ML18153A086

Monthly Operating Repts for Sept 1996 for Surry Power Station Units 1 & 2

ML18153A086
Person / Time
Site:	Surry
Issue date:	09/30/1996
From:	Fanguy M, Kilmer J, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-530, NUDOCS 9610280121
Download: ML18153A086 (21)

Text

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J VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 14, 1996 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.96-530 NURPC Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1996.

If you have any questions or require additional information, please contact us.

Very truly yours, R. F. Saunders Vice President - Nuclear Operations Enclosure cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

(-

9610280121"'. 960930 ---

PDR ADOCK 05000280 R

PDR

e VIRGINIA ELECTRIC AND POWER COMPANY.

SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-09 Approved:

~

Jj CCI--, /L l/~eit, Station Manager Date

TABLE OF CONTENTS Section

-Surry Monthly Operating Report No. 96-09 Page 2 of 20 Page Operating Data Report - Unit No. 1........................................................................................................................ :... 3 Operating Data Report - Unit No. 2............................................................................................................................ 4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................................. 5 Unit Shutdowns and Power Reductions - Unit No. 2.................................................................................................. 6 Average Daily Unit Power Level - Unit No. 1............................................................................................................. 7 Average Daily Unit Power Level - Unit No. 2............................................................................................................. 8 Summary of Operating Experience - Unit No. 1......................................................................................................... 9 Summary of Operating Experience - Unit No. 2....................................................................................................... 1 O Facility Changes That Did Not Require NRG Approval............................................................................................ 11 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 16 Tests and Experiments That Did Not Require NRG Approval.................................................................................. 17 Chemistry Report..................................................................................................................................................... 18 Fuel Handling - Unit No. 1........................................................................................................................................ 19 Fuel Handling - Unit No. 2........................................................................................................................................ 19 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 20

OPERATING DATA REPORT

-Surry Monthly Operating Report No. 96-09 Page 3 of 20 Docket No.:

Date:

50-280 10-02-96 Completed By:

D. K. Mason (804) 365-2459

1.

Unit Name:...........................................................

2.

Reporting Period:.................................................

3.

Licensed Thermal Power (MWt):..........................

4.

Nameplate Rating (Gross MWe):.........................

5.

Design Electrical Rating (Net MWe):....................

6.

Maximum Dependable Capacity (Gross MWe):...

7.

Maximum Dependable Capacity (Net MWe):.......

Surry Unit 1 September, 1996 2546 847.5 788 840 801 Telephone:

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe): -------------------

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11.

Hours In Reporting Period...............................

720.0 6575.0 208415.0

12.

Number of Hours Reactor Was Critical...........

720.0 6575.0 144625.7

13.

Reactor Reserve Shutdown Hours..................

0.0 0.0 3774.5

14.

Hours Generator On-Line................................

720.0 6575.0 142322.0

15.

Unit Reserve Shutdown Hours..................-......

0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH)......

1818209.7 16628141.0 333025933.5

17. Gross Electrical Energy Generated (MWH).....

600125.0 5518750.0 109095933.0

18. Net Electrical Energy Generated (MWH).........

578460.0 5326769.0 103782742.0

19.

Unit Service Factor..........................................

100.0%

100.0%

68.3%

20.

Unit Availability Factor.....................................

100.0%

100.0%

70.1%

21.

Unit Capacity Factor (Using MDC Net)............

100.3%

101.1%

64.1%

22.

Unit Capacity Factor (Using DER Net)............

102.0%

102.8%

63.2%

23.

Unit Forced Outage Rate................................

0.0%

0.0%

15.4%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Unit 1 Refueling Outage is scheduled to start February 20, 1997

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

N/A

26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

OPERATING DATA REPORT

~urry Monthly Operating Report No. 96-09 Page 4 of 20 Docket No.:

Date:

50-281 10-2-96 Completed By:

D. K. Mason

{804) 365-2459

1.

Unit Name:...........................................................

