Gross Alpha 0.0 + 7.9 E-01 Gross Beta 0.0 + 8.8 E-01 6

• i + 1. 8 E+OO 2. 5 + 1. 5 E+OO L.S. Tritium Less-than 3.0 E+02 Less-than 3.0 E+02

-405-

VEPCo JAMES RIVER WATER SAMPLES

• Date Collected Gamma Spectrometry Hog Island Point 1-13-76 (picocuries per liter)

Newport 1-26-76 News K-40 Less than 1. 3 E+02* 1.8 + 0.9 E+02 Nb~95 Less than 8.5 E+OO Less than 8.5 E+OO Sb-125 Less than 2.7 E+Ol Less than 2.7 E+Ol Cs-137 Less than 9.9 E+OO Less than 7.9 E+OO Tl-208 Less than 8.3 E+OO Less than 8.3 E+OO Pb-212 Less than 2.4 E+Ol Less than 2.3 E+Ol Bi-214 Less than 2.1 E+Ol Less than 2.8 E+Ol Pb-214 Less than 2.7 E+Ol Less than 2.7 E+Ol Ra-226 Less. than 2. I+ E+02 Less than 2.5 E+02 Ac-228 Less than 5.9 E+Ol Less than 5.9 E+Ol

-406-

VEPCo JAMES RIVER WATER SAMPLES

• Date Collected 1 76 Gannna Spectrometry (picocuries per liter)

Chickahominey Station Discharge 1-13-76 K-40 Less than 8. 8 E+Ol* Less .than 8.8 E+Ol Nb-95 Less than 8.5 E+OO Less than 8.5 E+OO Sb-125 Less than 2.8 E+Ol Less than 2.7 E+Ol Cs-137 Less than 7.0 E+OO Less than 6.1 E+OO Tl-208 Less than 9.8 E+OO Less than 8.3 E+OO Pb-212 Less than 2.3 E+Ol Less than 2.3 E+Ol Bi-214 Less *than 2.1 I. E+Ol Less than 2.5 E+Ol Pb-214 Less than 211 E+Ol Less than 2.8 E+Ol Ra-226 Less. than 2.4 E+02 Less than 2.4 E+02 Ac-228 Less than 5.9 E+Ol Less than 5.9 E+Ol

-*-~- -------

-W7-

- - ~

. i VEPCo '/

JAMES RIVER: WATER SAMPLES

• Date Collected 1-30-76 Gamm.a Sp-ectrometry (picocuries per liter) -

Station Intake K-40 8.3 + 7.4 E+Ol Nb-95 Less than 8.5 E+OO Sb-125 Less than 2.7 E+Ol Cs-137 4.6 + 4.1 E+OO

\

Tl-208 Less than 8.9 E+OO Pb-212 Less than 2.3 E+Ol Bi-214 Less than 2.1 E+Ol Pb-214 Less than 2. 7 E+Ol Ra-226 Less than 2.4 E+02 Ac-228 Less than 5.9 E+Ol

-408-

VEPCo JAMES RIVER WATER SAMPLES.

• Date Collected 3-11-76 (picocuries per liter)

Hog Island Point Station Intake 3-15-76 Gamma S;eectrometrr K-40 Less than 1.1 E+02. Less than 1.0 E+02

, Co-58 5.0 + 5.0 E+OO Less than 6.6 E+OO Sb-125 Less than 3.0 E+Ol Less than 3.0 E+Ol Cs-137 Less than 9.1 E+OO 4.6 + 4.1 E+OO Tl-208 Less than 1. 0 E+Ol Less than 1. 0 E+Ol Pb-212 Less than 2.3 E+Ol Less than 2.3 E+Ol Bi-214 Less than 2.7 E+Ol 2. 4 + 2 . 0 E+Ol Pb-214 Less than 3.0 E+Ol 3.8 + 2.0 E+Ol Ra-226 Less than 2.4 E+02 Less than 2.5 E+02 Ac-228 Less than 5.8 E+Ol Less than 5.8 E+Ol

-*~------~------

• -409-

VEPCo JAMES RIVER WATER SAMPLES (picocuries per liter)

Chickahominy Newport News Date Collected 3-15-76 .3-15-76 Ganrrna SEectrometry K-40 Less than 8. 9 E+Ol- 1.4 + 0.8 E+02 Co-58 Less than 6.6 E+OO Less than 6.6 E+OO Sb-125 Less than 3.0 E+Ol Less than 3.0 E+Ol Cs-137 Less than 6.4 E+OO .Less than 6.8 E+OO Tl-208 Less than 1. 0 E+Ol Less than 1. 0 E+Ol Pb-212 Less than 2.3 E+Ol Less than 2.3 E+Ol Bi-214 Less than 2.9 E+Ol Less than 2.7 E+Ol Pb-214 Less than 3.0 E+Ol 2. 6 + 1. 9 E+Ol Ra-226 Less than 2.4 E+02 Less than 2.4 E+02 Ac-228 Less than 5.8 E+Ol Less than 5.8 E+Ol

-.410-

JAMES RIVER WATER SAMPLES (picocuries per liter)

Station Discharge Date Collected 3-11-76 Gannna Spectrometry K-40 Less than 9.2 E+Ol Co-58 4.8 + 4.4 E+OO Sb-125* Less than 3.0 E+Ol Cs-137 Less than 4.7 E+OO Tl-208 Less than 1. 0 E+Ol Pb-212 Less than 2.3 E+Ol Bi-214 Less than 2. 7 E+Ol Pb-214 Less than 3.0 E+Ol Ra-226 Less than 2.4 E+02 Ac-228 Less than 5.8 E+Ol

• ~-~--. -~~-

_/, 11- I

VP.PCo JAMES RIVER WATER SAMPLES (picocuries per liter)

Newport News Point of Shoals Date Collected 5-21-76 5-21-76 Radiochemistry Tritium (En.) Less than 3.7 E+02* Less than 3.7 E+02 Gamma Spectrometry K-40 1.8 + 0.9 E+02 1.2 + 0.9 E+02 Cr-.51 Less than 6.4 E+Ol Less than 6.4 E+Ol Sb-125 Less than 2.9 E+Ol Less than 2.9 E+Ol Cs-137 4.6 +/- 4.1 E+OO Less than 7.4 E+OO Ce-144 Less than 5.0 E+Ol Less than 5.0 E+Ol Tl-208 Less thari 8.9 E+OO Less than 8.8 E+OO Pb-212 Less.than 2.2 E+Ol Less than 2.4 E+Ol Bi-214 Less than 2.4 E+Ol Less than 2.4 E+Ol Pb-214 Less than 2.7 E+Ol Less than 2.7 E+Ol Ra-226 Less than 2.4 E+02 Less than 2.4 E+02 Ac-228. Less than 5o7 E+Ol Less than 5.7 E+Ol

-~ *-~~--- - -*--------'-, -------

-412-

JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Radiochemistry Station Discharge 5-21-76 Chickahominey 5-21-76 Tritium (En.) Less than 3. 7 E+02- Less than 3.7 E+02 Gamma SEectrometry K-40 Less than 1. 2 E+02 Less than 1. 2 E+02 Cr-51 8.1 + 4.3 E+Ol Less thari 6.4 E+Ol Sb-125 Less than 2.9 E+Ol Less than 2.9 E+Ol Cs-137 Less than 6.4 E+OO Less than 8.4 E+OO Ce-144 Less than 5.0 E+Ol Less than 5.0 E+Ol Tl-208 Less than 8.8 E+OO Less than 8.8 E+OO Pb-212 Less than 2.2 E+Ol Less than 2.2 E+Ol Bi-214 Less than 2.4 E+Ol Less than 2.4 E+Ol Pb-214 Less than 2.7 E+Ol Less than 2.7 E+Ol Ra-226 Less than 2.5 E+02 Less than 2.4 E+02 Ac-228 Less than 5.7 E+Ol Less than 5.7 E+Ol

_f,_11-

VEPCo JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Radiochemistrx Hog Island Point 5-21-76 Tritium (En.) Less than 3.7 E+02 Gamma SEectrometry K-40 1. 1 + 0. 8 E+02 Cr-51 Less than 6.4 E+Ol Sb-125 Less than 2.9 E+Ol Cs-137 Less than 4.0 E+OO Ce-144 Less than 5.0 E+Ol Tl-208 Less than 8.8 E+OO Pb-212 Less than 2.2 E+Ol Bi-214 Less than 2.4 E+Ol Pb-214 Less than 2.7 E+Ol Ra-226 Less than 2.4 E+02 Ac-228 Less than 5.7 E+Ol

-~-----~--~~~~

-414-

JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Chickahominx 7-22-76 Gannna S2ectrometry Hog Island Point 7-21-76' K-40 Less than 1. 3 E+02 9.1 + 7.6 E+Ol Cs-137 Less than 4.4 E+OO Less than 6.3 E+OO Pb-212 Less than 2.2 E+Ol Less than 2.3 E+Ol Bi-214 Less than 2.5 E+Ol Less than 2.4 E+02 Ra-226 Less than 2.4 E+02 Less than 2.4 E+02

