ML032810447
| ML032810447 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/01/2003 |
| From: | Thayer J Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 03-90 | |
| Download: ML032810447 (38) | |
Text
Entergy Nuclear Vermont Yankee, LLC Entergy Nuclear Operations, Inc.
En tergy 185 Old Ferry Road Brattleboro, VT 05302-0500 October 1, 2003 BVY 03-90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Technical Specification Proposed Change No. 263 - Supplement No. 1 Extended Power Uprate - Technical Review Guidance By letter' dated September 10, 2003, Vermont Yankee2 (VY) proposed to amend Facility Operating License, DPR-28, for the Vermont Yankee Nuclear Power Station (VYNPS) to increase the maximum authorized power level from 1593 megawatts thermal (MWt) to 1912 MWt. The request for license amendment was prepared in accordance with the guidelines contained in the NRC-approved, NEDC-33004P-A3. Included with the license amendment request was NEDC-33090P4, a summary of the results of the safety analyses and evaluations performed specifically for the VYNPS power uprate.
To facilitate NRC staff review of the license amendment request, VY is providing as Attachment 1, a review matrix that cross-references NRC review criteria with associated sections of the VYNPS Constant Pressure Power Uprate Safety Analysis Report (i.e., NEDC-33090P). The review matrix is based on the matrices found in NRC's draft review standard RS-0015 for extended power uprates.
In addition, Attachment 2 contains a matrix of the draft General Design Criteria (GDC) used by the U.S.
Atomic Energy Commission to evaluate VY's original request for an operating license, compared to the GDC finally adopted in Appendix A to 10CFR50. As discussed in Appendix F to the Updated Final Safety Analysis Report (UFSAR), VYNPS was not licensed to the final GDC, and conformance with the intent of the draft GDC remains as stated in the UFSAR. Accordingly, the GDC matrix should be used in this context.
1Vermont Yankee letter to U.S. Nuclear Regulatory Commission, "Extended Power Uprate," Proposed Change No. 263, BVY 03-80, September 10,2003.
2 Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. are the licensees of the Vermont Yankee Nuclear Power Station.
GE Nuclear Energy, "Constant Pressure Power Uprate," Licensing Topical Report NEDC-33004P-A (Proprietary),
July 2003, and NEDO-33004-A (Non-Proprietary), July 2003.
4GE Nuclear Energy, "Safety Analysis Report for Vermont Yankee Nuclear Power Station Constant Pressure Power Uprate," NEDC-33090P, September 2003.
5 U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, "Review Standard for Extended Power Uprates," RS-00 1 (Draft), December 2002.
BVY 03-90 / Page 2 If you have any questions, please contact Mr. Len Gucwa at (802) 2584225.
Sincerely, ay Tiayer Me Vice President STATE OF VERMONT WINDHAM COUNTY
)ss Then personally appeared before me, Jay K. Thayer, who, being duly sworn, did state that he is Site Vice President of the Vermont Yankee Nuclear Power Station, that he is duly authorized to execute and file the foregoing document, and that the statements therein are true to the best of his knowledge and belief.
Sally A. Sindstruin, Notary Public f
f 0Ai Attachments cc: (with attachments)
USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS (two copies)
Vermont Department of Public Service
Docket No. 50-271 BVY 03-90 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 Supplement No. 1 Extended Power Uprate - Technical Review Guidance Review Guidance Matrix
MATRIX I SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Materials and Chemical Engineering ReactordVessel Matental All EPUs EMCB SRXB 5.3.1 GDC-14 RG 1.190 2.1.1 2.1.1 3.2.1 Surveillance Program Draft Rev. 2 GDC-31 April 1996 1 0 CFR 50, App.
H 10 CFR 50.fiO Preswure-Temperature Uffts and All EPUs EMCB SRXB 5.3.2 GDC-14 RG 1.161 2.1.2 2.1.2 3.2.1 Upper-Shelf Energy Draft Rev.
2 GDC 31 RG 1.190 Apr!1 1996 10OCFR 50, Ap. G RG 1.99 1 0 CFR, 50.60 Pressurized Themmal Shock PWR EPUs EMCB SRXB 5.3.2 GDC-14 RG 1.190 2.1.3 NA Draft Rev.2 GDC-31 RG 1.154 April 1996 1 0 CFR 50.61.
Reactor Intemnal and Core All EPUs EMCB SRXB 4.5.2 GDC-1 Note I*
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2.1.4 10.7 Support Materlals Draft Rev. 3 10 CFR 50.55a April 1996 MATRIX 1 OF SECTION 2.1 OF RSB001 (DRAFT)
DECEMBER 2002 Ace
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Note 3*
2.1.4 2.1.5 2.5.3 3.2.1 3.2.2 AND 10.7 4.5.1 GDC-1 Draft Rev. 3 10 CFR 50.55a April 1996 GDC-14 5.2.4 10 CFR 50.55a Draft Rev. 2 April 1996 5.3.1 Draft Rev. 2 April 1996 5.3.3 Draft Rev. 2 April 1996 6.1.1 Draft Rev. 2 April 1996 GDC-1 10 CFR 50.55a GDC-4 GDC-14 GDC-31 10 CFR 50, App. G Leak-Before-Break PWR EPUs EMCB Protective Coating Systems All EPUs EMCB (Paints) - Organic Materials t
1 2.1.6 l NA 3.6.3 Draft Aug. 1987 GDC-4 4.2.6 6.1.2 10 CFR 50, App. B Draft Rev. 3 RG 1.54 April 1996 2.1.7 MATRIX I OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 Effect of EPU on Flow-Accelerated Corrosion Ail EPUs EMCB Note 4*
l 2.1.6 12.1.8 10.7 Steam Generator Tube Inservice PWR EPUs EMCB Inspection Steam Generator Blowdown PWR EPUs EMCB System Chemical and Volume Control PWR EPUs EMCB System (Induding Boron Recovery System)
Reactor Water Cleanup System BWR EPUs EMCB NA 5A.2.2 Draft Rev. 2 April 1996 10 CFR 50.55a SPLB SRXB 10.A.8 GDC-14 Draft Rev. 3 April 1996 9.3A GDC-14 Draft Rev. 3 GDC-29 April 1996 5.4.8 GDC-14 Draft Rev. 3 GDC-60 April 1996 GDC-61 NA NA 3.11 10.7 Notes:
- 1. In addition to the SRP, guidance on neutron irradiation-related threshold for Inspection for Irradiation-assisted stress-corrosion cracking for BWRs is in BWRVIP-26 and for PWRs In BAW-2248 for E>1 MeV and In WCAP-14577 for E>0.1 MeV. For intergranular stress-corrosion cracking and stress-corrosion cracking In BWRs, review criteria and review guidance Is contained in BWRVIP reports and associated staff safety evaluations. For thermal and neutron embrittiement of cast austenitic stainless steel, stress-corrosion cracking, and vold swelling, applicants will need to provide plant-specific degradation management programs or participate In Industry programs to Investigate degradation effects and determine appropriate management programs.
