ML18153B999

Forwards Response to Generic Ltr 89-21 Re Status of Implementation of USI Requirements at Facilities.Actions Re USI A-26, Reactor Vessel Pressure Transient Protection Completed Via Amends 55 & 56 to SER on 800304

ML18153B999
Person / Time
Site:	Surry, North Anna, 05000000
Issue date:	11/29/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR 89-770, GL-89-21, NUDOCS 8912060448
Download: ML18153B999 (12)

Text

• . e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 29, 1989 United States Nuclear Regulatory Commission Serial No.89-770 Attention: Document Control Desk NUCGL:vlh R1 Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 89-21 STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE REQUIREMENTS Generic Letter (GL) 89-21, entitled "Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements," requests licensee review and reporting of the status of implementation of USls for which a final technical resolution has been achieved and which are applicable to the licensee's facility.

Attachments 1 and 2 identify the status and pertinent remarks for the USls listed in GL 89-21 for Surry Power Station Units 1 and 2 and North Anna Power Station Units 1 and 2, respectively.

Should you have any questions regarding this information, please contact us.

Very truly yours,

. Stewart e ior Vice President - Nuclear Attachments 8912060448 891129 ,,

PDR ADOCK 05000280 1'

' p PNU I

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

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station

ATIACHMENT 1 SURRY POWER STATION UNITS 1 AND 2 UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-1 Water Hammer SECY 84-119, All NC **Full member of National NUREG-0927 Rev. 1, Academy for Nuclear Training -

NUREG-0993 Rev. 1, INPO accredited.

NUREG-0737 Item I.A.2.3,**

A-2/ Asymmetric Blowdown SRP revisions NUREG-0609, PWR NC 6/16/86 SER - Amendment e

MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Nos. 108/108.

Coolant Systems A-3 Westinghouse Steam NUREG-0844, W-PWR NC Refer to our letter 85-300, Generator Tube Integrity SECY 86-97, 6/17/85.

SECY 88-272, GL 85-02 (No requirements)

A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97, CE-PWR NA Integrity SECY 88-272, GL 85-02 (No requirements)

A-5 B&W Steam Generator NUREG-0844, SECY 86-97, B&W-PWR NA Tube Integrity SECY 88-272, GL 85-02 (No requirements)

A-6 Mark I Containment NUREG-0408 Mark 1-BWR NA A-7/ Mark I Long-Term Program NUREG-0661, Mark 1-BWR NA D-01 NUREG-0661 Suppl. 1, GL 79-57

• LEGEND:

C - NECESSARY CHANGES COMPLETE NC - NO PHYSICAL CHANGES NECESSARY NA - NOT APPLICABLE I - NECESSARY CHANGES INCOMPLETE E - EVALUATING IF ACTIONS REQUIRED

ATTACHMENT 1 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-8 Mark II Containment NUREG-0808, Mark 11-BWR NA Pool Dynamic Loads NUREG-0487 Suppl. 1/2, NUREG-0802, SRP 6.2.1.1C, GDC 16 A-9/ Anticipated Transients NUREG-0460 Vol. 4, All 5/26/88 SER for AMSAC de-MPA A-20 Without Scram 10 CFR 50.62 sign. Per our letter 87-347, 7/31/87, installation planned for refueling outage at end of e

Cycle 10 - current forecast for Units 1 and 2 is Fall 1990 and Spring 1991, respectively.

A-10/ BWR Feedwater Nozzle NUREG-0619, BWR NA MPA B-25 Cracking Letter from DG Eisen hut dated 11 /13/80, GL81-11 A-11 Reactor Vessel Material NUREG-0744 Rev. 1, All E Refer to our letter 87-223D, Toughness 10 CFR 50.60, 2/20/89. Response to NRC 82-26 request for additional information outstanding -

submittal forecast 12/15/89.

Unit 2 - > 50 ft lb for 40 year OL. Unit 1 - 18 EFPY with program to evaluate flux reduction. Participation in e

BWOG Materials Group.