-*-- -4b-*

JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Station Intake 7 76 Gamma S:eectrometry Station Discharge 7-21-76 K-40 1.1 + 0.9 E+02 Less than 1. 3 E+02 Cs-137 Less than 5.9 E+OO Less than 7.8 E+OO Pb-212 Less than 2.4 E+Ol Less than 2.2 E+Ol Bi-214 Less than 2.4 E+02 Less than 2.4 E+02 Ra-226 Less than 2.4 E+02 Less than 2.4 E+02

--*'-~ -416-

JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Newport News 7-21-76 Gamma Spectrometry K-40 1. 9 + 0. 9 E+02 Cs"".137 Less than 6.6 E+OO Pb-212

• Less than 2.2 E+Ol Bi-214 Less than 2.6 E+Ol Ra-226 Less than 2.4 E+02

• -.417-

JAMES RIVER WATER SAMPLES (picocuries per liter)

• Date Collected Radiochemistry Hog Island Point 9-23-76 Station Intake 9-23-76 Enr. Tritium 3.8 + 0.9 E+02 2.0 + 0.8 E+02 Gamma SEectrometry Be-7 5.3 + 3.0 E+Ol Less than 4. 5 E+Ol K-40 1. 2 + 0.9 E+02 1. 6 + 0. 9 E+02 Ru-106 Less than 6.6 E+Ol Less than 6.6 E+Ol I-131 Less than 1. 0 E+Ol Less than 1. 0 E+Ol Cs-137 Less than 7.2 E+OO Less than 8.0 E+OO Tl-208 Less than 9.6 E+OO Less than 9.6 E+OO Pb-212 Less than 2.3 E+Ol Less than 2.2 E+Ol Bi-214 Less than 4.5 E+Ol Less than 4.5 E+Ol Pb-214 Less than 5.0 E+Ol Less than 5.0 E+Ol Ra-226 Less than 2.4 E+02 Less than -2.4 E+02

JAMES RIVER WATER SAMPLES (picocuries per liter)

Chickahominy Station Discharge Date Collected 9-23-76 9-23-76 Radiochemistry Enr. Tritilllll , 2.6'+ 0.9 E+02

4. 0 + 0. 9 E+02 Gamma Spectrometry Be-7 Less than 4.5 E+Ol Less than 4.5 E+Ol K-40 Less than 8.5 E+Ol 7.5 + 7.2 E+Ol Ru-106 Less than 6.6 E+Ol Less than 6.6 E+Ol I-131 Less than 1.0 E+Ol Less than 1.0 E+Ol Cs-137 5.4 + 4.3 E+OO Less than 6.7 E+OO TL-208 Less than 9.6 E+OO Less than 9.6 E+OO Pb-212 Less than 2.3 E+Ol Less than 2.3 E+Ol Bi-214 Less than 4.5 E+Ol 3.5 +*3.0 E+Ol Pb-214 Less than 5.0 E+Ol Less than 5.0 E+Ol Ra-226 Less than 2.5 E+02 Less than 2.4 E+02

• -419*-

JAMES RIVER WATER SAMPLES (picocuries per liter)

Newport News Lawnes Creek Date Collected 10-29-76 10-29-76 Radiochemistry Enr. Tritium 7.5 + 3.7 E+02 7.6 + 4.6 E+02 Gross Alpha 0.0 + 5.2 E+OO 0.0 + 2.1 E+OO Gamma Spectrometry Be-7 4.4 + 3.7 E+Ol Less than 5.5 E+Ol K-40 1. 3 + 1. 0 E+02 Less than 1. 5 E+02

• Cr-51 5.2 + 4.1 E+Ol Less than 6.1 E+Ol

, Sb-125 Less than 2.9 E+Ol Less than 2.9 E+Ol Cs-137 Less than 7.9 E+OO Less than 6.8 E+OO Ce-141 Les*s than 1. 8 E+Ol Less than 1.8 E+Ol Tl-208 Less than 8.3 E+OO Less than 8.3 E+OO Pb-212 Less than 2.4 E+Ol

• Less than 2.3 E+Ol Bi-214 Less than 2.1 E+Ol 1.5 + 1.4 E+Ol Pb-214 Less than 2.6 E+Ol Less than 2.6 E+Ol Ra-226 Less than 2.4 E+02 Less .than 2. 4 E+02

JAMES RIVER WATER SAMPLES (picocuries per liter)

Point O' Shoals Deep Water Shoals Date Collected 10-29-76 10-29-76 Radiochemistry Enr. Tritium 3.7 + 3.7 E+02 2.6 + 2.6 E+02 Gross Beta 0.0 + 4.2 E+OO 7.0 + 5.2 E+OO Gannna Spectrometry Be-7 Less than 5.5 E+Ol Less than 5.5 E+Ol K-40 Less than 1. 5 E+02 Less than 1. 5 E+02 Cr-51 Less than 6.1 E+Ol Less than 6.1 E+Ol Sb-125 Less thaµ 2.9 E+Ol Less than 2.9 E+Ol Cs-137 Less than 6.0 E+OO Less than 5.2 E+OO Ce-141 Less than 1. 8 E+Ol Less than 1. 8 E+Ol Tl-208. Less than 8.3 E+OO Less than 8.3 E+OO Pb-212 Less than 2o3 E+Ol Less than 2.3 E+Ol Bi-214 Less than 2ol E+Ol Less than 2.1 E+Ol Pb-214 Less than 2.6 E+Ol Less than 2.6 E+Ol Ra....:226 Less than 2.4 E+02 Less than 2.4 E+02

• -421--

JAMES RIVER WATER SAMPLES (picocuries per liter)

Ne~ort News Station Intake Date Collected 11-17-76 11-17-76 Radiochemistrx Enr. Tritium 3.0 + 1.5 E+02 Less than 1. 5 E+02 Gamma Spectrometry K-40 1.3 + 1. 0 E+02 1. 1 + 1. 0 E+02 Sb-125 Less than 2.7 E+Ol Less than 2.7 E+Ol Cs-137 Less than 7.0 E+OO Less than 5.6 E+OO Ce-141 Less than 1. 9 E+Ol Less than 1. 9 E+Ol Bi-212 5.9 + 5.8 E+Ol Less than 8.7 E+Ol Pb-212 Less than 2.2 E+Ol Less than 2.3 E+Ol Bi-214 5.4 + 3.4 E+Ol Less than 2.5 E+Ol Pb-214 2.1 + 2.0 E+Ol Less than 4. 7 E+Ol Ra-226 Less than 2.4 E+02 Less than 2.4 E+02 Ac-228 Less than 5.9 E+Ol Less than 5.9 E+Ol

• -422-

• Date JAMES RIVER WATER SAMPLES (picocuries per liter)

Station Discharge Chickahominex Collected* 11-17-76 11-17-76 Radiochemistrx Enr. Tritium 2. 4 + 1. 6 E+02 Less than 1.3 E+02 Gamma SEectrometry*

K-40 Less than 1. 3 E+02 Less than 1. 3 E+02 Sb-125 Less than 2.7 E+Ol Less than 2.7 E+Ol *.

Cs-137 Less than 7.6 E+OO Less* than 6.7 E+OO Ce-141 Less than 1. 9 E+Ol Less than 1. 9 E+Ol Bi-212 Less than 8.7 E+Ol Less than 8.7 E+Ol Pb-212 Less than 2.3 E+Ol Less than 2.2 E+Ol Bi-214 Less than 2.5 E+Ol Less than 2.5 E+Ol Pb-214 Less than 4. 7 E+Ol Less than 4.7 E+Ol Ra-226 Less than 2.5 E+02 Less than 2.4 E+02 Ac-228 Less than 5.9 E+Ol Less than 5.9 E+Ol

-423-

• Date JAMES. RIVER WATER SAMPLES (picocuries per liter)

Hog Island Point

• Collected 11-17-76 Radiochemistry Enr. Tritium 2.2 + 1.3 E+02 Gamma SEectrometr:y K-40 Less than 1. 3 E+02 Sb-125 Less than 2.7 E+Ol Cs-137 Less than (5.0 E+OO Ce-141 Less than 1. 9 E+Ol Bi-212 Less than 8.7 E+Ol Pb-212 Less than 2.3 E+Ol Bi-214 Less than 2.5 E+Ol Pb-214 Less than 4.7 E+Ol

. Ra-226 Less than 2.4 E+02 Ac-228 Less than 5.9 E+Ol J

• -424-

VEPCo JAMES RIVER WATER SAMPLES

• (picocuries per liter)

SEMI-ANNUAL COMPOSITE 1976 Chickahominey Newport News Tritium (En.) 2.0 + 1.0 E+02 5.7 + 2.0 E+02

• -425-

• JAMES RIVER WATER SAMPLES (picocuries per liter) 2nd SEMI-ANNUAL COMPOSITE 1976 Chickahominey Newport News Enr. Tritium 2.1 + 1.0 E+02 3. 3 + 1. 1 E+02