2.

Reporting Period:.................................................

3.

Licensed Thermal Power (MWt):..........................

4.

Nameplate Rating (Gross MWe):.........................

5.

Design Electrical Rating (Net MWe):....................

6.

Maximum Dependable Capacity (Gross MWe):...

7.

Maximum Dependable Capacity (Net MWe):.......

Surry Unit 2 September, 1996 2546 847.5 788 840 801 Telephone:

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

1 O.

Reasons For Restrictions, If Any:

This Month

11. Hours In Reporting Period...............................

720.0

12. Number of Hours Reactor Was Critical...........

720.0

13.

Reactor Reserve Shutdown Hours..................

0.0

14.

Hours Generator On-Line................................

720.0

15. Unit Reserve Shutdown Hours........................

0.0

16.

Gross Thermal Energy Generated (MWH)......

1799879.5

17.

Gross Electrical Energy Generated (MWH).....

593975.0

18. Net Electrical Energy Generated (MWH).........

573039.0

19.

Unit Service Factor..........................................

100.0%

20.

Unit Availability Factor.....................................

100.0%

21.

Unit Capacity Factor (Using MDC Net)............

99.4%

22.

Unit Capacity Factor (Using DER Net)............

101.0%

23.

Unit Forced Outage Rate................................

0.0%

YTD 6575.0 5605.2 0.0 5583.1 0.0 14003364.1 4637870.0 4481475.0 84.9%

84.9%

85.1%

86.5%

2.3%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

26. Unit In Test Status (Prior to Commercial Operation):

Cumulative 205295.0 141108.1 328.1 139139.2 0.0 326538418. 1 106793514.0 101591890.0 67.8%

67.8%

63.4%

62.8%

12.6%

N/A FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%}

REPORT MONTH: September, 1996

~urry Monthly Operating Report No. 96-09 Page 5 of 20 Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

10-03-96 Completed by:

M.J. Fanguy (1)

Date Type 9114196 s

(1)

F:

Forced S:

Scheduled (2)

(3)

Method Duration of LER Hours NIA Reason B

(2)

REASON:

Shutting No.

Down Rx NIA NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction (4)

System Code EL Teleehone:

(804} 365-2155 (5)

Component Cause & Corrective Action to Code Fan Prevent Recurrence Replaced Belt (3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(5)

Exhibit 1 - Same Source

(1)

Date Type 9/01/96 s

9/06/96 F

(1)

F:

Forced S:

Scheduled (4) e (2)

~urry Monthly Operating Report No. 96-09 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1996 (3)

Method (4)

Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

10-3-96 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (5)

Duration Hours of LER No.

Reason Shutting System Code Component Cause & Corrective Action to Code Prevent Recurrence N/A N/A B

A (2)

REASON:

Down Rx N/A N/A N/A N/A A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction AB NN CLR SCN TM S2-96-26 installed to remove inspection covers of 2-RC-P-1 C.

Decrease Rx power due to degradation of Unit 2 CW pumps and screens from hurricane Fran.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)

Exhibit 1 - Same Source

e urry Monthly Operating Report No. 96-09 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL MONTH:

September, 1996 Average Daily Power Level Day (MWe - Net) 1 805 2

804 3

802 4

784 5

804 6

806 7

803 8

803 9

801 10 802 11 807 12 807 13 807 14 663 15 768 16 815 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.:

50-280 Unit Name: Surry Unit 1 Date:

10-03-96 Completed by: J. D. Kilmer Telephone:

(804) 365-2792 Average Daily Power Level (MWe - Net) 815 816 817 816 812 814 817 818 816 814 812 818 818 818 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

~urry Monthly Operating Report No. 96-09 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL MONTH:

September, 1996 Average Daily Power Level Day (MWe - Net) 1 730 2

810 3

809 4

810 5

795 6

644 7

747 8

730 9

749 10 810 11 807 12 807 13 805 14 816 15 816 16 814 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25

