ML043560499

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Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupation Radiation Exposure Reports
ML043560499
Person / Time
Site: Millstone, Surry, North Anna  
Issue date: 12/21/2004
From: Matthews W
Dominion Nuclear Connecticut, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, NRC/FSME
References
04-738
Download: ML043560499 (25)
v • d • e


Text

Surry Units 1 and 2

TS 6.6-2 w

resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operations),

supplementary reports shall be submitted at least every 3 months until all three events have been completed.

1

2. Annual Reports eir associated exposure accor aintenance (des ain tenance), was east 80% of th Note: Footnotes 1 and 2 are located on page TS 6.6-1 1.

w Amendment Nos.

TS 6.6

b. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.1.D.4. In addition, the information itemized in Specification 3.1.D.4 shall be included in this report.

c s and shutdown e ter than the 15t

-\\

Amendment Nos.

Serial No.04-738 Millstone Power Station Units 1, 2 and 3 North Anna Power Station Units 1 and 2 Surry Power Station Units 1 and 2 Proposed Technical Specification Changes For Removal of Monthly Operating Report and Occupational Radiation Exposure Report Revised Pages Virginia Electric and Power Company (Dominion)

Dominion Nuclear Connecticut, Inc. (DNC)

Millstone Unit 1

Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements The following reports shall be submitted in accordance with 1 OCFR50.4.

5.7.1 Deleted Millstone - Unit 1 5.0-1 5 (continued)

Amendment No. %, 112,

Millstone Unit 2

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS....................................................................................................

6-16 STARTUP REPORTS...................................................................................................

6-16 A"JAL REPORTS..................................................................................................... 6.17 ANNUAL RADIOLOGICAL REPORT........................................................................ 6-18 CORE OPERATING LIMITS REPORT 6-18 6.9.2 SPECIAL REPORTS....................................................................................................

6-19 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM.....................................................................

6-20 6.12 HIGH RADIATION AREA.............................................................................................

6-20 6.1 3 SYSTEMS INTEGRITY.................................................................................................. 6.23 6.14 IODINE MONITORPNG.................................................................................................. 6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM).................................................................

6.24 6.16 RADIOACTIVE WASTE TREATMENT........................................................................

6-24 6.17 SECONDARY WATER CHEMISTRY.............................................................................

6-25 U D E L E T E D 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM.......................................

6-26 6.20 RADIOACTIVE EFFULENT CONTROLS PROGRAM...............................................

6.26 6.2 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.........................

6-28 6.22 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM....................

6-28 6.23 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM.......................

6-28 6.24 DIESEL FUEL OIL TEST PROGRAM........................................................................

6-29 I

MILLSTONE.

UNIT 2 XVII Amendment No. 39. 34.63. 6.443.

+84. =. w. *. =.

+@. w. =Q.

=. =.

=Q.

274. =.

ADMINISTRATIVE CONTROLS ANNUAL REPORTS' 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4 6.9.1.5a.DELETED 6.9.1.5b The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.1.5.b). The report covering the previous calendar year shall be submitted prior to March 1 of each year.

6.9.1.5~. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1)

Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3)

Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-13 1 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit. The report covering the previous calendar year shall be submitted prior to March 1 of each year.

1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

MILLSTONE - UNIT 2 6-17 Amendment No. 34,444, 444, 4-63,

? 3 8 7 236,

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL REPORTS 6.9.1.6a ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

- _ - - - - - _ - - - - - _ - NOTE - - - - - - _ _ _ - - - - - _ -

A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and 1V.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the REMODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in the next annual report.

6.9.1.6b RADIOACTIVE EFFLUENT RELEASE REPORT

- - - - - - - - - - - - - _ - NOTE - - - - - _ - - - - - - - - - -

A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the REMODCM and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.1.

I 6.9.1.7 Deleted MILLSTONE - UNIT 2 6-18

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.8 a.

Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.

314.1.1.1 SHUTDOWN MARGIN (SDM) 314.1.1.4 Moderator Temperature Coefficient 314.1.3.6 Regulating CEA Insertion Limits 314.2.1 Linear Heat Rate 314.2.3 314.2.6 DNB Margin Total Integrated Radial Peaking Factor - FT,

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

EMF-96-029(P)(A) Volumes 1 and 2, Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 -Benchmarking Results, Siemens Power Corporation.