-426-

• Date SPECIAL WATER SAMPLES (picocuries per liter)

Discharge Canal Collected 7-6-76 Radiochemistry Tritium (L.S.) Less than 3.7 E+02 Gamma Spectrometry Mn-54 8.5 + 5.1 E+OO Co-58 2.7 + 0.9 E+Ol Co-60 3. 6 + 1. 1 E+Ol Cs-134 1. 0 + 0. 9 E+O 1 Cs-137 3 . 6 + 1. 1 E+O 1 Pb-212 Less than 2.3 E+Ol Pb-214 Less than 3.1 E+Ol Ra-226 Less than 2.6 E+02

-427-

• Date SPECIAL WATER SAMPLES (picocuries per liter)

Discharge Canal Collected 10-19-76 Radiochemistry Gross Alpha 0.0 + 5.2 E+OO Gross Beta 5. 9 + 1. 2 E+O 1 Enr. Tritium 5. 0 +/- 1. 5 E+02 Gamma Spectrometry Co-60 1. 9 + 0. 8 E+Ol Mn-54 6.5 + 4.1 E+OO Cs-134 L 5 + 0. 6 E+Ol Cs-137 2.9 + 0.8 E+Ol Ph-212 Les$ than 2.4 E+Ol

-428-

VEPCo SILT SAMPLES (picocuries per kilogram dry)

Station Intake Point of Shoals Date Collected 3-15-76 3-15-76 Sample Weight Dry 0.129 kg 0.1285 kg Gamma Spectrometry K-40 1.4 + 0. 3 E+04 1. 3 + 0. 3 E+04 Mn-54 Less than 1.5 E+02 Less than 1. 5 E+02 Co-58 Less than 1. 5 E+02 1. 2 + 1. 0 E+02 Co-60 Less than 1. 6 E+02 1.8+1.0 E+02 Cs-134 6. 5 + 1. 0 E+02 2.3 + 0.9 E+02 Cs-137 Less than 3.0 E+02 1. 0 + 0. 2 E+O 3 Hg-203 Less than 2.2 E+02 Less than 2.2 E+02 Tl-208 4 . 0 +. 1. 4 E+O 2 3.0 + 1.6 E+02 Bi-212 1. 5 + 1. 4 E+03 Less than 2.1 E+03 Pb-212

• 1. 3 + 0. 4 E+03 1. 6 + 0. 4 E+03 Bi-214 1. 5 + 0. 4 E+03 1. 0 + 0. 4 E+O 3 Pb-214 9

• 0 + 1. 6 E+O 2 7. 2 + ~,. 8 E+02 Ra-226 4.2 + 3.5 E+03 4.3 + 3.5 E+03 Ac-228 1. 4 +/- 0. 7 E+03 1. 4 + 0. 7 E+03

• 429-

VEPCo .

SILT SAMPLES

• • Date Collected (picocuries per kilogram dry)

Newport 3-15-76 News Station Discharge 3-15-76 Sample Weight Dry 0.164 kg 0.1115 kg Gamma Spectrometry K-40 1. 5 + 0. 2 E+04 L4 + 0.3 E+03 Mn-54 . Less than 1.1 E+02 Less than 1.7 E+02 Co-58 Less than 1.1 E+02 Less than 1.7 E+02 Co-60 Less than 1.3 E+02 Less than 1.9 E+oz*

Cs-134 Less than 1.0 E+02 1. 8 + 1. 1

• E+02 Cs-137 3. 4 + 1. 0 E+02 2. 0 + 1. 3 E+02 Hg-203 Less than 1.7 E+02 Less than 2. 5 E+02 Tl-208 2

• 3 + 1. 1 E+O 2 4. 0 + 1. 7 E+02 Bi-212 Less than 1.6 E+03 1. 6 + 1. 4 E+03 Pb:...212 1. 2 + 0. 3 E+O 3 1. 4 + 0

• 4 E+O 3 Bi-214 6.8 + 3.0 E+02 7.0 + 3.0.E+02 Pb-214 6.8 + 2.8 E+02 9.7 + 3.8 E+02 Ra-226 Less than 3.9 E+03 Less than 5.9 E+03

• Ac-228 8.0 + 4.8 E+02 1.5 + 0. 7 E+03

\_

-430-

VEPCo SILT SAMPLES (picocuries per kilogram dry)

• Date Collected Sample Weight Dry Chickahominey 3-15-76 0.093 kg Hog Island Point 3-15-76 0.082 kg Gamma Spectrometry K-40 1. 2 + 0 . 3 E+04 1. 2 +/- 0. 2 E+04 Mn-54 Less than 1. 9 E+02 Less than 2.2 E+02 Co-58 Less than 1. 9 E+02 Less than 1. 5 E+02 Co-60 Less than 2.3 E+02 Less than 2.6 E+02 cs..:.134 1. 4 + 1. 0 E+02 Less than 2.0 E+02 Cs-137 4. 5 + 1. 7 E+O 2 Less than 2.1 E+02 Hg-203 Less than 2.8 E+02 Less than 3.4 E+02 Tl-208 2.7 +.._ 2.0 E+02 4. 6 + 1. 6 E+02 Bi-214 Less than 2.8 E+03 Less than 3.2 E+03 Pb-212 1. 6 + 0. 4 E+03 1. 6 + 0. 4 E+03 Bi-214 9.1 + 3.5 E+02 4. 6 + 0. 6 E+03 Pb-214 1. 4 +/- 0. 4 E+03 7.0 + 0.5 E+03 Ra-226 Less than 6.5 E+03 Less than 5.9 E+03 Ac-228 8.4 + 8.2 E+02 1. 4 + 0 . 8 E+O 3

-431-

• Date Collected 9-23-76 SILT SAMPLES (picocuries per kilogram dry)

Station Discharge Chickahominz 9-23-76 Sample Weight Dry 0.116 kg 0.093 kg Gamma Spectrometry K-40 1 . 8 + 0. 3 E+04 1. 4 + 0. 3 E+04 Mn-54 4. 1 + 1. 6 E+O 2 Less than 3.0 E+02 co-58 9 . *4 + 2 . 0 E+O 2 Less than 3.7 E+02 Co-60 2.5 + 0.3 E+03 Less than 1. 9 E+02 Nb-95 1. 7 + 1. 6 E+02 Less than 3.0 E+02 Cs-134 1.0 +/- 0.2 E+03 Less than 3. 7 E+02 Cs-137 3.3 + 0.3 E+03 1. 1 + 0. 2 E+O 3 Tl-208 5 . 5 + 1. 9 E+O 2 4. 5 + 1. 8 E+O 2 Bi-212 2.6 +/- 2.0 E+03 1. 8 + 1. 8 E+03 Pb-212 1. 6 + 0. 4 E+03 1. 6 + 0. 4 E+03 Bi-214 1. 1 + 0. 5 E+03 1.1 + 0.4 E+03 Pb-214 1.4 + 0.4 E+03 1. 4 + 0. 5 E+O 3 Ra-226 Less than 6.5 E+03 4.9 + 4.5 E+03 Ac-228 1.6 + 0.9 E+03 9.2 + 8.9 E+02

-432-

l

• Date SILT SAMPLES (picocuries per kilogram dry)

Hog Island Point Collected 9-23-76 Sample Weight Dry Oolll kg Gamma Spectrometry K-40 L 5 + 0. 3 E+04 Mn-54 Less than 2.5 E+02 Co-58 Less than 3.1 E+02 Co-60 Less than 1. 6 E+02 Nb-95 Less than 2.5 E+02

.Cs-134 Less than 3.1 E+02 Cs-137 Less than 2.1 E+02 Tl-208 4 . 6 + 1. 7 E+O 2 Bi-212 Less than 2.3 E+03 Pb-212 1. 7 + 0 o4 E+03 Bi-214 908 + 3o9 E+02 Pb-214 lo4 + Oo4 E+03 Ra-226 Less than 5.8 E+03 Ac-228 1. 5 +/- 0. 8 E+03

-433-

• *Date Collected SILT SAMPLES (picocuries per kilogram dry)

Station Intake Newport News 10-29-76 10-29-76 Sample Weight Dry 0.1085 kg 0.1145 kg Gamma Spectrometry*.**

Be-7 1. 3 + 1. 1 E+03 Less than 1.6 E+03 K-40 1. 0 + 0. 3 E+04 1. 4 + 0 . 3 E+04 Mn-54 1.1 + 1. 0 E+02 Less than 1. 4 E+02

• Nb-95 Less than 1.9 E+02 Less than 1.8 E+02 Zr-95

• Less than 2.7 E+02 Less than 2.5 E+02 Ru-103 Less than 1. 9 E+02 Less than 1.8 E+02 Cs-134 1. 4, + 0. 9 E+O 2 Less than 1.3 E+02 Cs-137 6.5 +/- 1.6 E+02 5. 6 + 1. 6 E+O 2 Ce-141 5.6 + 3.2 E+02 Less than 4.1 E+02 Tl-208 2