,26 27 28 29 30 Docket No.: 50-281 Unit Name:

Surry Unit 2 Date:

10-03-96 Completed by: J. D. Kilmer Telephone:

(804) 365-2792 Average Daily Power Level (MWe - Net) 765 818 818 818 818 819 804 816 817 819 820 810 813 823 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September, 1996

.Surry Monthly Operating Report No. 96-09 Page 9 of 20 The following chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE:

9/01/96 9/04/96 9/14/96 9/15/96 9/30/96 0000 1020 1354 The reporting period began with the unit operating at 100% power, 835 MWe Start power reduction to maintain condenser vacuum while removing 1-CW-E-1A from service for cleaning Stop power reduction at 90%, 735 MWe 1455 Start power increase 1726 Stop power increase at 100%, 831 MWe 0500 0744 Start power reduction to remove 'A' isophase bus duct for belt replacement and 1-CW-E-1 A from service for cleaning Stop power reduction at 65%, 544 MWe 1515 Start power increase after 'A' isophase bus duct returned to service 1653 Stop power increase at 86%, 710 MWe 1940 Start power increase after 1-CW-E-1 C return to service 2104 Stop power increase at 100%, 825 MWe 2240 Start power reduction to maintain condenser vacuum while removing 1-CW-E-1 B from service for cleaning 2325 Stop power reduction at 95.5%, 772 MWe 1712 1835 2400 Start power increase after 1-CW-E-1 B was returned to service Stop power increase at 100%, 848 MWe The reporting period ended with the unit operating at 100% power, 850 MWe

UNITTWO:

9/01/96 9/06/96 9/08/96 9/08/96 9/09/96 9/11/96 9/13/96 9/17/96 9/30/96 0000 e

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: September, 1996

.Surry Monthly Operating Report No. 96-09 Page 10 of 20 The reporting period began with the unit operating at 100% power, 845 MWe 0852 Start power reduction to remove the inspection covers per Temporary Modification 82 26 to improve cooling of 2-RC-P-1 C motor 1129 Stop power reduction at 67%, 572 MWe 1627 Start power increase after 2-RC-P-1C TM was completed 1930 Stop power increase at 100%, 845 MWe 0501 0939 Start power reduction due to degradation of CW pumps and screens Stop power reduction at 49.6%, 400 MWe 1247 Start power increase 1819 Stop power increase at 94.5%, 780 MWe to maintain 'A' condenser vacuum 1430 1542 1420 1531 0645 1954 2014 0426 Start power reduction to maintain condenser vacuum while removing 1-CW-E-1 A from service for cleaning Stop power reduction at 89.5%, 735MWe Start power increase Stop power increase at 100%, 835 MWe Reduced power to 99.5% to ensure Calorimetric calculations remained conservative with normal letdown out of service Start power increase after normal letdown was returned to service Stop power increase at 100%, 840 MWe Start power reduction to maintain condenser vacuum while removing 2-CW-E-1 C from service for cleaning 0454 Stop power reduction at 93%, 755 MWe 2025 Start power increase after 2-CW-E-1 C was returned to service 2133 2400 Stop power increase at 100%, 849 MWe The reporting period ended with the unit operating at 100% power, 857 MWe

Appendix R Report FS 96-29 DCP 95-011 e

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1996 Technical Report (Safety Evaluation No.96-115)

.Surry Monthly Operating Report No. 96-09 Page 11 of 20 9-5-96 The tracking of combustible loading for areas of the station is being eliminated for fire areas that do not have explicit statements concerning combustible loading discussed in NRG Safety Evaluation Reports (SERs). The current combustible loading will be retained in the Appendix R Report as a reference for these fire areas but will not be updated.

Significant changes, such as new types of combustibles will be maintained in general by the fire hazards analysis which is maintained in the Evaluation of Specific Plant Areas section of the UFSAR (9.10.4).