- 2.
For thermal aging of cast austenitic stainless steel, review guidance and criteria Is contained in the May 19,2000, letter from C. Grimes to D. Walters, 'Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components.'
- 3. For intergranular stress corrosion cracking In BWR piping, review criteria and review guidance Is contained In BWRVIP reports, NUREG-0313, Rev. 2, GL 88-01, and associated safety evaluations.
MATRIX I OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 MATRIX 2 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Mechanical and Civil Engineering r
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DECEMBER 2002 Pressure-Retaining Components and Component Supports All EPUs EMEB 3.9.1 Draft Rev. 3 April 1998 GDC-1 GDC-2 GDC-14 GDC-15 2.2.2 2.2.2 2.5.3 3.1 3.9.2 Draft Rev. 3 April 1996 GDC-1 GDC-2 GDC-4 GDC-14 GDC-15 IN 95-016 IN 02-026 3.2.2 3.4 3.5 3.7 3.8 3.9.3 10 CFR 50.55a IN 96-049 Draft Rev. 2 GDC-1 GL 98-08 April 1998 GDC-2 GDC-4 GDC-14 GDC-15 5.2.1.1 Draft Rev. 3 April 1998 10 CFR 50.55a GDC-1 RG 1.84 RG 1.147 DG 1.1089 DG 1.1090 DG 1091 I _________
I MATRDI 2 OF SECTION 2.1 OF RS-01 (DRAFT)
DECEMBER 2002 w
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Reactor Pressure Vessel Internals and Core Supports All EPUs EMEB 3.9.1 GDC-1 Draft Rev. 3 GDC-2 April 1996 2.2.3 2.2.3 3.9.2 Draft Rev. 3 April 1996 GDC-1 GDC-2 GDC-4 IN 95-016 IN 02-026 3.1, 3.3 and 3.4.2 3.9.3 10 CFR 50.55a IN 96-049 Draft Rev. 2 GDC-1 GL 96-06 April 1996 GDC-2 GDC-4 3.9.5 Draft Rev. 3 April 1996 10 CFR 50.55a GDC-1 GDC-2 GDC-4 GDC-10 IN 02-026 MATRIX 2 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002
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IN 96-049 GL 96-06 2.2.4 2.2.4 3.1,3.8, 4.1.3, 4.1.4, 4.1.6 and 4.2 4
4 3.9.6 Draft Rev. 3 April 1996 GDC-1 GDC-37 GDC-40 GDC-43 GDC-46 GDC-54 10 CFR 50.55a(f)
GL 89-10 GL 95-07 GL 96-05 IN 97-090 IN 96-048s1 IN 96-048 IN 96-003 RIS 00-003 RIS01-015 RG 1.147 RG 1.175 DG 1089 DG 1091
- 4.
4 4
Seismic and Dynamic Qualification of Mechanical and Electrical Equipment All EPUs EMEB EEIB 3.10 Draft Rev. 3 April 1996 GDC-1 GDC-2 GDC-4 GDC-14 GDC-30 10 CFR 100, App. A 10 CFR 50, App. B USI A46 2.2.5 2.2.5 10.1 &
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.1 MATRIX 2 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 MATRIX 3 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Electrical Engineering 7
1-Areas of Review Applicable to Primary Review Branch Secondary Review Branch(es)
Environmental Qualification of All EPUs EEIB Electrical Equipment Offsite Power System All EPUs EEIB AC Onsite Power System All EPUs EEIB SRP Focus of SRP Section Usage Number 3.11 10 CFR 50.49 Draft Rev. 3 April 1996 8.1 GDC-17 Draft Rev. 3 April 1996 8.2 GDC-17 Draft Rev. 4 April 1996 8.2, App. A GDC-17 Draft Rev. 4 April 1996 8.1 GDC-17 Draft Rev. 3 April 1996 8.3.1 GDC-17 Draft Rev. 3 April 1996 Other Guidance Template Safety Evaluation Sed tion Number 0 BWR I
PWR Acceptance Review JCPPU: SAR
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BTP PSB-1 Draft Rev. 3 April 1996 BTP ICSB-1 1 Draft Rev. 3 Anril 1996 2.3.1 2.3.1 10.3.1 2.3.2 2.3.2 6.1.1 2.3.3 2.3.3 6.1.2 MATRIX 3 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 U
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8.1 GDC-17 Draft Rev. 3 10 CFR 50.63 April 1996 8.3.2 GDC-17 Draft Rev. 3 10 CFR 50.63 April 1996 2.3.4 2.3.4 6.2 Station Blackout All EPUs EEIB SPLB SRXB 8.1 Draft Rev. 3 April 1996 10 CFR 50.63 Note 1*
2.3.5 2.3.5 9.3.2 4
8.2, App. B Draft Rev. 4 April 1996 10 CFR 50.63 I
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- 1. The review of station blackout Includes the effects of the EPU on systems required for core cooling in the station blackout coping analysis (e.g., condensate storage tank Inventory, controls and power supplies for relief valves, residual heat removing system, etc.) to ensure that the effects are accounted for In the analysis.
MATRIX 3 OF SECTION 2.1 OF RS-Q01 (DRAFT)
DECEMBER2002 MATRIX 4 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Instrumentation and Controls Y
Areas of Review Applicable to.
' Prmnary:
.Review;'.
Branch Secondary.
- :'Review '
Branch(es):
Reactor Trip System All EPUs EEIB Engineered Safety Features All EPUs EEIB Systems Safety Shutdown Systems All EPUs EEIB
- SRPj :-
- Focus ofSRP Section Usage
Number..
Rev. 4 10 CFR 50.55a(h)
June 1997 GDC-1 GDC-4 GDC-13 GDC-19 7.3 GDC-20 Rev. 4 GDC-21 June 1997 GDC-22 GDC-23 GDC-24 7.4 10 CFR 50.55(a)(1)
Rev. 4 10 CFR 50.55a(h)
June 1997 GDC-1 GDC-4 GDC-13 GDC-19 GDC-24 7 '
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Guidance i:, Template Safety i
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2.4.1 2.4.1 5.3 2.4.1 2.4.1 5.3 2.4.1 2.4.1 53 MATRIX 4 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 U
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Y Areas of Review Applicable to Primary 0 Secondaiy Review
,,Review Branch Branch(es)
SRP: '
, Section Numbe r Focus' of SRP
- UsageOG, Other Template Safety Guidance Evaluation Section.