• 8 + 1. 7 E+O 2 2. 4 + 1. 6 E+O 2 Bi-212 Less than .2.5 E+03 1. 6 + 1. 3 E+03 Pb-212 1. 0 + 0. 4 E+03 1. 4 + 0. 4 E+03 Bi-214 9.2 + 3.0 E+02 5. 0 + 3. 0 E+O 2 Pb-214 1.1 + 0. 4 E+03 . 1.2 + 0.4 E+03 Ra-226 4.5 + 3.8 E+03 Less than 5.5 E+03 Ac-228 9.8 +'7.3 E+02 1. 3 +/- 0. 6 E+03

-434-

VEPCo OYSTER SAMPLES (picocuries per kilogram)

• Date Collected Sample Weight Dry/Wet Newport News 1-26-76 0.020/0.3285 kg Point of Shoals 1-26-76 0.026./0.241 kg Gamma Spectrometry K-40 3.5 + 3.2 E+02 1. 7 +/- 0. 5 E+03 Co-58 3.8* + 2.1 E+Ol 4.0 + 2o2 E+Ol Co-60 2*2 +/- 1. 9 E+O 1 2.6 + 2.6 E+Ol Ru-103 1. 7 + 1. 2 E+O 1 Less than 1.4 E+Ol Cs-137 2.6 + 2.1 E+Ol 1. 1 + 0. 4 E+02 Ce-141 Less than 1.1 E+02 Less than 8.2 E+Ol Tl-208 Less than 6.0 E+Ol Less than 4.6 E+Ol Pb-212 Less than 7.0 E+Ol Less than 1.1 E+02 Bi-214 Less than 1.4 E+02 8. 5 + 7. 3 E+Ol Pb-214 Less than 8.9 E+Ol Less than 1. 3 E+02 Ra-226 Less than 7.6 E+02 Less than 1.1 E+03

• . -435-

VEPCo

• Date Collected OYSTER SAMPLES (picocuries per kilogram)

Deep Water.Shoals 1-26-76 Sample Weight Dry/Wet 0.018/0.284 kg Gamma Spectrometry K-40 6.8 + 4.1 E+02 Co-58 Less than 3.5 E+Ol Co-60 Less than 2.9 E+Ol Ru-103 Less than 2.0 E+Ol Cs-137 2.8 + 2.3 E+Ol Ce-141 Less than 1. 2 E+02 Tl-208 Less than 6.7 E+Ol Pb-212 Less than 8.3 E+Ol Bi-214 Less than 1.5 E+02 Pb-214 Less than 1. 9 E+02 Ra-226 Less than 8.9 E+02

• -ti36-

VEPCo OYSTER SAMPLES

• Date.

Collected Sample Weight (picocuries per kilogram wet)

DeeE Water Shoals 3-15-76 Point of Shoals 3-15-76 Dry/Wet 0.0145/0.177 0.016/0.2825 Gamma SEectrometry K-40 6.4 + 5.9 E+02 4.9 + 3.*o E+02 Co-58 4.6 + 3.6 E+Ol 3.0 + 2.3 E+Ol Sb-125 Less than 1. 2 E+02 Less than 1.1 E+02 Cs-137 Less than 5.6 E+Ol Less than 3.7 E+Ol Tl-208 Less than 5.8 E+Ol Less than 3.5 E+Ol Pb-212 Less than 1.4 E+02 Less than 1. 3 E+02 Bi-214 1. 9 + 1. 4 E+02 Less than 1. 9 E+02 Pb-214 Less than 1. 7 E+02 Less than 1. 0 E+02 Ra-226 Less than 1.4 E+OJ Less than 1. 3 E+03

-437-I

VEPCo OYSTER SAMPLES (picocuries per kilogram wet)

• Date Collected Sample Weight Naseway Shoals 3-11-76 Dry/Wet . 0.0235/0.331 Gamma Spectrometry K-40 7.7 + 3.7 E+02 Co-58 6.7 + 2.0 E+Ol Sb-125 Less than 7.5 E+Ol Cs-137 Less than 2.0 E+Ol Tl-208 Less than 2.4 E+Ol Pb-212 Less than 6.9 E+Ol Bi-214 Less than 1. 3 E+02 Pb-214 Less than 6.8 E+Ol Ra-226 Less than 7.6 E+02

• -438-

VEPCo OYSTER SAMPLES (picocuries per kilogram)

Newport News Date Collected 5-11-76 Sample Weight Dry/Wet 0.440 kg Gamma Spectrometry K-40 1. 6 + 0. 5 E+03 Mn-54 Less than 1.2 E+Ol Co-58 Less than 3.9 E+Ol Co-60 Less than 1. 7 E+Ol Sb-125 Less than 6.1 E+Ol Cs-137 Less than 4.3 E+Ol Ce-141 Less than 4.2 E+Ol Tl-208 **~--Less than 4. 8 E+Ol Bi-212 Less than 6.0 E+02 Pb-212 Less than 1.3 E+02 Pb-214 Less than 6.1 E+Ol Ra-226 Less than 5.6 E+02 Ac-228 Less than 1.3 E+02

-439-

VEPCo OYSTER SAMPLES (picocuries per kilogram wet)

Point of Shoals .. Deep .water Shoals Date Collected 5-21-76 5-21-76 Sample Weight Dry/Wet. 0.193 kg 0.130 kg Gamma Spectrometry K-40 8.0 + 4.5 E+02 8.8 + 8.0 E+02 Mn-54 Less than 2.8 E+Ol 3.2 + 2.8 E+Ol Co-58 2.2 + 1.8 E+Ol 5. 4 +

- 3

• 7 E+O. 1 Co-60 Less than 3.9 E+Ol Less than 5.8 E+Ol Sb-125 Less than 1.4 E+02 Less than 2.1 E+02 Cs-137 Less than 4.7 E+Ol Less than 7.0 E+Ol Ce-141 Less than 9.6 E+Ol Less than 1. 4 E+02

• Tl-208 *~Less than 1.1 E+02 Less than 7.0 E+Ol Bi-212 Less than 5.2 E+02 Less than 7.7 E+02 Pb-212 Less than 1. 2 E+02 .Less than 1. 8 E+02 Pb-214 Less than 1. 4 E+02 Less than 2.1 E+02 Ra-226 Less than 1. 3 E+03 Less than 1. 9 E+03 Ac-228 Less than 3.0 E+02 Less than 4.5 E+02

.:..440-

• Date Collected 7-21-76 OYSTER SAMPLES (picocuries per kilogram wet)

Deep Water Shoals Newport News 7-21-76 Sample Weight Dry/Wet 0.0175/0.1873 kg 0.01500/0.1270 kg Gamma Spectrometry K-40 8.6 + 4.8 E+02 2.1 + 0.8 E+03 Co-60 Less than 4.6 E+Ol Less than 6.8 E+Ol Sb-125 Less than 1. 5 E+02 Less than 2.3 E+02 Cs-137 Less than 5.6 E+Ol Less than 8.3 E+Ol Ce-141 Less than 1. 0 E+02 Less than 1. 5 E+02 Tl-208 tess than 5.4 E+Ol Less than 7.6 E+Ol Pb-212 Less than 1.3 E+02 Less than 1. 9 E+02 Bi-214 Less than 1. 4 E+02 Less than 2.0 E+02 Pb-214 Less than 1. 5 E+02 Less than 2.3 E+02 Ra-226 Less than L 3 E+03 Less than 1. 9 E+03

-441-

• Date OYSTER SAMPLES (picocuries per kilogram wet)

Point of Shoals Collected 7-21-76 Sample Weight Dry/Wet 0.0270/0.2882 kg Gamma Spectrometry K-40 4.1 + 4.0 E+02 Co-60 Less than 3.0 E+Ol Sb-125 Less than 1.0 E+02 Cs-137 Less than 3.6 E+Ol Ce-141 Less than 6.7 E+Ol Tl-208 Less than 3.5 E+Ol Pb-212 Less than 8.4 E+Ol Bi-214 Less than 8.8 E+Ol Pb-214 Less than 1.0 E+02 Ra-226 Less than 8 ..5 E+02

• Date OYSTER SAMPLES (picocuries per kilogram wet)

James River Bridge DeeE Water Shoals Collected 9-9-76 9-9-76 Sample Weight Dry/Wet 0.0220/0.2465 kg. 0.0185/0.2079 kg.

Garmna SEectrometry K-40 6.4 + 4.9 E+02 8.1 + 4.4 E+02 Ag-llOm Less than 2.5 E+Ol 4.7 + 3.0 E+Ol Cs-137 Less than 2.0 E+Ol Less than 3.3 E+Ol Tl-208 Less than 3.8 E+Ol Less than 4.5 E+Ol Pb-212 Less than 9.1 E+Ol Less than 1. 2 E+02 Bi-214 Less than 1. o E+02 -Less than 1. 2 E+02 Pb-214 Less than 1.1 E+02 Less than 1. 3 E+02 Ra-226 Less than 9.7 E+02 Less than 1.1 E+03

-443-

• Date Collected OYSTER SAMPLES (picocuries per kilogram wet)

• Naseway Shoals 11~29~76 Sample Weight Dry/Wet 0.041/0.412 kg.