This change will not affect the ability to safely shutdown in the event of a fire. All barriers required by Appendix R are three hour rated or evaluated and will remain in place. There will be no change to the fire protection systems or the fire brigade. Transient controls on combustibles remain in place. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation 96-114) 9-5-96 This change updates the fire protection portions of the UFSAR to correct inconsistencies and out dated material. This change does not adversely affect the ability of the plant to safely shutdown in the event of a fire. All fire protection equipment currently in service will remain in service.

This change does not affect the margins of safety, since all fire protection systems will remain in place. The Operating License and the Technical Specifications will not be affected because the design descriptions that are being revised for clarity are not in the Operating License or the Technical Specifications.

Therefore, an unreviewed safety question does not exist.

Design Change Package (Safety Evaluation 95-174) 9-09-96 Design Change Package (DCP)95-011 replaced the existing 3,000 horsepower Main Feedwater Pump motors with new 3,500 horsepower motors. There is no impact on the margin of safety as the motors themselves are not directly responsible for any safety related function and the motor size is not mentioned in the Technical Specifications. No new failure modes exist, since this is a replacement of existing equipment with equal or better than existing equipment. Therefore there are no unreviewed safety questions.

TM 82-96-17 TM 82-96-24 TM 82-96-19 FS 95-18 VPAP-0809 e

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1996 Temporary Modification (Safety Evaluation No.94-088 Rev. 1)

~urry Monthly Operating Report No. 96-09 Page 12 of 20 9-16-96 These TMs connect a chart recorder to allow for the continuous monitoring of the Unit 2 Pressurizer Safety Valve acoustic monitor.

This will allow for more precise and continuous monitoring.

The pressurizer utilizes redundant indications of safety valve position.

The primary

• indication is an acoustic monitoring channel and the backup is a downstream high temperature channel. This activity will provide for continuous monitoring of the primary indication through the use of a strip chart recorder. The installed acoustic monitoring and alarm indication will be unaffected by this TM. Therefore there are no unreviewed safety questions.

Temporary Modification 9-16-96 (Safety Evaluation No.96-095 Rev 1)

This temporary modification routes the Unit 2 Pressurizer Relief Tank vapor space through the sample line to the Gas Purge Line in the Sample Sink to provide a continuous vent.

The Gas Purge Line is already connected to the Primary Drains Tank.

The continuous vent will then be processed through the Overhead Gas System to the Waste Gas Decay Tanks (WGDT).

Overall radioactive gas releases will be lower from this processing method because the radioactive gaseous waste will now decay in the WGDT instead of being routinely released. This process involves an improvement in the processing of gaseous waste and properly utilizes the existing system for processing gas. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change Administrative Procedure (Safety Evaluation 96-066 Rev. 1) 9-19-96 Updated Final Safety Analysis Report Change 95-18 revised Section 98.3, "Control of Heavy Loads," to summarize Virginia Power's commitments related to NUREG-0612.

Administrative procedure VPAP-0809, "NUREG-0612 Heavy Load Program," was also revised to be consistent with the UFSAR.

The subject changes reflect Virginia Power's commitment to comply with the guidelines of NUREG-0612 which provides overall defense-in-depth at preventing load handling accidents. Therefore, an unreviewed safety question does not exist.

SE 96-121 TM 82-96-017 TM 82-96-24 TM 82-96-27 TM 82-96-27 e

FACILITY CHANGES THAT DIDNOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1996 Safety Evaluation (Safety Evaluation No. 96-121}

~urry Monthly Operating Report No. 96-09 Page 13 of 20 9-23-96 This safety evaluation was prepared to confirm that the heavy load drops evaluated in the UFSAR bound all of the potential heavy load drops associated with the handling of any of the casks used or planned for use to store spent fuel at Surry.