A-12 Fracture Toughness of NUREG-0577 Rev. 1, PWR NA Resolution applies only to Steam Generator and SRP 5.3.4 Revision CP issued after 10/83. No Reactor Coolant Pump backfit requirements.

Supports ATIACHMENT 1 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-17 Systems Interactions Ur: De Young to All Internal flooding aspect will licensees - 9/72, be addressed in IPEs. Per NUREG-1174, NUREG- our letter 89-654, 10/30/89, 1229, NUREG/CR-3922, IPEs to NRG in 11/90. USI NUREG/CR-4261, NUREG/ A-46 addresses seismic CR-4470, GL 89-18 aspect. USI A-44 and Gl-128 A-24/ Qualification of Class (No requirements)

NUREG-0588 Rev. 1, A II C address electrical aspect.

3/12/88 SER for EQ program.

e MPA B-60 1 E Safety-Related SRP3.11, NRG letter, dated 2/16/88.

Equipment 10 CFR 50.49, NRG Inspection Report GL 82-09, GL 84-24, 50-280, 281/88-24, GL 85-15 8/2/88, closed issue A-26/ Reactor Vessel Pressure DOR Letters to PWR C 3/4/80 SER -

MPA B-04 Transient Protection Licensees 8/76, Amendment Nos. 56/55.

NUREG-0224, NUREG-0371, SRP 5.2, GL 88-11 A-31 Residual Heat Removal NUREG-0606, All OLs After NA Shutdown Requirements RG 1.113, RG 1.139, 01/79 SRP 5.4.7 A-36/ Control of Heavy Loads NUREG-0612, All C 5/16/84 SER. Ongoing MPA C-10, C-15 Near Spent Fuel SRP 9.1.5, GL 81-07, GL 83-42, GL 85-11, program self-assessment to identify and resolve deficiencies, which are e

Letter from DG being addressed separate Eisenhut dated from this generic activity.

12/22/80 A-39 Determination of SRV NUREG-0802, BWR NA Pool Dynamic Loads NUREG-0763, NUREG-and Pressure Transients 0783, NUREG-0802, NUREG-0661, SRP 6.2.1.1.C ATTACHMENT 1 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-40 Seismic Design SRP Revisions, NUREG/ All NA Refer to A-46. Member Criteria CR-4776, NUREG/CR-0054, of SQUG.

NUREG/CR-3480, NUREG/

CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776, NUREG/CR-3805, NUREG/CR-5347, NU REG/CR-3509 A-42/ Pipe Cracks in Boiling NUREG-0313 Rev. 1, BWR NA MPA B-05 Water Reactors NUREG-0313 Rev. 2, GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All NA GL 85-22 imposes no Sump Performance NUREG-0869 Rev. 1, requirements for SPS.

NUREG-0897, RG 1.82 (Rev. 0), SRP 6.2.2, GL 85-22 (No requirements)

A-44 Station Blackout RG 1.155, All Refer to our letters88-414, NUREG-1032, 4/17/89 and 88-414A, NUREG-1109, 4/20/89. Completion of 10 CFR 50.63 proposed mods 2 years after NRC notification per A-45 Shutdown Decay Heat SECY 88-260, All 10CFR50.63(C)(3).

Will be addressed in IPEs.

e Removal Requirements NUREG-1289, Per our letter 89-654, NUREG/CR-5230, 10/30/89, IPEs to NRG in SECY 88-260 11/90.

(No requirements)

A-46 Seismic Qualification NUREG-1030, All I Refer to our letter 88-514, of Equipment in NUREG-1211, 10/7/88. Seismic plant Operating Plants GL 87-02, GL 87-03 walkdowns scheduled for end of second refueling outage after 12/31/89 -

current forecast for Units 1 and 2 is Spring 1992 and Winter 1993, respectively.

ATIACHMENT 1 {Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-47 Safety Implication NUREG-1217, All E GL 89-19 response of Control Systems NUREG-1218, GL 89-19 due 3/19/90.