Gamma Spectrometry K-40 1.4 + 0.5 E+03 Co-60 Less than 3.1 E+Ol

. Nb-95 Less than 2.0 E+Ol Zr-95 Less than 1.9 E+Ol Ru-103 3. 8 + 2. 1 E+Ol Cs-137 2 . 0 + 1. 4 E+O 1 Ge-141 Less than 4.6 E+Ol Pb-212 Less than 1. 2 E+02 Pb-214 Less than 9.7 E+Ol Ra-226 Less* than 1.4 E+OJ

. Ac-228 Less than 1.4 E+02

-444-

• .Date Collected 11-30-76 OYSTER SAMPLES (picocuries per kilogram wet)

Point of Shoals Deep Water Shoals 11-30-76

.Sample Weight

• Dry/Wet 0.0250/0.3426 kg. 0.0215/0.3049 kg.

• Gamma Spectrometry K-40 4 .5. + 3 2 E+02 0 Less than 6.1 E+02 Co-60 Less than 3.7 E+Ol Less than 4.2 E+Ol Nb-95 Less than 2.4 E+Ol Less than 2. 7 E+Ol .

Zr-95 Less than 2.3 E+Ol Less than 2.6 E+Ol Ru-103 Less than 3. 8 E+Ol

• Less than 4. 3 E+Ol Cs-137 Less than* 2.4.E+Ol 1. 8 + 1. 4 E+Ol Ce-141 Less than 5.5 E+Ol Less than 6.2 E+Ol Pb~212 Less than 6.6 E+Ol* ,Less than 7.5E+Ol Pb-214 Less than 8.1 E+Ol Less than 9 *.1 E+Ol Ra-226 Less than. 7.3 E+02 Less than 1. 9 E+03

.,_Ac-228 Less than 1. 7 E+02 Less than 1. 9 E+02 .

=445-

VEPCo

• Date Collected 1-13-76 CLAM SAMPLES (picocuries per kilogram wet)

Lawnes Creek Chickahominy 1-13-76 Sample Weight Dry/Wet 0.0215/0.418 0.0215/0.316 Radiochemistry

.Sr-89 0.0 + 5.0 E+OO 0.0 + 8*,4 E+OO Sr-90 0.0 + 4.3 E+OO 1. 7 + 0 . 5 E+O 1 Gamma S:eectrometry K-40 Less than 3.0 E+02 Less than 4.4 E+02 Co-58 2. 4 +/- 1. 4 E+Ol Less than 4.8 E+Ol Co-60 Less than 3.5 E+Ol Less than 3.5 E+Ol Ag-llOm Less than 2.2 E+Ol Less than 2o2 E+Ol Sb-125 Less than 7.2 E+Ol Less than 908 E+Ol Cs-137 Less than 1. 8 E+Ol 1.9 + 1.8 E+Ol Tl-208 Less than 2.3 E+Ol Less than 3.1 E+Ol Bi-212 Less than 2.4 E+02 Less than 2.4 E+02 Pb-212 Less than 5.5 E+Ol Less than 7.9 E+Ol Pb-214 Less than 1. 2 E+02 7.0 + 5.9 E+Ol Ra-226 Less than 6.0 E+02 Less than 7.9 E+02

• -446-

VEl'Co CLAM SAMPLES (picocuries per kilogram wet)

• Date Collected Sample*Weight Jamestowne 1-13-76 Station Discharge 1 76 Dry/Wet 0.0215/0.434 Kg 0.023/0.416 kg Radiochemistry Sr-89 0.0 + 6.1 E+OO 0.0 + 6.4 E+OO Sr-90 6.0 + 3.5 E+OO 4.1 + 3.6 E+OO Gamma Spectrometry K-40 Less than 3.4 E+02 Less than 3.7 E+02 Co-58 Less than 4.8 E+Ol 1. 3 + 0. 3 E+02 Co-60 Less than 3.5 E+Ol 6.8 + 2.2 E+Ol Ag-llOm Less than 2.2 E+Ol 2. 7 + 1. 4 E+O 1 Sb-125 Less than 1.1 E+02 Less than 1. 0 °E+02 Cs-137 1. 7 + 1. 6 E+O 1 2.6 + 2.4 E+Ol Tl-208 Less than 2.3 E+Ol Less than 2.1 E+Ol Bi:...212 1.6 + L6 E+02 Less than 2.2 E+02 Pb-212 Less than 5.5 E+Ol Less than 6.0 E+Ol Pb-214 Less than 1. 2 E+02 Less than 7.2 E+Ol Ra-226 Less than 5.8 E+02 Less than 6.5 E+02

• I l

I j

_/, I, 7-

VEPCo CLAM SAMPLES

• Date Collected Sample Weight (picocuries per kilogram wet)

Hog Island Point 1-13-76 Dry/Wet 00023/0.273 Radiochemistry Sr-89 0.0 + 8.8 E+OO Sr-90 0.0 + 7.6 E+OO Gannna Spectrometry K-40 6.8 +/- 4.2 E+02 Co-58 Less than 4.5 E+Ol Co-60 Less than 3.3 E+Ol Ag-llOm Less than 2.1 E+Ol

• Sb-125 Less than loO E+02 Cs-137 Less than 408 E+Ol Tl-208 Less than 4.1 E+Ol Bi-212 Less than 2.2 E+02 Pb-212 Less than 9.7 E+Ol Pb-214 Less than 1.1 E+02 Ra-226 Less than 9.2 E+02

-448-

VEPCo CLAM SAMPLES (picocuries per kilogram wet)

Jamestowne Station Discharge Date Collected 3-15-76 3-15-76 Sample Weight Dry/Wet 0.0215/0.287 kg 0.0205/0.330 kg Gamma Spectrometry Be-7 Less than 3.1 E+02 Less than 3.2 E+02 K-40 Less than 4.6 E+02 2.3 + 2.2 E+02 Cr-51 Less than 2.2 E+02 Less than 2.3 E+02 Mn-54 Less than 3.1 E+Ol Less than 3.2 E+Ol Co-58 6.2 + 2.4 E+Ol 1. 9 + 0 . 4 E+O 2 Co-60 , Less than 2.7 E+Ol 4.5 + 3.6 E+Ol I-131 Less than 3.7 E+Ol 2.8 + 2.6 E+Ol Cs-134 Less* than 4.1 E+Ol Less than 4.3 E+Ol Cs-137 1.9 + 1.8 E+Ol 2.9 + 2.5 E+Ol Tl-208 Less than 5.1 E+Ol Less than 5.4 E+Ol Pb-212 Less than 8.2 E+Ol Less than 7.3 E+Ol Bi-214 Less than 1.0 E+02 Less than 1.1 E+02 Pb-214 Less than 9.4 E+Ol Less than 9.5 E+Ol Ra-226 Less than 8.4 E+02 Less than 7.9 E+02 Ac-228 Less than 2.1 E+02 Less than 2.2 E+02

• -449-

VEPCo CLAM SAMPLES

• • Date Collected (picocuries per kilogram wet)

Lawnes Creek 3-15-76' Hog Island Point 3-15-76 Sample Weight

• Dry/Wet 0.015/0.2115 kg o.~075/0.1195 kg Gaunna SEectrometr?

Be-7 2.3 + 2_.0 E+02 4.2 + 3.3 E+02 K-40 Less than 6.6 E+02

• Less than 1.3 E+03 Cr-51 Less than 3.1 E+02 Less :than 6.3 E+02 Mn-54 Less than 4.4 E+02 Less than 8.8 E+Ol Co-58 4.2 + 4.1 E+Ol 3.2 + 0.8 E+02 Co-60 Less than 4.0 E+Ol Less than 7.9 E+Ol

.I-131 3.7 + 3.5 E+Ol 7.9 + 6.8 E+Ol Cs-134 Less than 5.9 E+Ol Less than 1.2 E+02 Cs-137 Less than 3. 8 E+.01 7.1 + 4.5 E+Ol Tl-208 Less than 4.6 E+Ol Less than 1. 5 E+02 Pb-212 Less than 1.1 E+02 Less than 2.0 E+02 Bi-214 Less than 1. 5 E+02 Less than 3.0 E+02 Pb-214 Less than 1. 3 E+02 Less than 2.6 E+02 Ra-226 Less than 1. 2 E+03 Less than 2.4 E+03 Ac-228 Less than 3.0 E+02 Less than 5.2 E+02 I.

i

-450-

VEPCo I. Date C'o1lecttea1

- CLAM SAMPLES (picocuries per kilogram wet)

Chickahominy-J-15-76 Sample Weight DrylWet - 0.0245/0.258 Gatmlla Spectrometry Be-7 Less than 2.7 E+02 K-40 6.0 + 3.4 E+02 Cr-51 Less than 1.9 E+02 Mn-54 2.2 + 1.8 E+Ol Co-58 2.2 + 0.4 E+02 Co-60 Less than*4.1 E+Ol I-131 - Less than 3.2 E+Ol Cs-134 Less than 3.6 E+Ol Cs-137 8.6 + 3.0 E+Ol Tl-208 Less than 4.5 E+Ol Pb-212 - Less than 1. 0 E+02 Bi-214 1.5 + 0.8 E+02 r

Pb-214 L 5 + O. 8 E+02 Ra-22~ Less than 9.8 _E+02 Ac-228 Less than 2.7 E+02

-451-

VEPCo CLAM SAMPLES (picocuries per kilogram wet)

Chickahominx Jamestowne Date Collected 5-21-76 5-21-76 Sample Weight Dry/Wet 0.352 kg. 0.235 kg.