The probability of occurrence of a heavy load drop during spent fuel cask handling does not depend on the specific cask design used because the handling equipment and methods for handling casks and cask lids remains as described in the UFSAR and ISFSI SAR. Since the consequences of dropping a cask lid or one of the five cask designs is bounded by the cask drop evaluation documented in appendix 98.1 of the UFSAR, the margin of safety will not be decreased. Therefore, an unreviewed safety question does not exist.

Temporary Modifications 9-24-96 (Safety Evaluation No.96-088 Rev 2)

These Temporary Modifications installed a strip chart recorder to provide more precise and continuous monitoring of the Unit 2 Pressurizer Safety Valve acoustic monitors.

The TM does not affect the acoustic monitoring system and alarm indication. The TM does not impact any automatic protection or control functions. Therefore, an unreviewed safety question does not exist.

Temporary Modification 9-24-96 (Safety Evaluation No.96-095 Rev 2)

Temporary modification 82-96-19 routes the Unit 2 Pressurizer Relief Tank vapor space through the sample line and to the Gas Purge Line in the Sample Sink. The Gas Purge Line is already connected to the Primary Drains Tank. The continuous vent will then be processed through the Overhead Gas System to the Waste Gas Decay Tanks (WGDT).

Temporary modification 82-96-27 requires a seismic interaction walkdown be performed by Engineering.

Overall radioactive gas releases will be lower from this processing method because the radioactive gaseous waste will now be decayed in the WGDT instead of being routinely released. This process involves an improvement in the processing of gaseous waste and properly utilizes the existing system for processing gas. Therefore, an unreviewed safety question does not exist.

_J

DR S-96-1445 SE 96-124 TM S1-96-017 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: September, 1996 Deviation Report (Safety Evaluation No.96-123)

~urry Monthly Operating Report No. 96-09 Page 14 of 20 9-26-96 The 'A' Main Control Room (MCR) Chiller is currently only capable of being powered via its alternate power supply (2J) and therefore only two MCR Chillers are capable of being powered by two emergency buses. UFSAR Section 9.13.3.6 indicates that three MCR Chillers have this capability. However, this condition does not affect the operability of the MCR Chiller System but only limits the flexibility of equipment alignment.

This condition does not increase the consequences of any accident described in the Safety Analysis or create another type of accident.

The 'A' MCR Chiller remains operable, capable of providing its intended function, on its alternate power supply.

Compliance with TS 3.23 is also maintained with this condition. The inoperability of the

'A' MCR Chiller normal power supply is not an unanalyzed condition.

Therefore, an unreviewed safety question does not exist.

Safety Evaluation 9-26-96 (Safety Evaluation No.96-124)

This Safety Evaluation evaluates the 'A' Waste Gas Diaphragm Compressor being out of service for greater than 30 days. The purpose of the compressor is to transfer waste gas from the surge drum to either of the waste gas decay tanks. The redundant 'B' Waste Gas Diaphragm Compressor remains available maintaining the operability of the gaseous waste system.

The unavailability of the 'A' Waste Gas Diaphragm Compressor does not cause or increase the consequences of any accident in the Safety Analysis Report.

The compressors are not assumed operable in any analyzed accident. The 'B' Waste Gas Diaphragm Compressor remains operable and capable of providing the intended function of the compressor to transfer waste gas from the surge drum to the waste gas decay tanks. Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.96-125) 9-26-96 This Temporary Modification is used to replace test switch 1-SI-CS-FC-494-TA in the Unit 1 train 'A' of the Safety Injection (SI) system. All work performed will be in the train 'A' portion of the SI system only, train 'B" will remain unaffected and will function as designed at all times. With the jumper installed, train 'A' of the SI system will provide all of it's manual and automatic functions.

The test switch replacement is a like for like replacement with no change to the design of the system or any station isolation. There is no change to the station design. During the time of switch replacement both trains of SI will function as designed.

Therefore, an unreviewed safety question does not exist.

FS 96-37 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1996 Updated Final Safety Analysis Report Change (Safety Evaluation 96-126)

~urry Monthly Operating Report No. 96-09 Page 15 of 20 9-26-96 This UFSAR change revises chapter 17 of the UFSAR to reflect the current organization, including a reference section, clarify what procedures govern non-conformance's found at a vendor's facility and include editorial changes.