A-48 Hydrogen Control 10 CFR 50.44, All, except NA Also not applicable to Measures and Effects SECY 89-122 PWRswith subatmospheric of Hydrogen Burns large dry containments.

A-49/

on Safety Equipment Pressurized Thermal RG 1.154, RG 1.99, containments PWR NC 12/7/87 SER. Updated e

MPA A-21 Shock SECY 82-465, assessment of projected SECY 83-288, values of RT-PTS required SECY 81-687, by 10 CFR 50.61.

10 CFR 50.61, GL 88-11 e

ATTACHMENT2 NORTH ANNA POWER STATION UNITS 1 AND 2 UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-1 Water Hammer SECY 84-119, All NC 6/76 SER, NUREG-0053.

NUREG-0927 Rev. 1, Full member of National NUREG-0993 Rev. 1, NUREG-0737 Item I.A.2.3, SRP revisions Academy for Nuclear Training -

INPO accredited. e A-2/ Asymmetric Blowdown NUREG-0609, PWR NC 12/15/88 SER -

MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Amendment Nos. 107/93.

Coolant Systems '

A-3 Westinghouse Steam NUREG-0844, W-PWR NC Refer to our letter 85-300, Generator Tube Integrity SECY 86-97, 6/17/85. 10/23/87 and SECY 88-272, 12/11 /87 SE Rs for SGTR.

GL 85-02 (No requirements)

A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97, CE-PWR NA Integrity SECY 88-272, GL 85-02 (No requirements)

A-5 B&W Steam Generator NUREG-0844, SECY 86-97, B&W-PWR NA Tube Integrity SECY 88-272, GL 85-02 (No requirements)

A-6 Mark I Containment NUREG-0408 Mark 1-BWR NA

• LEGEND:

C - NECESSARY CHANGES COMPLETE NC - NO PHYSICAL CHANGES NECESSARY NA - NOT APPLICABLE I - NECESSARY CHANGES INCOMPLETI;:

E - EVALUATING IF ACTIONS REQUIRED

ATTACHMENT 2 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-7/ Mark I Long-Term Program NUREG-0661, Mark 1-BWR NA D-01 NUREG-0661 Suppl. 1, GL 79-57 A-8 Mark II Containment NUREG-0808, Mark 11-BWR NA Pool Dynamic Loads NUREG-0487 Suppl. 1/2, NUREG-0802, SRP 6.2.1.1C, GDC16 A-9/ Anticipated Transients NUREG-0460 Vol. 4, All C 5/26/88 SER for AMSAC MPA A-20 Without Scram 10 CFR 50.62 design. Implemented on Units 1 and 2 on 7/8/89 and 5/4/89, respectively.

A-10/ BWR Feedwater Nozzle NUREG-0619, BWR NA MPA 8-25 Cracking Letter from DG Eisenhut dated 11/13/80, GL 81-11 A-11 Reactor Vessel Material NUREG-0744 .Rev. 1, All NA 50 ft lb for 40 year OL.

Toughness 10 CFR 50.60, 82-26 A-12 Fracture Toughness of Steam Generator and NUREG-0577 Rev. 1, SRP 5.3.4 Revision PWR NA Resolution applies only to CP issued after 10/83. No e

Reactor Coolant Pump backfit requirements.

Supports Deletion of min/max temperature limits acceptable in accordance with NUREG-0577 - 6/7/84 SER -

Amendments 58/40.

ATIACHMENT 2 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-17 Systems Interactions Ur: De Young to All Internal flooding aspect will licensees - 9/72, be addressed in IP Es. Per our NUREG-1174, NUREG- letter 89-654, 10/30/89, IPE 1229, NUREG/CR-3922, to NRC in 12/91. USI A-46 NUREG/CR-4261, NUREG/ addresses seismic aspect.

CR-4470, GL 89-18 USI A-44 and Gl-128 address A-24/ Qualification of Class (No requirements)

NUREG-0588 Rev. 1, All C electrical aspect.