ANF-84-73 Appendix B (P)(A), Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events, Advanced Nuclear Fuels.

XN-NF-82-2 1 (P)(A), Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations, Exxon Nuclear Company.

XN-75-32(P)(A) Supplements 1 through 4, Computational Procedure for Evaluating Fuel Rod Bowing, Exxon Nuclear Company.

EFN-2328(P)(A), PWR Small Break LOCA Evaluation Model S-RELAP5 Based, Framatome ANP.

EMF-2087(P)(A), SEMPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications, Siemens Power Corporation.

XN-NF-44(NP)(A), A Generic Analysis of the Control rod Ejection Transient for Pressurized water reactors, Exxon Nuclear Company.

MILLSTONE - UNIT 2

Millstone Unit 3

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.8 PROCEDURES AND PROGRAMS..................................................................................

6-14 6.9 REPORTING REOUIREMENTS......................................................................................

6. 17 6.9.1 ROUTINE REPORTS.......................................................................................

6-17 Startup Report..................................................................................................

6. 17 Annual Reports................................................................................................
6. 18 I

Annual Radiological Environmental Operating Report..................................

6. 19 Annual Radioactive Effluent Release Report..................................................
6. 19 I

Core Operating Limits Report........................................................................

6-19a 6.9.2 SPECIAL REPORTS......................................................................................... 6-21 6.10 DELETED 6.1 1 RADIATION PROTECTION PROGRAM......................................................................

6-21 6.12 HIGH RADIATION AREA.............................................................................................. 6-21 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)...................................................................

6.24 6.14 RADIOACTIVE WASTE TREATMENT.......................................................................

6-24 6.15 RADIOACTIVE EFFLUENT CONTROLS PROGRAM................................................

6-25 6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.........................

6-26 6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM....................

6-26 6.18 TECHNlCAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM.....................

6-26 6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT........................................................

6-27 MILLSTONE.

UNIT 3 xix Amendment No. 54.69. 84. 473. 4%.

2 8 4 7 =7 M7

ADMINISTRATIVE CONTROLS Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*

6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4.

6.9.1.2a. Deleted 6.9.1.2b.The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-13 1 concentration (pCi/gm) and one other radioiodine isotope concentration (pCi/gm) as a function of time for the

  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

MILLSTONE - UNIT 3 6-1 8 Amendment No. 69, My

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the reactor coolant exceeded the radioiodine limit. The report covering the previous calendar year shall be submitted prior to March 1 of each year.

6.9.1.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and 1V.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the REMODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in the next annual report.

6.9.1.4 RADIOACTIVE EFFLUENT RELEASE REPORT

- - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - -.

A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the REMODCM and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section 1V.B. 1.

MILLSTONE - UNIT 3 6-19 Amendment No. 24, 33,69,84,W,

-7

ADMINISTRATIVE CONTROLS 6.9.1.5 Deleted CORE OPERATING LIMITS REPORT 6.9.1.6 a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Overtemperature AT and Overpower AT setpoint parameters for Specification 2.2.1,

2.

Shutdown Margin for Specifications 3/4.1.1.1.1, 3/4.1.1.1.2, and 3/4.1.1.2,

3.

Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3.

MILLSTONE - UNIT 3 6-19a Amendment No. %,G, 69,86,W,

218, I

North Anna Units 1 and 2

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted i n accordance w i t h 10 CFR 50.4.

5.6.1 Not used I

5.6.2 Annual Radio1 ogi cal Envi ronmental Operati nq Report The Annual Radi o l ogi cal Envi ronmental Operating Report coveri ng the operation o f the u n i t during the previous calendar year shall be submitted by May 1 o f each year. The report s h a l l include summaries, interpretations, and analyses o f trends o f the r e s u l t s o f the r a d i o l ogi cal envi ronmental monitoring program f o r the reporting period. The material provided shall be consistent w i t h the objectives outlined i n the O f f s i t e Dose Calculation Manual (ODCM),

and i n 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and 1V.C.