Gamma S:Eectrometri K-40 Less than 3.5 E+02 4.9 + 3.4 E+02 Co-58 3. 0 + 1. 2 E+O 1 Less than 4.2 E+Ol Co-60 Less than 3.0 E+Ol Less than 4.5 E+Ol Ag-llOm Less than 3.2 E+Ol Less than 4.8 E+Ol Sb-125 Less than 7.3 E+Ol Less than 1.1 E+02 Cs-134 Less than 2.1 E+Ol Less than 3.1 E+Ol Cs-137 2. 5 + 1. 4 E+Ol 2.6 + 2.1 E+Ol Ce-141 Less* than 5.3 E+Ol Less than 8.0 E+Ol Ce-144 1.0 + 0.9 E+02 Less than 2.0 E+02 Tl-208 Less than 2.9 E+Ol Less than 4.3 E+Ol Pb-212 Less than 6.6 E+Ol Less than 1. 0 E+02 Bi-214 7.1 + 5.1 E+Ol Less than 1.1 E+02 Pb-214 Less than 7.9 E+Ol Less than 1. 2 E+02 Ra-226 Less than 6.9 E+02 Less than 1.0 E+03 Ac-228 Less than 1. 7 E+02 Less than 2.6 E+02

-452-

VEPCo CLAM SAMPLES (picocuries per kilogram wet)

Hog Island Point Lawnes Creek Date Collected 5-21-76 5-21-76 Sample Weight Dry/Wet 0.212 kg 0.214 kg Ganuna S12ectrometri K-40 Less than 7.1 E+02 6.1 + 5.0 E+02 Co-58 9.7 + 3.6 E+Ol Less than 4.6 E+Ol Co-60 Less than 4.6 E+Ol Less than 5.0 E+Ol Ag-llOm Less than 5.3 E+Ol Less than 5.2 E+Ol Sb-125 Less than 1. 2 E+02 Less than 1.2*E+02 Cs-134 3.3 + 2.3 E+Ol Less than 3.4 E+Ol Cs-137 3.0 + 2.8 E+Ol 3.1 + 2.6 E+Ol Ce-141 Less than 8.9 E+Ol Less than 8.8 E+Ol Ce-144 Less than 2.2 E+02 Less than 2.2 E+02 Tl-208 Less than 4.6 E+Ol Less than 4.8 E+Ol Pb-212 Less than 1.1 E+02 Less than 1.1 E+02 Bi-214 Less than 1. 2 E+02 Less than 1. 2 E+02 Pb-214 Less than 1. 3 E+02 Less than 1. 3 E+02 Ra-226 Less than 1. 2 E+03 Less than 1.1 E+03 Ac-228 Less than 2.9 E+02 Less than 2.9 E+02

-453-

VEPCo

. CLAM SAMPLES

• • • Dftte Collected (picocuries per kilogram wet)

Station Discharge 5-21-76 Sample Weight Dry/Wet 0.261 kg Gamma S2ectrometrI K-40 Less than 4.6 E+02 Co-58 Less than 3.8 E+Ol Co-60 Less than 4.1 E+Ol Ag-llOM Less than 4.3 E+Ol Sb-125 Less than 9.9 E+Ol Cs-134 Less than 2.8 E+Ol Cs-137 Less than 3.9 E+Ol Ce-141 Less than 7.2 E+Ol Ce-144 Less than 1. 8 E+02 Tl-208 Less than 3.9 E+Ol Pb-212 Less than 9.0 E+Ol Bi-214 Less than 1. 0 E+02 Pb-214 Less than 1. 0 E+02 Ra-226 Less than 9.0 E+02 Ac-228 Less than 2.3 E+02

-li.C,li.-

'i i:

I

• Date Collected CLAM SAMPLES (picocuries per kilogram wet)

Hog Island Point 7-22-76 Station Discharge 7-22-76

\

I

)

I.

Sample Weight Dry/Wet 0.0215/0.1920 kg 0.0440/0.3002 kg Gamma SEectroinetri K-40 Less than 1.1 E+03 9.6 + 5.5 E+02 Co-58 Less than 5.7 E+Ol 8.2 + 3.2 E+Ol Co-60 . 1 . 0 + 0

• 5 E+O 2 7.4 + 4.6 E+Ol Cs-134 Less than 6.2 E+Ol Less than 4.0 E+Ol Cs-137 Less than 7.8 E+Ol Less than 5.5 E+Ol Ge-141 Less than 2.5 E+02 Less than 1. 6 E+02 Tl-208 Less than 1. 2 E+02 Less than 5.7 E+Ol Pb-212 Less *than 2.7 E+02 Less than 1. 7 E+02 Bi-214 4. 8 + 2

• 2 E+O 2 Less than LS E+02 Pb-214 1.1 + 0.2 E+03 Less than 2.0 E+02 Ra~226 Less than 3.0 E+03 Less than 1. 9 E+03

• Date CLAM SAMPLES (picocuries per kilogram wet)

Lawnes Creek Chickahominy Collected 7-22-76 7-22-76 Sample Weight Dry/Wet 0.0320/0.2014 kg 0.0175/0.1445 kg Gamma Spectrometry K-40 1.2 + Oo9 E+03 1. 1 + 0 . 8 E+O 3 Co-58 7.1 + 4.3 E+Ol Less than 7.6 E+Ol Co-60 5.2 + 3.6 E+Ol Less than 9.4 E+Ol Cs-134 Less than 6.0 E+Ol Less than 8.3 E+Ol Cs-137 Less than 6.7 E+Ol Less than 5.2 E+Ol Ce-141 Less than 2.4 E+02 Less than 3.3 E+02 Tl-208 Less than 1.2 E+02 Less than 1.7 E+02 Pb-212 Less than 2.5 E+02 Less than 3.5 E+02 Bi-214 2o4 + L 5 E+02 Less than 3.2 E+02 Pb-214 2.3 + 2.0 E+02 Less than 3.8 E+02

.Ra-226 Less than 2.8 E+03 Less than 3.8 E+03

-456-

• Date Collected Jamestown 7-22-76.

CLAM SAMPLES (picocuries per kilogram wet)

Sample Weight

. Dry/Wet 0.0350/0.2185 kg Gamma Spectrometry K-40 L 1 + 0. 6 E+03 Co-58 Less than 5.0 E+Ol Co-60 4.0 + 2.9 E+Ol Cs-134 Less.tha.il 5.5 E+Ol Cs-137 Less than 6.2 E+Ol Ce-141 Less than 2.2 E+02 Tl-208 . Less than 1.1 E+02 Pb-212 Less than 2.2 E+02 Bi-214.* 2 . 6 + 1. 6 E+O 2

• Pb-214 2 . 7 + 1. 6 E+O 2 Ra-226 Less than 2.5 E+03

• II I

II

-457-

• Date CLAM SAMPLES (picocuries per kilogram wet)

Station Discharge Chickahominz Collected 9-9-76 4 9-9""'. 76 Sample Weight Dry/Wet 0.0215/0.1838 kg. 0.0190/0.185 kg.

I Gamma s:eectrometrz K-40 9.0 + 5.5 E+02 Less than 7.2 E+02 Co-58 Less than 3.0 E+Ol Less than 3.0 E+Ol Co-60 8.1 + 4.8 E+Ol Less than 4.5 E+Ol Ag-llOm Less than 4.0 E+Ol Less than 4.0 E+Ol Cs-137 Less than 4.4 E+Ol Less .than 4.5 E+Ol Ce-141 Less than 1. 0 E+02 Less than 1. 0 E+02 Hg-203 Less than 4.7 E+Ol Less than 4.6 E+Ol

+/-1:-208 Less than 5.1 E+Ol Less than 5.0 E+Ol Bi-212 3.9 + 3.3 E+02 Less than 4.6 E+02 Pb-212 Less than 1.2 E+02 Less than 1. 2 E+02 Bi-214 Less than 1. 7 E+02 Less than 3.3 E+02

. Pb-214

• Less than 3.0 E+02 Less than 1. 5 E+02

• Ra-226 Less than 1.3 E+03 Less than 1. 3 E+03 I

I

• 1 I

-458-

• Date CLAM SAMPLES (picocuries per kilogram wet)

Lawnes Creek Jamestown Collected 9-9-76 9-9-76 Sample Weight Dry/Wet 0.0230/0.1606 kg. 0.0205/0.1460 kg.