BWRNumberPWR Acceptance
- Review' Control Systems All EPUs EEIB Diverse l&C Systems All EPUs EEIB General guidance for use of other All EPUs EEIB SRP Sections related to I&C 1.
7.7 Rev. 4 June 1997 7.8 Rev. 4 June 1997 7.0 Rev. 4 June 1997 10 CFR 50.55(aXI) 10 CFR 50.55a(h)
GDC-1 GDC-13 GDC-19 GDC-24 2.4.1 2.4.1 j.i & 5.2 2.4.1 2.4.1 53 and 9.3.1 MATRDC 4 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 MATRIX 5 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Plant Systems I
Areas of Review Applicable to
'Primary:
-Review; Branch
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'Review; CPPU SAR Flood Protection EPUs that result in significant SPLB Increases In fluid volumes of tanks and vessels Equipment and Floor Drainage EPUs that result in Increases in SPLB System fluid volumes or in installation of larger capacity pumps or piping systems Circulating Water System EPUs that result In increases In SPLB fluid volumes associated with the circulating water system or in installation of larger capacity pumps or piping systems 3.4.1 GDC-2 Rev. 2 July 1981 9.3.3 GDC-2 Rev. 2 GDC-4 July 1981 10.4.5 GDC-4 Rev. 2 July 1981 A
2.5.1.1.1 2.5.1.1.1 NA*
2.5.1.1.2 2.5.1.1.2 NA*
2.5.1.1.3 2.5.1.1.3 NA*
2.5.1.2.1 2.5.1.2.1 NA**
2.5.1.2.1 2.5.1.2.1 NA**
Internally Generated Missiles (Outside Containment)
EPUs that result in substantially higher system pressures or changes in existing system configuration SPLB EMCB EMEB 3.5.1.1 Rev. 2 July 1981 GDC-4 Internally Generated Missiles EPUs that result in substantially SPLB EMCB 3.5.1.2 GDC-4 (Inside Containment) higher system pressures or EMEB Rev. 2 changes in existing system July 1981 configuration l
I* No significant increase in fluid volumes I** No substanial increase in system pressure (pressure increase) or no increase at all (CPPU) I MATRIX 5 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002
I Y
Areas of Review,
Applicable to Primary Review B:ranch-,
Secondary
'Review iI
-Branch(es).
Turbine Generator All EPUs except where the SPLB application demonstrates that previous analysis is bounding Protection Against Postulated EPUs that affect environmental SPLB Piping Failures In Fluid Systems conditions, habitability of the Outside Containment control room, or access to areas important to safe control of postaccident operations Fire Protection Program All EPUs except where the SPLB application demonstrates that previous analysis Is bounding PWR Dry Containments, EPUs for PWR plants with dry SPLB Including Subatmospheric containments (including Containments subatmospheric containments) except where the application demonstrates that previous analysis Is bounding Ice Condenser Containments EPUs for PWR plants with Ice SPLB condenser containments except where the application demonstrates that previous analysis is bounding EMCB EMEB SRP:
FocusofSRP.
Section ' :4
- 'Usage, Number 10.2 GDC-4 Rev. 2 July 1981 3.6.1 GDC-4 Rev. I July 1981 9.5.1 10 CFR 50.48 Rev. 3 10 CFR 50, App. R July 1981 GDC-3 GDC-5 6.2.1 GDC-13 Rev. 2 GDC-16 July 1981 GDC-38 GDC-50 6.2.1.1A GDC-64 Rev. 2 July 1981 6.2.1 GDC-13 Rev. 2 GDC-16 July 1981 GDC-38 GDC-50 6.2.1.1.E GDC-64 Rev. 2 July 1981
- Other Guidance
- - 1..'
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- 1.
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2.5.1.2.2 2.5.1.2.2 7.1 2.5.1.3 2.5.1.3 10.1 &
10.2 Note 1*
2.5.1.4 2.5.1.4 6.7 2.5.2.1 1NA 2.5.2.1 1 NX MATRIX SOF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER2002 Areas of Review Applicable to Primary Review Branch Secondary E Review I Branch(es)
Pressure-Suppression Type EPUs for BWR plants with SPLB BWR Containments pressure-suppression containments except where the application demonstrates that previous analysis Is bounding Subcompartment Analysis All EPUs except where the SPLB application demonstrates that previous analysis Is bounding Mass and Energy Release All EPUs except where the SPLB Analysis for Postulated application demonstrates that Loss-of-Coolant previous analysis Is bounding Mass and Energy Release PWR EPUs except where the SPLB Analysis for Postulated application demonstrates that Secondary System Pipe previous analysis is bounding Ruptures SRP '
2Focus of SRP
- - Other :
Guidance i - ~:
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Review
- kNumnber liD 0 i EW ;P\\Nt00lCPPU SAR 2.5.2.1 4_.1
~~~.1.2ug 4.1.2.3 2.5.2.2 4
2.5.2.3.1 4.1.1 through 4.1.2.2 2.5.2.3.2 I NA MATRIX 5 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 S
I Areas of Review Applicable to
- Primary Review Branch
- I Secondary Review
- Branch(es) t
- .
- SRP Section Number -
FocUS of SRP 4 Usage
- Other Guidance l z Template Safety l
Evaluation Section N:
Number F
BWR I
PWR:
Acceptance
- Review
Combustible Gas Control In EPUs that Impact hydrogen SPLB Containment release assumptions Containment Heat Removal All EPUs except where the SPLB application demonstrates that previous analysis Is bounding Secondary Containment EPUs that affect the pressure SPLB Functional Design and temperature response, or draw-down time of the secondary containment 6.2.5 10 CFR 50.44 Rev. 2 10 CFR 50.46 July 1981 GDC-5 GDC-41 GDC-42 GDC-43 6.2.2 GDC-38 Rev. 4 Oct 1985 6.2.3 GDC-4 Rev. 2 GDC-16 July 1981 2.5.2.4 2.5.2.4 4.7 DG-1 107 I
2.5.2.5 2.5.2.5 3.10 Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance Capability Studies PWR EPUs except where the application demonstrates that previous analysis is bounding SPLB SRXB 6.2.1 Rev. 2 July 1981 6.2.1.5 Rev. 2 July 1981 10 CFR 50.46 10 CFR 50, App. K 45 NA NA Pressurizer Relief Tank PWR EPUs that affect SPLB EMEB 5.4.11 GDC-2 pressurizer discharge to the PRT Rev. 2 GDC-4 July 1981 Control Room Habitability All EPUs except where the SPLB SPSB 6.4 GDC-4 System application demonstrates that Draft Rev. 3 GDC-19 previous analysis is bounding April 1996 ESF Atmosphere Cleanup All EPUs except where the SPLB SPSB 6.5.1 GDC-19 System application demonstrates that Rev. 2 GDC-41 previous analysis Is bounding July 1981 GDC.61 G D C -64 Note 2 2.5.3.1 Note 3*
2.5.3.1 1 4.4 2.5.3.2 2.5.3.2 4.5 MATRDI 5 OF 8ECTION 2.1 OF RS"001 (DRAFT)
DECEMBER 2002
'Areas of Review Applicableto Primary Secondary SRP Focusof SRP; Other Template Safety Acceptance Review-Review Section Usage Guidance Evaluation Section Review
-Banch: i Branch(es)
Number Number BWR PWR CPPU SAR Fission Product Control Systems All EPUs except where the SPLB EMCB 6.5.3 GDC-41 2.5.3.3 2.5.3.3 45 and Structures application demonstrates that Rev. 2 previous analysis is bounding July 1981 Main Condenser Evacuation EPUs for which the main SPLB_
10.4.2 GDC-60 2.5.3.4 2.5.3.4 No EPU System condenser evacuation system Is Rev. 2 GDC-64 effect modified July 1981 Turbine Gland Sealing System EPUs for which the turbine gland SPLB 10.4.3 GDC60-2.5.3.5 2.5.3.5 No EPU sealing system Is modified Rev.2 GDC64 effect July 1981
[j l3-~
Main Steam Isolation Valve BWR EPU that affect the amount SPLB 6.7 GDC-54 2.5.3.6.