These changes are administrative in nature and do not reduce the effectiveness of the QA Program or reduce the commitments in the NRC approved QA Program. There are no changes to any component, system or structure in the plant, or to any method of operations as a result of these changes. Therefore, an unreviewed safety question does not exist.

TMOP-3039 2-0P-CH-007 e

e,,urry Monthly Operating Report No. 96-09 Page 16 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1996 Temporary Maintenance Operating Procedure (Safety Evaluation No.96-120) 9-19-96 Temporary Maintenance Operating Procedure O-TMOP-3039, "Unblocking Ventilation Vent RM Nozzle," was developed to provide instructions for installing a purge supply to the down stream side of the ventilation vent isokinetic nozzle at the input of the ventilation vent radiation monitor, 1-RM-VG-109/110. This modification will enable the ventilation vent multi-ported isokinetic nozzle to be flushed with instrument air to remove a clog that prevents the radiation monitors from drawing a sample from the ventilation vent.

This modification was removed immediately following the purging operation and did not negatively impact any plant equipment or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

Operating Procedures (Safety Evaluation No.96-122) 9-24-96 The Primary Grade (PG) water flow path to the blender is inoperable.

An alternate method of boration and dilution make-up to the VCT is required to support continued operation until the PG flowpath is repaired. The alternate method will align local manual valves to bypass the blender while maintaining flow indication on the Control Room Strip Chart and Flow Integrators.

Administrative control of the flowpaths will be maintained when they are in use. Use of these alternate flowpaths is procedurally controlled.

Administrative controls are established to prevent inadvertent dilution. Therefore, an unreviewed safety question does not exist.

Special Test 2-ST-0318 e,,urry Monthly Operating Report No. 96-09 Page 17 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: September, 1996 Final test results were received from Combustion Engineering on 8/26/96 and presented to SNSOC on 9/9/96 for Steam Generator moisture carryover testing performed on 4/16/96. The test was performed using a non-radioactive tracer and the results indicated a 100% power level value of 0.223%, which is within the design value of 0.25%.

e Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hydrogen, cc/kg Lithium, ppm Boron - 10, ppm*

Oxygen, (DO), ppm Chloride, ppm pH at 25 degree Celsius Boron - 10 = Total Boron x 0.196 Comments:

None CHEMISTRY REPORT MONTH/YEAR: September, 1996 Unit No. 1 Max.

Min.

AvQ.

7.73E-1 4.82E-1 6.76E-1

~0.010

~0.010

~0.010 5.53E-1 4.54E-1 4.95E-1 1.311E-2 5.17E-3 7.81 E-3 0.65 0.42 0.50 38.7 37.1 37.8 2.33 2.05 2.19 101.5 84.9 94.2

~0.005

~0.005

~0.005 0.004 0.002 0.003 6.95 6.61 6.85

~urry Monthly Operating Report No. 96-09 Page 18 of 20 Unit No. 2 Max.

Min.

AvQ.

2.23E-1 8.60E-2 1.32E-1

~0.010

~0.010

~0.010 5.41E-1 4.35E-1 4.77E-1 2.15E-4 2.64E-5 5.55E-5 0.12 0.06 0.09 35.2 18.6 27.7 2.38 2.10 2.24 248.1 229.1 237.6

~0.005

~0.005

~0.005 0.006 0.004 0.005 6.34 6.08 6.21

New or Spent Fuel Shipment Date Stored or Number Received e

FUEL HANDLING UNITS 1 &2 MONTH/YEAR: September, 1996 Number of Assemblies per Shipment Assembly Number ANSI Number

~urry Monthly Operating Report No. 96-09 Page 19 of 20 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period

e

~urry Monthly Operating Report No. 96-09 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: September, 1996 None During the Reporting Period