12/11/84 SER. NRC letter, e

MPA B-60 1E Safety-Related SRP3.11, dated 2/16/88. NRC Equipment 10 CFR 50.49, Inspection Report 50-338, GL 82-09, GL 84-24, 339/88-20, 8/2/88, GL 85-15 closed issue.

A-26/ Reactor Vessel Pressure DOR Letters to PWR C NAPS 1 - 12/28/79 SER, MPA B-04 Transient Protection Licensees 8/76, Amendment No. 16.

NU REG-0224, NAPS 2 - SER (NUREG-0053)

NU REG-0371, Supplement 10, 4/80.

SRP 5.2, GL 88-11 A-31 Residual Heat Removal NUREG-0606, All OLs After NAPS 1 - NA NAPS 2 - SER (NUREG-0053)

Shutdown Requirements RG1.113, 01/79 NAPS2-NC Supplements 10 (4/80) and RG 1.139, SRP 5.4.7 11 (8/80).

A-36/

MPA C-10, C-15 Control of Heavy Loads Near Spent Fuel NUREG-0612, SRP 9.1.5, GL 81-07, GL 83-42, All C 5/25/84 SER. Ongoing program self-assessment to identify and resolve e

GL 85-11, deficiencies, which are Letter from DG being addressed separate Eisenhut dated from this generic activity.

12/22/80 A-39 Determination of SRV NUREG-0802, BWR NA Pool Dynamic Loads NUREG-0763, NUREG-0783, and Pressure Transients NUREG-0802, NUREG-0661, SRP 6.2.1.1.C ATTACHMENT 2 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-40 Seismic Design SRP Revisions, NUREG/ All NA Refer to A-46.

Criteria CR-4776, NUREG/CR-0054, Member of SQUG.

NUREG/CR-3480, NUREG/

CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776, NUREG/CR-3805, NUREG/CR-5347, NUREG/CR-3509 A-42/ Pipe Cracks in Boiling NUREG-0313 Rev. 1, BWR NA MPA B-05 Water Reactors NUREG-0313 Rev. 2, GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All NC SER (NUREG-0053)

Sump Performance NUREG-0869 Rev. 1, Supplements 8 (12/77)

NUREG-0897, RG 1.82 and 10 (4/80).

(Rev. 0), SAP 6.2.2, GL 85-22 (No requirements)

A-44 Station Blackout RG 1.155, All Refer to our letters88-414, NUREG-1032, 4/17/89 and 88-414A, NUREG-1109, 4/20/89. Completion of 10 CFR 50.63 proposed mods 2 years after NRG notification per A-45 Shutdown Decay Heat SECY 88-260, All 10 CFR 50.63(C)(3).

Will be addressed in IPEs.

e Removal Requirements NUREG-1289, Per our letter 89-654, NUREG/CR-5230, 10/30/89, IPEs to NRG in SECY 88-260 12/91.

(No requirements)

A-46 Seismic Qualification NUREG-1030, All Refer to our letter 88-514, of Equipment in NUREG-1211, 10/7/88. Seismic plant Operating Plants GL 87-02, GL 87-03 walkdowns scheduled for end of second outage after 12/31/89 - current forecast for Units 1 and 2 is Fall 1993 and Spring 1992, respectively.

ATTACHMENT 2 (Cont'd)

USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE* REMARKS A-47 Safety Implication NUREG-1217, All E GL 89-19 response of Control Systems NUREG-1218, due 3/19/90.

GL 89-19 A-48 Hydrogen Control 10 CFR 50.44, All, except NA Also not applicable Measures and Effects SECY 89-122 PWRswith to subatmospheric of Hydrogen Burns on Safety Equipment large dry containments containments.

e A-49/ Pressurized Thermal AG 1.154, RG 1.99, PWR NC 5/29/87 SER. Updated MPAA-21 Shock SECY 82-465, assessment of projected SECY 83-288, values of RT-PTS required SECY 81-687, by 10 CFR 50.61.

10 CFR 50.61, GL 88-11 e