4.
Leakage Control System of valve leakage that Is assumed Rev.2 and resultant dose July 1981 Control Room Area Ventilation All EPUs except where the SPLB SPSB 9.4.1 GDC-4 2.5.4it.
2.5.4.1 4.4 System application demonstrates that Rev. 2 GDC-19 previous analysis Is bounding July 1981 GDC-60 Spent Fuel Pool Area Ventilation All EPUs except where the SPLB SPSB 9.4.2 GDC-60 2.5.4.2 2.5.4.2 No EPU System application demonstrates that Rev. 2 GDC-61 2
2 N
effect previous analysis Is bounding July 1981_______
Auxiliary and Radwaste Area All EPUs except where the SPLB 9.4.3 GDC-60 2.5.4.3 2.5.4.3 No EPU Ventilation System application demonstrates that Rev. 2 effect previous analysis is bounding July 1981 Turbine Area Ventilation System All EPUs except where the SPLB 9.4.4 GDC-60 2.5.4.3 2.5.4.3 6.6 application demonstrates that Rev.2 previous analysis Is bounding July 1981_-______
ESF Ventilation System All EPUs except where the SPLB 9.4.5 GDC4 2.5.4.4 2.5.4.4 6.6 application demonstrates that Rev.2 GDC-17 previous analysis Is bounding July 1981 GDC-60 MATRIX 5 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 Areas of Review Applicable to Primary Secondary SRP Focuf SRP er pt Sa an Review i:Review Section Usage Guidance Evaluation Section Review
-Brn Br nch(es)
Number Number 7
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BWR PWR CPPU SAR Spent Fuel Pool Cooling and Al EPUs except where the SPLB EMCB 9.1.3 GDC-5 Note 4' 2.5.5.1 2.5.5.1 6.3 Cleanup System application demonstrates that Rev. 1 GDC-44 previous analysis is bounding July 1981 GDC-61 Station Service Water System All EPUs except where the SPLB 9.2.1 GDC-4 GL 89-13 2.5.5.2 2.5.5.2 6.4.1 &
application demonstrates that Rev. 4 GDC-5 and 6.4.4 previous analysis Is bounding June 1985 GDC-44 Suppl. 1 GL 96-06 and
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ S u p p l. 1 Reactor Auxiliary Cooling Water All EPUs except where the SPLB 9.2.2 GDC-4 GL 89-13 2.5.5.3 2.5.5.3 6.4.3 Systems application demonstrates that Rev. 3 GDC-5 and previous analysis Is bounding June 1986 GDC-44 Suppl. 1
~~~~~~~~~~GL 9606
~~~~~~~~~~and Suppl. 1~~~~~S Ultimate Heat Sink All EPUs except where the SPLB 9.2.5 GDC-5 2.5.5.4 2.5.5.4 6.4.5 application demonstrates that Rev. 2 GDC44 previous analysis is bounding July 1981 Auxiliary Feedwater System PWR EPUs except where the SPLB 10.4.9 GDC-4 2.5.5.5 NA application demonstrates that Rev. 2 GDC-5 previous analysis Is bounding July 1981 GDC-19
~~~~~GDC-34_
GDC-44 Main Steam Supply System All EPUs except where the SPLB 10.3 GDC4 2.5.6.1 2.5.6.1 3.5.2 &
application demonstrates that Rev. 3 GDG5 7.3 previous analysis is bounding April 1984 GDC-34 MATRIX 5 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 U
- l.
x V
x Areas of Review Applicable to -
Primary
- Review, W`Branch Secondary SRP-Review SectfonM Branch(es)
Number Focus of SRP I 'Usage l
Other -
l Guidance
- 'Template Safety;
- Evaluation Section
- t. - XNumber BWR Acceptanc
- Revlew CPPU SAR Main Condenser All EPUs except where the SPLB application demonstrates that previous analysis Is bounding Turbine Bypass System All EPUs except where the SPLB application demonstrates that previous analysis is bounding Condensate and Feedwater All EPUs except where the SPLB System application demonstrates that previous analysis Is bounding 10.4.1 GDC-60 2.5.6.2 2.5.6.2 7.2 Rev. 2 July1981 10.4.4 GDC-4 2.5.6.3 2.5.6.3 7.3 Rev. 2 GDC-34 July 1981 E '
10.4.7 GDC-4 2.5.6.4 2.5.6.4 7.4 Rev. 3 GDC-5 April 1984 GDC-44
,___i,_
Gaseous Waste Management Systems EPUs that impact the level of fission products In the reactor coolant system, or the amount of gaseous waste SPLB IEHB 11.3 Draft Rev. 3 April 1996 10 CFR 20.1302 GDC-3 GDC-60 GDC-61 10 CFR 50, App. I 2.5.7.1 2.5.7.1 8.2 Liquid Waste Management EPUs that Impact the level of SPLB IEHB 11.2 1 0 CFR 20.1302 2.5.7.2 2.5.7.2 8.1 Systems fission products in the reactor Draft GDC-60 coolant system, or the amount of Rev. 3 GDC-61 liquid waste April 1996 10 CFR 50, App. I Solid Waste Management EPUs that Impact the level of SPLB IEHB 11.4 10 CFR 20.1302 2.5.7.3 2.5.7.3 8.1 Systems fission products in the reactor Draft GDC-60 coolant system, or the amount of Rev. 3 GDC63 solid wasteApril1996 GDC-64 10 CFR 71 Emergency Diesel Engine Fuel EPUs that result In higher EDG SPLB 9.5.4 GDC4 2.5.8.1 2.5.8.1 No EPU Oil Storage and Transfer System electrical demands Rev. 2 GDC-5 effect
_ July 1981 GDC-17 Light Load Handling System EPUs except where the SPLB SPSB 9.1.4 GDC-61 1
2.5.8.2 2.5.8.2 No EPU (Related to Refueling) application demonstrates that Rev. 2 GDC-62 effect previous analysis Is bounding July 1981 l;
i D al MATRIX 5 OF SECTiON 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 MATRIX 6 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Reactor Systems Areas of Review
.Applicable to:
Primary Review Branch Secondary
- Review '
Branchtes)
SRPW:
Section Number I I.