The Annual Radi ol ogi cal Environmental Operati ng Report shall i ncl ude the r e s u l t s o f analyses o f a1 1 radiological environmental samples and o f a1 1 environmental r a d i a t i o n measurements taken during the period pursuant t o the locations specified i n the t a b l e and figures i n the ODCM, as well as summarized and tabulated r e s u l t s o f these analyses and measurements commensurate w i t h the format i n the ODCM.

I n the event t h a t some individual r e s u l t s are not available f o r inclusion w i t h the report, the report shall be submitted noting and explaining the reasons f o r the missing results. The missing data s h a l l be submitted i n a supplementary report as soon as possible.

5.6.3 Annual Radioactive E f f l u e n t Release Report NOTE--------------------------------

A single submittal may be made for a m u l t i p l e u n i t station. The submittal shall combine sections common t o a l l u n i t s a t the station; however, f o r u n i t s w i t h separate radwaste systems, the submittal shall specify the releases o f radioactive material from each u n i t.

The Annual Radioactive Effluent Release Report covering the operation o f the u n i t i n the previous year shall be submitted p r i o r t o May 1 o f each year i n accordance w i t h 10 CFR 50.36a. The report (continued)

North Anna Units 1 and 2 5.6-1

Reporting Requi rements 5.6 5.6 Reporting Requi rements 5.6.3 Annual Radioactive E f f l u e n t Release Report (continued) s h a l l include a summary o f the q u a n t i t i e s o f r a d i o a c t i v e l i q u i d and gaseous e f f l u e n t s and s o l i d waste released from the u n i t. The material provided s h a l l be consistent w i t h the objectives o u t l i n e d i n the ODCM and Process Control Program and i n conformance w i t h 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.l.

5.6.4 Not used I

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating l i m i t s s h a l l be established p r i o r t o each reload cycle, o r p r i o r t o any remaining p o r t i o n o f a reload cycle, and s h a l l be documented i n the COLR f o r the following:

1.

Safety Limits,

2.

SHUTDOWN MARGIN,

3.

Moderator Temperature Coefficient,

4.

Shutdown Bank I n s e r t i o n Limits,

5.

Control Bank I n s e r t i o n Limits,

6.

AXIAL FLUX DIFFERENCE l i m i t s,

7.

Heat Flux Hot Channel Factor,

8.

Nuclear Enthalpy Rise Hot Channel Factor,

9.

Power Factor Mu1 t i p 1 i e r,

10. Reactor T r i p System Instrumentation - OTAT and OPAT T r i p Parameters,
11. RCS Pressure, Temperature, and Flow DNB Limits, and
12. Boron Concentration.

North Anna Units 1 and 2 5.6-2

Report i ng Requi rement s 5.6 5.6 Reporting Requi rements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

b.

The a n a l y t i c a l methods used t o determine the core operating l i m i t s s h a l l be those previously reviewed and approved by the NRC, s p e c i f i c a l l y those described i n the f o l l o w i n g documents:

1. VEP-FRD-42-A, "Reload Nuclear Design Methodology."

2. WCAP-9220-P-AY "WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION. I'

3. WCAP-9561-P-AY "BART A-1:

A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS-SPECIAL REPORT:

THIMBLE MODELING I N W ECCS EVALUATION MODEL."

4. WCAP-10266-P-A, "The 1981 Version o f the Westinghouse ECCS Evaluation Model Using the BASH Code."
5. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."
6. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code. I'
7. WCAP-12610, "VANTAGE+ FUEL ASSEMBLY-REFERENCE CORE REPORT."
8. VEP-NE-2-A,

" S t a t i s t i c a l DNBR Evaluation Methodology. I'

9. VEP-NE-3-A,

" Q u a l i f i c a t i o n o f t h e WRB-1 CHF Correlation i n the V i r g i n i a Power COBRA Code."