Gamma Spectrometry K-40 Less than 9.0 E+02 8.9+ 7.3 E+02 Co-58 Less than 3.4 E+Ol 3.2 + 2.5 E+Ol Co-60 Less than 5.2 E+Ol Less than 5.7 E+Ol Ag-llOm Less than 4.6 E+Ol Less than 5.1 E+Ol Cs-137 4.0 + 3.1 E+Ol Less than 6.6 E+Ol Ce-141 Less than 1.1 E+02 Less than 1.3 E+02 Hg-203 4.3" + 3.6 E+Ol Less than 5.9 E+Ol Tl-208 Less than 5.8 E+Ol Less than 6.4 E+Ol Bi-212 Less than 5.3 E+02 Less than 5.8 E+02 Pb-212 Less than 1.4 E+02 Less than 1.6 E+02 Bi-214 Less .than 2.0 E+02 Less than 3.8 E+02 Pb-214 Less than 1.7 E+02 Less than 1.9 E+02 Ra-226 Less than 1.5 E+03 Less than 1.6 E+03

-459-

=-

• Date CLAM SAMPLES (picocuries per kilogram wet)

Hog Island Point Collected 9-9-76" Sample Weight Dry/Wet

• 0.0205/0.1457 kg.

Gamma Spectrometry K-40 1.5 + 0.7 E+03 Co-58 Less than 3.8 E+Ol Co-60 4.2 + 3.8 E+01 Ag-llOm Less than 5.1 E+Ol Cs-137 Less than 4. 7 E+Ol Ce-141 Less than L3 E+02 Hg-203 Less than 5.9 E+Ol Tl-208 Less than 6.4 E+Ol Bi-212 Less than 5.8 E+02

-Ph-212 Less than 1. 6 E+02 Bi-.214 Less than 2.2 E+02 Pb-214 Less than 3.5 E+02 Ra-226. Less than 1. 7 E+03

-460-

• Date CLAM SAMPLES (picocuries per kilogram wet)

Lawnes Creek Hog Island Point Collected 11-19-76 11-19-76 Sample Weight Dry/Wet 0.024/0.1791 kg. 0.0255/0.1879 kg.

Gaillllla SEectrometry K-40 9.7 + 5.7 E+02 Less than 9.0 E+02

. Co-58 4.2 + 2.7 E+Ol 3.4 + 3.3 E+Ol Co-60 Less than 6.9 E+Ol Less than 6.6 E+Ol Nb-95 Less than 6.3 E+Ol Less than 6.0 E+Ol Zr-95 Less than 7.4 E+Ol Less than 7.1 E+Ol Ag-llOm Less than 8.3 E+Ol Less than 7.9 E+.01 Cs-137 Less than 6.1 E+Ol Less than 5.9 E+Ol Ce-141 Less than 1. 0 E+02 Less than 1. 0 E+02 Tl-208 Less than 6.1 E+Ol Less than 5.8 E+Ol Bi-212 Less than 6.8 E+02 Less than 6.5 E+02 Pb-212 Less than 1. 3 E+02 Less than 1. 3 E+02 Ra-226 Less than 1. 4 E+03 Less than 1. 3 E+03

• . Date CLAM SAMPLES (picocuries per kilogram wet)

Station Discharge *chickahominey Collected 11-19-76 11-19-76

• Sample Weight Dry/Wet 0.0290/0.2767 kg. 0.013/0.194 kg.

Gamma Spectrometry K-40 3.8 + 2.8 E+02 Less than 6.8 E+02

• Co-58 8.1 + 2.8 E+Ol Less than 3.7 E+Ol Co-60

• 8. 8 + 3. 0 E+Ol Less than 6.4 E+Ol Nb-95 Less than 4.1 E+Ol. 3.9 + 3.3 E+Ol Zr-95 Less than 4.8 E+Ol 4.9 + 3.2 E+Ol Ag-llOm 4.7* + 3.6 E+Ol Less than 7.7 E+Ol Cs-137 Less than 3.1 E+Ol Less than 4.5 E+Ol Ce-141 Less than 6.8 E+Ol Less than 9.7 E+Ol Tl-208 Less than 3.9 E+Ol Less than 5.6 E+Ol Bi-212 Less than 4.4 E+02 Less than 6.3 E+02

.Pb-212 Less than 8.8 E+Ol Less than 1. 3 E+02 Ra~226. Less than 9.1 E+02 Less than 1. 3 E+03

' I

-462-

• Date CLAM SAMPLES (picocuries per kilogram wet)

Jamestown Collect.ed 11-19-76

• sample Weight Dry/Wet 0.0125/0.1655 kg.

Gamma Spectrometry K-40 Less than 6.1 E+02 Co-58 Less than 4.4 E+Ol Co-60 Less than 7.5 E+Ol Nb-95 Less than 6.3 E+Ol Zr-95 Less than 6.4 E+Ol Ag-llOm Less than 9.0 E+Ol Cs-137 Less than 4.5 E+Ol Ce-141 Less than 1.2 E+02 Tl-208 Less than 6.6 E+Ol Bi-212 Less than 7.4 E+02 Pb-212 Less than 1.4 E+02 Ra-226 Less than 1.5 E+03

-463-

• Date

~

CRAB SAMPLES (picocuries .per kilogram wet)

Intake Canal;;

'j.

Collected 7-29-76 Sample Weight Dry/Wet 0.0570/0.2918 kg Ganuna Spectrometry K...:*40 2. 7 + 0. 8 E+03 Co-58 4.5 + 2.4 E+Ol Co-60 3.2 + 2.1 E+Ol cs-137 Les.s than 4.3 E+Ol Bi-212 3.3 + 2.6 E+02 Bi-214 Less than 1. 5 E+02 Pb-214 Less than 1. 9 E+02

~~-226 Less than 1.8 E+03

-464-

• Date CRAB SAMPLES (picocuries per kilogram wet)

Station Intake Collected 8-9-76 Sample Weight Dry/Wet 0.0485/0.3360 kg Gannna Spectrometry K-40 1. 8 + 0. 7 E+03 Co-58 1. 0 + 0. 4 E+O 2 Co-60 3.9 + 3.3 E+Ol Cs-134 Less than 4.5 E+Ol Cs-137 Less than 4.4 E+Ol Pb-212 Less than 1. 4 E+02 Pb-214 Less than 1. 7 E+02

..:465-

• Date CRAB SAMPLES (picocuries per kilogram wet)

Intake (Lower Level)

.Collected September, 1976 Sample *weight Dry/Wet 0.0540/0.5345 kg.

'Gannna Spectrometry K-40 1.1 + 0.5 E+03 Cs-137 Less than 2.4 E+Ol Pb-214 Less than 9.1 E+Ol Ac-228 Less than 2.0 E+02

-466-

VEPCo FISH SAMPLES (picocuries per kilogram wet)

Bottom Feeder Free Swinnner Date Collected 3-1-76 3-1-76 Sample Weight Dry/Wet .0075/.0194kg .014/.054kg Gamina Spectrometry K-40 Less than 3.4 E+03 1. 6 + 1. 2 E+03 Cr-51 Less than 2.6 E+03 Less than 1.4 E+03

• Mn-54 2.0 + 1.1 E+02 Less than 8.8 E+Ol Cs-137 Less than 2.4 E+02 7.8 + 5.7 E+Ol

.Pb-212 Less than 8.4 E+02 Less than 5.2 E+02 Pb-214 Less than 1. 0 E+03 Less than 5.3 E+02 Ra-226 Less than 8.8 E+03 Less than 4.7 E+03

• ,I

-467-

• Date Collected Colonial Pkwy.

SOIL SAMPLES (picocuries per kilogram dry)

Dow 8-24~76 8-24-76 Sample*Weight Dry 0.132 kg. 0.116 kg.

Radiochemistry Sr-89 0.0 + 5.8 E+Ol 0.0 + 9.4 E+Ol

• sr-90 1.1 + 0.4 E+02 2. 0 + 0. 7 E+O 2 Gamma Spectrometry K-40 3.0 + 1.5 E+03 1. 4 + 0 . 2 E+04 Co-58 Less than 9.2 E+Ol 1. 2 + 0

• 7 E+02

• Co-60 . Less than 1. 5 E+02 Less than 1.7 E+02 Cs-137 1. 5 . + 0 . 2 E+O 3 1. 9 + 1. 3 E+02 Ce-141 Less than 3.6 E+02 Less than 4.1 E+02 Hg-203

• Less than 2.1 E+02 Less than 2.4 E+02 T1-*2oa

• Less than 1. 7 E+02 4. 5 + 1. 6 E+O 2 Bi-212 .Less than 1. 8 E+03 2. 1 + 1. 4 E+03 Pb-212 3.3 + 2.6 E+02 1. 5 + 0. 4 E+03 Bi-214 3.6 + 2.6 E+02 1. 2 + 0 . 4 E+O 3 Pb-214 6.5 + 2.9 E+02 1. 7 + 0. 4* E+03 Ra-226 Less than 4.3 E+03 4. 9 + 3

• 5 E+O 3 Ac-228 Less than 8.2 E+02 1. 2 +/- 0. 7 E+03

-468-

• Date Alliance SOIL SAMPLES (picocuries per kilogram dry)

Hog Island Point Collected 8-24-76 8-24-76

. S'ample Weight Dry 0.154 kg. 0.130 kg.