Focus of SRP U, lsage';
.~..
. Other
'Guidance
- Template Safety Evaluaton Sectiro
- Number
!~~BWR.~
~ PWR-IAcceptance Review Fuel System Design All EPUs SRXB Nuclear Design AU EPUs SRXB Thermal and Hydraulic Design All EPUs SRXB 4.2 10 CFR 50.46 Note 1*
2.6.1 2.6.1 2.1 Draft Rev. 3 GDC-10 Note 2*
April 1996 GDC-27 GDC-35 4.3 GDC-10 RG 1.190 2.6.2 2.6.2 2.2,2.3 Draft Rev. 3 GDC-1 I GSI 170
& 2A April 1996 GDC-12 IN 97-085 GDC-13 GDC-20 GDC-25 GDC-26 GDC-27 GDC-28 4.4 GDC-10 Note 3*
2.6.3 2.6.3 2.2,2.3 Draft Rev. 2 GDC-12
&22A April 1996 MATRDI 6 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002
-.... \\:
s.
s..
w r
w~~~~~~~~~~~A cepanc Areas of Review 1.........
Applicable to
.1..I..-
..- :. 1.....
I Primary.
Revfew Branch ;;
Secondary Review Branch(es)
-1... I
...I.
SRP Section Number Focus of SRPI
- ; Usage Other.
Template Safety Guidance:
Evaluation Section a i i: :
- Number BWR
PWR Acceptance Review CPPU SAR' 1
5 6
I Functional Design of Control Rod Drive System All EPUs SRXB SPLB 4.6 Draft Rev. 2 April 1996 GDC-4 GDC-23 GDC-25 GDC-26 GDC-27 GDC-28 GDC-29 10 CFR 50.62(c)(3) 2.6.4.1 2.6.4.1 2.5 Overpressure Protection during All EPUs SRXB Power Operation Overpressure Protection during PWR EPUs SRXB Low Temperature Operation Reactor Core Isolation Cooling BWR EPUs SRXB System Residual Heat Removal System All EPUs SRXB Emergency Core Cooling System All EPUs SRXI 5.2.2 GDC-15 Draft Rev. 3 GDC-31 April 1996 5.2.2 GDC-15 Draft Rev. 3 GDC-31 April 1996 5.4.6 GDC-4 Draft Rev. 4 GDC-5 April 1996 GDC-29 GDC-33 GDC-34 GDC-54 10 CFR 50.63 Note 4*
2.6.4.2 2.6.4.2 3.1 2.6.4.3 1 NA 3.9 3.10 5.4.7 Draft Rev. 4 April 1996 GDC-4 GDC-5 GDC-19 GDC-34 2.6.4.4 Note 5*
2.6.4.4 6.3 GDC-4 Note 6*
2.6.5.6.2 2.6.5.6.3 4.2 Draft Rev. 3 GDC-27 and April 1996 GDC-35 4.3 10 CFR 50.46 10 CFR 50 App. K MATRDI 6 OF SECTION 2.1 OF RS4001 (DRAFT)
DECEMBER 2002 Areas of Review Applicable to Primary; Review Branch Secondary
. Review:
Branch(es)
..~....
- SRI' :
Sectgon Number i :... -:.
I... I.
I
.I
- IFocus of SRP Usage Other Guidance Template Safety Acceptance Evaluation Section Review Number BWR PWR CPPU SAR 2.6.4.5 6.5 I
I I
- 1.
I Standby Liquid Control System BWR EPUs SRXB EMCB SPLB 9.3.5 Draft Rev. 3 April 1996 GDC-26 GDC-27 10 CFR 50.62(c)(4)
Note 12*
Decrease in Feedwater All EPUs SRXB Temperature, Increase in Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve Steam System Piping Failures PWR EPUs SRXB Inside and Outside of Containment Loss of Extemal Load; Turbine Aul EPUs SRXB Trip, Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed)
Loss of Nonemergency AC Al EPUs SRXB Power to the Station Auxiliaries I
I 15.1.1-4 Draft Rev. 2 April 1996 GDC-10 GDC-15 GDC-20 GDC-26 Note 7' 2.6.5.1 2.6.5.1.1 9.1 15.1.5 GDC-27 Note 7' Draft Rev. 3 GDC-28 April 1996 GDC-31 GDC-35 2.6.5.1.2 1 NA 15.2.1-5 Draft Rev. 2 April 1996 GDC-10 GDC-15 GDC-26 Note 7*
2.6.5.2.1 2.6.5.2.1 19.1 15.2.6 GDC-10 Note 7' 2.6.5.2.2 2.6.5.2.2 No EPU Draft Rev. 2 GDC-15 effect April 1996 GDC-26 Loss of Normal Feedwater Flow All EPUs SRXB EEIB 15.2.7 Draft Rev. 2 April 1996 GDC-10 GDC-15 GDC-26 Note 7*
2.6.5.2.3 2.6.5.2.3 9.1 Feedwater System Pipe Breaks PWR EPUs SRXB EEIB 15.2.8 GDC-27 Note 7 Inside and Outside Containment Draft Rev.2GDC-28 April 1996 GDC_
_3 2.6.5.2.4 1 NA MATRIX 6 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 Areas of Review Applicable to-,
Prtmary,:,
Secondary' SRP Focus of SRP:
Other:
Template Safety Acceptance Review Review Section Usage';
Guidance Evaluation Section Review 8ranch Branch(es)~ ::Number Number.