10. VEP-NE-1-A, "VEPCO Re1 axed Power D i s t r i b u t i o n Control Methodology and Associated FQ Survei 11 ance Technical Specifications."
11. WCAP-8745-P-A, "Design Bases f o r Thermal Overpower Del ta-T and Thermal Overtemperature Del ta-T T r i p Function. I'
12. WCAP-14483-A, "Generic Methodology f o r Expanded Core Operating L i m i t s Report. I'
13. BAW-10227P-A, "Eva1 uation of Advanced Cladding and Structural Material (M5) i n PWR Reactor Fuel.'I (Unit 2 )

(continued)

North Anna Units 1 and 2 5.6-3

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

b.

(continued)

14. BAW-10199P-A, "The BWU C r i ti cal Heat F1 ux Correl a t i ons. I' (Unit 2)
15. BAW-10170P-A, " S t a t i s t i c a l Core Design f o r Mixing Vane Cores. ' I (Unit 2)
16. EMF-2103 (P) (A), "Real i s t i c Large Break LOCA Methodology f o r Pressurized Water Reactors. I' (Unit 2)
17. EMF-96-029 (P) (A), "Reactor Analysi s System f o r PWRs. I' (Unit 2)
18. BAW-10168P-A, "RSG LOCA - BWNT Loss-of-Cool ant Accident Evaluation Model f o r Recirculating Steam Generator Plants,"

Volume I 1 only (SBLOCA models). (Unit 2)

c.

The core operating l i m i t s s h a l l be determined such t h a t a l l applicable l i m i t s (e.g.,

f u e l thermal mechanical l i m i t s, core thermal hydraul i c 1 i m i t s, Emergency Core Cool i ng Systems (ECCS) l i m i t s, nuclear l i m i t s such as SDM, t r a n s i e n t analysis l i m i t s,

and accident analysis l i m i t s ) o f the safety analysis are met.

d.

The COLR, i n c l u d i n g any midcycle revisions o r supplements, s h a l l be provided upon issuance f o r each reload cycle t o the NRC.

5.6.6 PAM Report When a r e p o r t i s required by Condition B o f LCO 3.3.3, "Post Accident Monitoring (PAM)

Instrumentation," a r e p o r t s h a l l be submitted w i t h i n the f o l l o w i n g 14 days. The r e p o r t s h a l l o u t l i n e the cause o f the i n o p e r a b i l i t y, and t h e plans and schedule f o r r e s t o r i n g the instrumentation channels o f the Function t o OPERABLE status.

5.6.7 Steam Generator Tube Inspection Report

a.

Following each inservice inspection o f steam generator tubes, the number o f tubes plugged i n each steam generator s h a l l be reported t o the Nuclear Regulatory Commission w i t h i n 15 days.

North Anna Units 1 and 2 5.6-4

Reporting Requi rements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

b.

The complete r e s u l t s o f t h e steam generator tube i n s e r v i c e inspection s h a l l be reported t o the NRC by March 1 o f each year f o r t h e previous calender year. This r e p o r t s h a l l include:

1. Number and extent o f tubes inspected.
2. Location and percent o f wall-thickness penetration f o r each i n d i c a t i o n o f an imperfection.
3. I d e n t i f i c a t i o n o f tubes plugged.
c.

Results o f steam generator tube inspections t h a t f a l l i n t o Category C-3 require prompt n o t i f i c a t i o n o f the Commission pursuant t o Section 50.72 t o 10 CFR Part 50. A Licensee Event Report s h a l l be submitted pursuant t o Section 50.73 t o 10 CFR Part 50 and s h a l l provide a d e s c r i p t i o n o f investigations conducted t o determine cause o f t h e tube degradation and c o r r e c t i v e measures taken t o prevent recurrence.

North Anna Units 1 and 2 5.6-5

Surry Units 1 and 2

TS 6.6-2 resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operations),

supplementary reports shall be submitted at least every 3 months until all three events have been completed.

1

2. Annual Reports
a. deleted Note: Footnotes 1 and 2 are located on page TS 6.6-1 1.

Amendment Nos.

TS 6.6-3

b. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.1.D.4. In addition, the information itemized in Specification 3.1.D.4 shall be included in this report.
3. deleted I

Amendment Nos.

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