• Radiochemistry Sr-89 0.0 + 8.7 E+Ol 0.0 + 4.4 E+Ol Sr-90 9.3 + 6.9 E+Ol 1. 1 + 0. 3 E+02

. Gamma Spectrometry K-40 1. 5 + 1. 1 E+OJ 1. 5 + 0 . 3 E+04 Co-58 Less thari 7.9 E+Oi Less than 9.4 E+Ol Co-60 Less than 1. 3 E+02 Less than 1. 5 E+02

.Cs-137 2.8.+ 0.9 E+02 1. 8 + 1. 0 E+O 2 Ce-141 Less than 3.1 E+02 Less than 3.7 E+02 Hg-203 Less than 1. 8 E+02 Less than 2.1 E+02 Tl-208 Less than 1. 5 E+02 3. 2 + 1. 6 E+02 Bi-212 Less than 1. 6 E+OJ Less than 1.9 E+OJ

.* Pb-212 - 2.4 E+02 2.6.. + 1. 5 + 0.4 E+03

Bi-214 3 . 9 + 2. 3 E+02 1. 2 + 0. 3 E+03

_*Pb-214 4. 7 + 2. 7 E+02 1. 3 + 0. 4 E+O 3 Ra-226 Less than 3.7 E+03 4. 5 + 3

• 3 E+03 Ac-228 Less than 7.0 E+02 1.2 + 0.6 E+03 I

-469-

• Date SOIL SAMPLES (p.icocuries per kilogram dry)

Bacon's Castle Surry Station Collected 8-24-76 8-24-76 Sample Weight.

Dry 0.094 kg. 0.121 kg.

Radiochemistry Sr-89 0.0 + 5.0 E+Ol 7. 3 + 4. 8 E+O 1 Sr-90 1.5 + 0.5 E+02 0.0 + 7.2 E+Ol Gannna Spectrometry K-40 9.2 + 2.5 E+03 1. 4 + 0. 3 E+04 Co-58 Less than 1. 3 E+02 Less than 1. 0 E+02 Co-60 Less than 2*.1 E+02 Less than 1. 6 E+02 Cs-137 2.4*-+ 0.3 E+03 9.5 + 9.3 E+Ol Ce-141 Less than 5.1 E+02 Less than 3.9 E+02 Hg-203 Less than 3.0 E+02 Less than 2.3 E+02 Tl-208 Less than 2.6 E+02 4. 4 + 1. 6 E+O 2 Bi-212 Less than 2.6 E+03 Less than 2.0 E+03

'Pb-212 7.4 + 4.1 E+02 1. 5 + 0 . 4 E+O 3 Bi-214 4.9 + 3.3 E+02 8.8 + 6.1 E+02 Pb-214 8.3 + 4.6 E+02 1. 2 + 0 . 4 E+O 3 Ra-226 4.7 + 4.2 E+03 Less than 5.5 E+03 Ac-228 1. 4 + 0. 7 E+OJ 1.4 + 0. 7 E+OJ

-470--

• * :Date .

• Qollected .

SOIL SAMPLES (picocuries per kilogram dry)

Newport News 8-24-76 Fort Eustis 8-24-76

$ample Weight Dry 0.166 kg. 0.107 kg.

Radiochemistry

. Sr-89 0.0 + 9.4 E+Ol 0.0 + 8.3 E+Ol

.*. Sr-90 7.2 + 0.6 E+02 2.6 + 0.5 E+02 Gamma Spectrometry

. ~-40 2.7 +/- 0.3 E+04 1.0 + 0.3 E+04

. c;:o-58 Less than 7.3 E+Ol Less than 1.1 E+02 Co-60 Less than 1. 2 E+02 Less than 1. 8 E+02

.Cs-137 2.0. +/- 1.2 E+02 1. 8 + 0 . 2 E+O 3

.ce-141 Less than 2.9 E+02 Less than 4.4 E+02

.Hg-203 Less than 1. 7 E+02 Less than 2.6 E+02 Tl-208 4. 6 + 1. 4 E+02 1. 9 + 1. 6 E+02

. Bi-212 Less than 1.5 E+03 Less than 2. 3 E+03

..* ~

Pb-212 1.3 + 0.4 E+02 8.0 + 3.9 E+02 Bi-214 2.8 + 0.5 E+03 4. 7 + 3. 1 E+O 2

pb.

.214 6.5 + 0.5 E+03 8.6 + 4.1 E+02

. Ra:..226 1.5 + 0.4 E+04 3.9 + 3.8 E+03

• (

• flc-228 2.0 +/- 0.7 E+03 Less than 1.0 E+03

-471-

\,,

r

• Date FOOD CROP SAMPLES (picocuries per kilogram wet)

Corn (Brock Farm)

\

\

\

)

Collected 10-11-76

(

Sample Weight Dry/Wet 0.0980/0.1116 kg Radiochemistry Sr-89 4.8 + 2.6 E+Ol Sr-90 0.0 + 3.2 E+Ol Gamma Spectrometry

.K-40 3. 2 + 1. 2 E+03 Cs-137 Less than 7.7 E+Ol Pb-212 Less than 3.1 E+02

-472-

• Date FOOD CROP SAMPLES (picocuries per kilogram wet)

Corn (Brock Farm)

Collected 10-12-76 Sample Weight Dry/Wet 0.092/0.104 kg Radiochemistry Sr-89 0.0 + 2.7 E+Ol Sr-90 0.0 + 2.2 E+Ol Ganuna Spectrometry K-40 2.5 + L 3 E+03 Sb-125 Less than 3.7 E+02 Cs-137 Less than 8.7 E+Ol Ba-140 Lesf? than 2.1 E+02 La-140 Less than 1. 6 E+02 Tl-208 Less than 9.9 E+Ol Pb-212 Less than 3.3 E+02 Bi-214 Less than 6.4 E+02

'Ra-226 Less than 3.6 E+03

-473-

• Date Collected FOOD CROP SAMPLES (picocuries per kilogram wet)

Peanuts (Brock Farm) 10-14-76 Sample Weight Dry/Wet 0.106/0.122 kg Radiochemistry Sr-89 0 . 0 + 1. 7 E+O 1 Sr-90 0. 0 + i. 4 E+Ol Gamma Spectrometry

. K-40 5. 8 + L 3 E+03

, ts-137 Less than 7.0 E+Oi

.Pb~212 Less than 2.8 E+02

'Bi-214 Les~ than 2.0 E+02 Ra-226 Less than 3.2 E+03

-474-

• Date Collected Soybeans 12-1-76 FOOD CROP SAMPLES (picocuries per kilogram wet)

Sample Weight Dry/Wet 0.088/.10075 kg.

Radiochemistry Sr-89 0.0 + 2.1 E+Ol Sr-90 1.4 + 1. 2 E+Ol Ga1llllla Spectrometry K-40 1. 4 + 0. 2 E+04

-cs-137 6.9 + 5.9 E+Ol Tl-208 Less than 1.1 E+02 Pb-212 Les~ than 3.6 E+02 Ra-226 Less than 3.8 E+03

-475-

VEPCo FOWL (GOOSE) SAMPLES (picocuries per kilogram wet)

Hog Island Point Date Collected 6-3-76 Sample Weight Dry/Wet 0.1574 kg Radiochemistry Sr-89 0.0 + 1.4 E+02 Sr-90 0. 0 + 1. 2 E+02 Gamma Spectrometry K-40 3 . 2 + 1. 1 E+03 Co-60 Less than 5.0 E+Ol Cs-137 Less than 7.8 E+Ol Pb-212 Less than 3.2 E+02 Bi-214 Less.than 2.7 E+02 Pb-214 Less than 3.3 E+02 Ac-228 Less than 7.0 E+02

~*

• -476-

• Date FOWL SAMPLES (picocuries per kilogram wet)

Hog Island (Blue Heron)

Collected 12-1-76 Sample Weight Dry/Wet o~o5S/o.1262 kg ..

Gannna. Spectrometry K-40 1. 9 + 1. 5 E+03

• Nb-95 Less than 1.1 E+02 Zr-95 7.5 + 7.4 E+Ol

.Cs-137 .

+ 4.5 E+Ol 6.4 *-

Ra-226 Less tha~ 4.3 E+03

. '.i

• 1

-477;_