BWR pWR CPPU SAR-Loss of Forced Reactor Coolant All EPUs SRXB I
15.3.1-2 GDC-10 Note 7*
2.6.5.3.1 2.6.5.3.1 No EPU Flow Including Trip of Pump Draft Rev. 2 GDC-15 effect Motor and Flow Controller I
April 1996 GDC-26 Malfunctions Reactor Coolant Pump Rotor All EPUs SRXB 15.3.3-4 GDC-27 Note 7*
2.6.5.3.2 2.6.5.3.2 No EPU Seizure and Reactor Coolant j
Draft Rev. 3 GDC-28 effect Pump Shaft Break April 1996 GDC-31 Uncontrolled Control Rod All EPUs SRXB 15.4.1 GDC-10 Note 7*
2.6.5.4.1 2.6.5.4.1 No EPU Assembly Withdrawal from a Draft Rev. 3 GDC-20 effect Subcritical or Low Power Startup April 1996 GDC-25 Condition Uncontrolled Control Rod All EPUs SRXB 15.4.2 GDC-10 Note 7*
2.6.5.4.2 2.6.5.4.2 No EPU Assembly Withdrawal at Power n
Draft Rev. 3 GDC-20 effect April 1996 GDC-25 Control Rod Misoperation PWR EPUs SRXB 15.4.3 GDC-10 Note 7*
2.6.5.4.3 NA (System Malfunction or Operator Draft Rev. 3 GDC-20 Error)
April 1996 GDC-25 Stareup of an Inactive Loop or All EPU SRXB 1.4.4-5 GDC-10 Note 7*
2.6.5.4.3 2.6.5.4.4 9.1 Recirculation Loop at an o
A EPDrast Rev. 2 GDC-15 Incorrect Temperature, and Flow April 1996 GDC-20 Controller Malfunction Causing GDC-26 an Increase In BWR Core Flow GDC-28 Rate Chemical and Volume Control PWR EPUs SRXB 15.4.6 GDC-10 Note 7*
2.6.5.4.5 NA System Malfunction that Results Draft Rev. 2 GDC-15 In a Decrease in Boron April 1996 GDC-26 Concentration In the Reactor Coolant
_3_
MATRDX 6 OF SECTION 2.1 OF RS001 (DRAFT)
DECEMBER 2002 w B -
~~~~~~~~~~~~~~~~~~~~~~~~~~~ceptance Areas of Review Applicable to
-.... I...
Primary Review Branch Secondary Review V Branch(es)
..... i
.. 1..
SRP-Section Number Focus of SRP Usage Other Template Safety Guidance Evaluation Section Number BWR PWR; Note 7*
2.6.5.4.6 4
4 tImi.
4 4.
Spectrum of Rod Ejection Accidents PWR EPUs SRXB I
. 7. - I 15.4.8 Draft Rev. 3 I
April 1996 GDC-28 Spectrum of Rod Drop Accidents BWR EPUs SRXBl Inadvertent Operation of ECCS All EPUs SRXB and Chemical and Volume Control System Malfunction that Increases Reactor Coolant I
Inventory
__ I Inadvertent Opening of a PWR All EPUs SRXB Pressurizer Pressure Relief Valve or a BWR Pressure Relief Valve Steam Generator Tube Rupture PWR EPUs SRXB Loss-of Coolant Accidents All EPUs SRXBI Resulting from Spectrum of I
Postulated Piping Breaks within the Reactor Coolant Pressure Boundary Anticipated Transient Without All EPUs SRXB Scram New Fuel Storage EPU applications that request SRXB approval for new fuel.
4 4
15.4.9 Draft Rev. 3 April 1996 GDC-28
.Acceptance Review CPPU SAR.
NA 9.2 No EPU Note 7*
4 4
15.5.1-2 Draft Rev. 2 April 1996 GDC-10 GDC-15 GDC-26 Note 7*
Note 8*
2.6.5.5 2.6.5.5 1'
I 15.6.1 Draft Rev. 2 April 1996 GDC-10 GDC-15 GDC-26 Note 7*
2.6.5;:6s 15.6.3 Note 7*
Note Draft Rev. 3 Note 9*
l Note 9*
April 1996 l
2.6.5.6.1 2.6.5.6.2 2.6.5.6.3 No EPU effect NA 9.2 15.6.5 Draft Rev. 3 April 1996 GDC-35 10 CFR 50.46 Note 7*
Note 10*
2.6.5.6.2 Note 7*
Note 11*
Note 12*
2.6.5.7 2.6.5.7 9.3 9.1.1 I
Draft Rev. 3 r
April 1996 GDC-62 2.6.6.1 2.6.6.1 No EPU effect MATIRD 6 OF SECTiON 2.1 OF RS 001 (DRAFT)
DECEMBER2002 U
U U
Areas of Review I Applicable to ri:mary Sebondary SRP:
Fou of SRP Other T
Se Acceptance I
i Q i; i
u Review Review Secton Usage Guidance Evaluation Section Revew I ;;
- R ;-tS f;
0 !:
- f BBranch Banch(es)l Number um er I
BWR }
~~~~~~~~~~~~~~~~~~~~~
CPPU SAR i
-., f X [. :::. : a:...i.2 S:
- W.
-R Spent Fuel Storage EPU applications that request SRXB
_ approval for new fuel.
9.1.2 GDC-4 Draft Rev. 4 GDC-62 April 1996 1 12.6.6.21 2.6.6.2 NA Notes:
- 1.
When mixed cores (i.e., fuels of different designs) are used, the review covers the licensee's evaluation of the effects of mixed cores on design-basis accident and transient analyses.
- 2.
The current acceptance criteria for fuel damage for reactivity Insertion accidents (RIAs) requires revision per Research Information Letter No. 174, Interim Assessment of Criteria for Analyzing Reactivity Accidents at High Bumup.* The Office of Nuclear Regulatory Research is conducting confirmatory research on RIAs and the Office of Nuclear Reactor Regulation is discussing the Issue of fuel damage criteria with the nuclear power Industry as part of the industry's proposal to increase fuel bumup limits in the future. In the interim, current methods for assessing fuel damage In RIAs are considered acceptable based on the NRC staffs understanding of actual fuel performance, as shown In three-dimensional kinetic calculations which Indicate acceptably low fuel cladding enthalpy.
- 3.
The review also covers core design changes and any effects on radial and bundle power distribution, including any changes In critical heat flux ratio and critical power ratio. The review will also confirm the adequacy of the flow-based average power range monitor flux trip and safety limit minimum critical power ratio at the uprated conditions.
- 4.
The review also covers the method used In determining allowable power levels with Inoperable main steam safety valves.
- 5.
The review also covers the total time necessary to reach the shutdown cooling Initiation temperature.
- 6.
The review for BWRs will cover (1) the basis for use of the ISCOR computer code In emergency core cooling system analyses, (2) the spectrum of breaks analyzed, (3)justification for changes in calculated peak cladding temperature (PCT) for the licensing-basis case and the upper-bound case and any impact of the changes In PCTs on the use the licensing methods for the power uprates.
- 7.
The review also confirms:
The licensee used codes and methods approved for the plant-specific application and the licensee's use of the codes and methods complies with any limitations, restrictions, and conditions specified In the approving safety evaluation.
All changes of reactor protection system trip delays are correctly addressed and accounted for in the analyses.
(For PWRs) Steam generator plugging and asymmetry limits are accounted for in the analyses.
(For PWRs), Any observed hot-leg streaming effects are accounted for In the analyses.
(For PWRs). The licensee's evaluation of the effects of Westinghouse Nuclear Service Advisory Letters (NSALs). NSAL 02-3 and Revision 1, NSAL 02-4, and NSAL 02-5. These NSALs document problems with water level setpoint uncertainties in Westinghouse-designed steam generators. The review is conducted to ensure that the effects of the problems identified have been accounted for in steam generator water level setpoints used in LOCA, non-LOCA, and ATWS analyses.
MATRDI f OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 MATRIX 7 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Source Terms and Radiological Consequences Analyses Areas of Review Applicable to Primary Review Branch Secondary Review Branch(es)
SRP Section Number Focus of SRP Usage Other Guidance Template Safety Evaluation Section Number BWR I PWR Acceptance Review Source Terms for Input into All EPUs SPSB Radwaste Management Systems Analyses 11.1 10 CFR 20 Draft Rev. 3 10 CFR 50, App. I April 1996 GDC-60 2.7.1 2.7.1 8.4 Radiological Consequence Analyses Using Alternative Source Terms EPUs that utilize alternative source term SPSB EEIB EMCB EMEB IEHB SPLB SRXB 15.0.1 Rev. 0 July 2000 10 CFR 50.67 GDC-19 10 CFR 50.49 10 CFR 51 10 CFR 50, App. E NUREG-0737 2.7.2 2.7.2 9.2 I
I 4
.1.
4-Radiological Consequences of Main Steamline Failures Outside Containment for a PWR PWR EPUs that do not utilize alternative source term whose main steamline break analyses result in fuel failure SPSB SRXB 15.1.5, App. A Draft Rev. 3 April 1996 10 CFR 100 Notes 4, 5, 6, 7, 27*
2.7.2 1NA I
4 6.4 Draft Rev. 3 April 1996 GDC-19 Notes 1, 2, 3, 28, 29*
Radiological Consequences of EPUs that do not utilize SPSB SRXB 15.3.3-4 10 CFR 100 Notes 5, 8, Reactor Coolant Pump Rotor alternative source term whose Draft Rev. 3 9, 27*
Seizure and Reactor Coolant reactor coolant pump rotor April 1996 Pump Shaft Break seizure or reactor coolant pump shaft break results in fuel failure 6.4 GDC-19 Notes 1, 2, Draft Rev. 3 3, 28, 29*
April 1996 2.7.3 INA MATRIX 7 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 E~~
~ ~~~~~~~
9 U
Areas of Review Applicable to Primary Review
'Branch li
' Secondary Review Branch(es)
I. -.... I I...
I I SRP Section Number I.. -
I... - :
.... w..-
Focus of SRP
- Usage
Other..
Template Safety Guidance Evaluation Section Number BWR PWR Radiological Consequences of a PWR EPUs that do not utilize SPSB SRXB 15.4.8. App. A 10 CFR 100 Notes 4, Control Rod Ejection Accident alternative source term whose Draft Rev. 2 21, 22,27' rod ejection accident results In April 1996 fuel failure or melting 6.4 GDC-19 Notes 1, 2, Draft Rev. 3 3, 28,29*
April 1996
_~
2.7.4 Acceptance
- Review '
NA 9.2 9.2 Radiological Consequences of Control Rod Drop Accident BWR EPUs that do not utilize alternative source term whose control rod drop accident results in fuel failure or melting SPSB SRXB 15.4.9, App. A Draft Rev. 3 April 1996 10 CFR 100 Notes 9, 10,2r
.9 9
6.4 Draft Rev. 3 April 1996 GDC-19 Notes 1. 2.
3,28,29' Radiological Consequences of EPUs that do not utilize SPSB the Failure of Small Lines altemative source term whose Carrying Primary Coolant failure of small lines carrying Outside Containment primary coolant outside containment result in fuel failure 15.6.2 GDC-55 Draft Rev. 3 10 CFR 100 April 1996 2.7.3 2.7.5 6.4 Draft Rev. 3 April 1996 GDC-19 Notes 1. 2, 3, 28,29*
MATRDI 7 OF SECTION 2.1 OF RS-001 (DRAFT DECEMBER 2002 1 -
I.
. I Areas of Review Applicable to Primary
- Review Branch; Secondary
. Review Branch es) 7 1
SRP Section Number Focus of SRP U sage
- Other, i
Template Safety Guidance Evaluation Section Numbert BWR PWR Radiological Consequences of PWR EPUs that do not utilize SPSB SRXB 15.6.3 10 CFR 100 Notes 4, Steam Generator Tube Failure alternative source term whose Draft Rev. 3 13, 14,15, steam generator tube failure April 1996 27*
results in fuel failure 6.4 GDC-19 Notes 1, 2, Draft Rev. 3 3,28,29*
April 1996 I
INEEMOMENNOU 2.7.6 AAcceptance
- Review; f NA 9.2 9.2 Radiological Consequences of Main Steamline Failure Outside Containment for a BWR BWR EPUs that do not utilize alternative source term whose main steam line failure outside containment results in fuel failure SPSB SRXB 15.6.4 Draft Rev. 3 April 1996 10 CFR 100 I.
I.~~
Note 27*
Notes 1. 2, 3, 28,29*
2.7.4 6.4 Draft Rev. 3 April 1996 GDC-19
- 4.
4
- 4.
4 I
I Radiological Consequences of a Design Basis Loss-Of-Coolant-Accident Including Containment Leakage Contribution EPUs that do not utilize alternative source term SPSB SPLB 15.6.5, App. A Draft Rev. 2 Apnl 1996 10 CFR 100 Notes 4, 23,24,25, 26, 27*
2.7.5 2.7.7
- 1.
4 6.4 Draft Rev. 3 April 1996 GDC-19 Notes 1. 2, 3, 28,29*
A.
A.
L A.
J.
I I
1 MATRIX 7 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 Ara oifReview Applicable to
!,Primary Secondary SRP Section Focus of SRP Other.
Template Safety Acceptance Review Review Number
-Usage-Guidacem Evaluation Section -
Revw 4 Branc h Branch(es),1 Number:
~~ ~~
~~~ ~ ~ ~~BW R.
PW R V SA t.~~~~~~ ~~~
,0 : : ' V Sff; ' f.
Radiological Consequences of a EPUs that do not utilize SPSB SPLB 15.6.5, App. B 10 CFR 100 Notes 11, 2.7.5 2.7.7 9.2 Design Basis Loss-Of-Coolant-alternative source term Draft Rev.2 27 Accident Leakage from ESF April 1996 Components Outside Containment 6.4 GDC-19 Notes 1, 2.
Draft Rev. 3 3, 28, 29*
April 1996 Radiological Consequences of a BWR EPUs that do not utilize SPSB 15.6.5. App. D 10 CFR 100 Notes 9, 2.7.5 9.2 Design Basis Loss-Of-Coolant-alternative source term Draft Rev.2 12,27 Accident Leakage from Main April 1996 Steam Isolation Valves 6.4 GDC-19 Notes 1, 2, Draft Rev. 3 3,28.29*
~~~April 1996 Radiological Consequences of EPUs that do not utilize SPSB SPLB 15.7.4 10 CFR 100 Notes 4, 5.
2.7.6 2.7.8 9.2 Fuel Handling Accidents alternative source term Draft Rev. 2 GDC-61 18,19,20, April 1996 27*
6.4 GDC-19 Notes 1. 2, Draft Rev. 3 3,28,29*
April 1996 Radiological Consequences of EPUs that do not utilize SPSB EMEB 15.7.5 10 CFR 100 Notes, 5, 2.7.7 2.7.9-No EPU Spent Fuel Cask Drop alternative source term SPLB Draft Rev. 3 GDC-61 16, 17, 8, effect Accidents April 1996 18,27*
6.4 GDC-19 Notes 1, 2.
Draft Rev. 3 3,28,29*
April 1996 MATRDI 7 OF SECTION 2.1 OF RS001 (DRAFT)
DECEMBER 2002 MATRIX 8 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Health Physics Acceptance...........
Areas of Review
- Applicable to Prnmary:
IIReview
- Branch
- 0 Secondary.
- Review-Branch(es)
' 'SRP f Sectioni'
,.Number f
.. ::Focus of SRP.
1: :,
..Usa.ge; E':
- Other ::
Guidance:
_ I, T.:
i,emplateSafety..
' Evaluetlon Section:
`
iNumber
- :::':BWR:
I PWR::::
R 7
-5..I -- -....
Acceptance
': Review CPPU SAR.
Radiation Sources All EPUs IEHB Radiation Protection Design All EPUs IEHB Features Operational Radiation Protection All EPUs IEHB Program 12.2 10 CFR 20 Draft Rev. 3 April 1996 12.3-4 10 CFR 20 Draft Rev. 3 GDC-19 April 1996 2.8.1 2.8.1 8.3 8&
8.4 2.8.1 2.8.1 8.5 12.5 Draft Rev. 3 April 1996 10 CFR 20 Note 1 2.8.1 2.8.1
8.5 Notes
- 1. Regulatory Guide 8.14 was withdrawn on February 9, 2001, and should not be used.
MATRI 8 OF SECTION 2.1 OF RS-001 (DRAFT)
DECEMBER 2002 MATRIX 9 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Human Performance
~~~
Areas of Reviewv
..........1...... -... -.....
Applicable to
-.. I.
I...
I.....
, Primary
.:Review
- Branch'
_ Secondary
. Review -
.Branch(es).
., :'.I. '.'.'. I.:. ~.
Reactor Operator Training All EPUs IEHB Training for Non-Ucensed Plant All EPUs IEHB Staff Operating and Emergency All EPUs IEHB Operating Procedures Human Factors Engineering All EPUs IEH_
.Section 0 Usage
.0-Number.
132.1 Speclfic review Draft Rev. 2 questions are Dec. 2002 provided in the template safety evaluations.
13.2.2 Specific review Draft Rev. 2 questions are Dec. 2002 provided In the template safety evaluations.
13.5.2.1 Specific review Draft Rev. I questions are Dec. 2002 provided in the template safety evaluations.
18.0 Specific review Draft Rev. 1 questions are Dec. 2002 provided In the template safety evaluations.
I
'Other Guidance
....... I... -.11-1.....
.Template Safetyir' Evaluation Section Number
.BWR :
PWR Acceptance
-: R'evlew4 2.9 2.9 10.6 2.9 2.9 10.6 2.9 2.9 10.9 2.9 2.9 10.6 SPLB SRXB MATRIX 9 OF SECTION 2.1 OF RB.001 (DRAFT)
DECEMBER 2002 MATRIX 10 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Power Ascension and Testing Plan Areas of Review Applicable to Primary.
- Review :
Branch Secondary.
Review Branch(es)
!.'. SSRP. :::
I Section I Number
... I........
. q Focus of1SRP.
,; Usage,,,
1 :i Oher:'
- Guidance
.1.- I.
- : Template Safety I
Evaluathion ecton: :
. _ Number,.:
,,BWR -
PWR i Acceptance
...- Review'..
-- l...I :R Power Ascension and Testing All EPUs IEHB EEIB 14.2.1 Entire Section EMCB Draft Rev. 0 EMEB Dec. 2002 SPIB SPSB SRXB 210 2.10 10.4 MATRIX 10 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002 MATRIX I 1 SCOPE AND ASSOCIATED TECHNICAL REVIEW GUIDANCE Risk Evaluation 7~~~~~~~~~~~~~~~~~1.... I.-...
Areas of Review Applicable to Primary Secondary Review Review Branch Branch(es)
T SRP I-Section 1
) Number Focus of SWP
.? ::.Usage.:..
Other;;
.Guidance-I Template Saety
- Evaluation Section
- Number 0 BWR
[
PWR Acceptance R i~ eview:.'
CPPU SAR Risk Evaluation All EPUs SPSB Note 1*
2.11 2.11 10.5 RG 1.174 RIS 2001-02 Notes:
- 1. The staffs review Is based on Attachment 2 to this matrix. Attachment 2 invokes SRP Chapter 19, Appendix D, if special circumstances are Identified during the review.
MATRIX 11 OF SECTION 2.1 OF RS.001 (DRAFT)
DECEMBER 2002
- I -
Docket No. 50-271 BVY 03-90 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 Supplement No. 1 Extended Power Uprate - Technical Review Guidance AEC/GDC Matrix
BVY 03-90 / Attachment 2 / Page 1 AEC / GDC Matrix AEC Draft GDC 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 I OCFR50. Appendix A GDC 1
2 3
5 1
10 12 11 14 16 19 13 13 20 20 30 64 63 21 21 N/A 24 22 17 21 23 26 N/A 26 26 25 28 14 & 31 31 31 32 33 & 35 36&37 17 & 18 4
35 & 38 4
N/A
BVY 03-90 / Attachment 2 / Page 2 AEC / GDC Matrix (continued)
AEC Draft GDC 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 IOCFR50. Appendix A GDC 35 36 37 37 37 50 51 54 & 55 38 56 & 57 52 52 53 54 39 40 40 40 42 43 43 43 62 61 &63 61 61 60