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| issue date = 11/29/1989
| issue date = 11/29/1989
| title = 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
| title = 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
| author name = STEWART W L
| author name = Stewart W
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:*. e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 29, 1989 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:*.                     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:
Document Control Desk Washington, D. C. 20555 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.
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 Serial No. NUCGL:vlh Docket Nos. License Nos. 89-770 R1 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 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.
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  
Should you have any questions regarding this information, please contact us.
-Nuclear Attachments 8912060448 891129 ,, PDR ADOCK 05000280 1' ' p PNU I 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 e 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 SECY 84-119, NUREG-0927 Rev. 1, NUREG-0993 Rev. 1, NUREG-0737 Item I.A.2.3,**
Very truly yours,
SRP revisions A-1 Water Hammer A-2/ NUREG-0609, MPA D-10 Asymmetric Blowdown Loads on Reactor Primary Coolant Systems GL 84-04, GDC-4 A-3 A-4 A-5 A-6 A-7/ D-01 Westinghouse Steam Generator Tube Integrity CE Steam Generator Tube Integrity B&W Steam Generator Tube Integrity Mark I Containment Mark I Long-Term Program
          . Stewart e ior Vice President - Nuclear Attachments 8912060448 891129         ,,
* LEGEND: NUREG-0844, SECY 86-97, SECY 88-272, GL 85-02 (No requirements)
PDR ADOCK 05000280 1'
NUREG-0844, SECY 86-97, SECY 88-272, GL 85-02 (No requirements)
'   p                   PNU   I
NUREG-0844, SECY 86-97, SECY 88-272, GL 85-02 (No requirements)
 
NUREG-0408 NUREG-0661, NUREG-0661 Suppl. 1, GL 79-57 C -NECESSARY CHANGES COMPLETE NC -NO PHYSICAL CHANGES NECESSARY NA -NOT APPLICABLE I -NECESSARY CHANGES INCOMPLETE E -EVALUATING IF ACTIONS REQUIRED APPLICABILITY STATUS/DATE*
e cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
All PWR W-PWR CE-PWR B&W-PWR Mark 1-BWR Mark 1-BWR NC NC NC NA NA NA NA REMARKS **Full member of National Academy for Nuclear Training -INPO accredited.
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
6/16/86 SER -Amendment Nos. 108/108. Refer to our letter 85-300, 6/17/85. e I ATTACHMENT 1 (Cont'd) . I 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, e 7/31/87, installation planned for refueling outage at end of Cycle 10 -current forecast for Units 1 and 2 is Fall 1990 and Spring 1991, respectively.
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 -
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
NUREG-0993 Rev. 1,                                   INPO accredited.
-submittal forecast 12/15/89.
NUREG-0737 Item I.A.2.3,**
Unit 2 -> 50 ft lb for 40 year OL. Unit 1 -18 EFPY with e program to evaluate flux reduction.
A-2/           Asymmetric Blowdown SRP revisions NUREG-0609,                   PWR            NC      6/16/86 SER - Amendment e
Participation in 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.
MPA D-10       Loads on Reactor Primary GL 84-04, GDC-4                                       Nos. 108/108.
Supports ATIACHMENT 1 (Cont'd) USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE*
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.
REMARKS A-17 Systems Interactions Ur: De Young to All Internal flooding aspect will licensees
SECY 88-272, GL 85-02 (No requirements)
-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 (No requirements) address electrical aspect. e A-24/ Qualification of Class NUREG-0588 Rev. 1, A II C 3/12/88 SER for EQ program. 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, Near Spent Fuel SRP 9.1.5, program self-assessment e C-15 GL 81-07, GL 83-42, to identify and resolve GL 85-11, deficiencies, which are Letter from DG being addressed separate Eisenhut dated from this generic activity.
A-4            CE Steam Generator Tube  NUREG-0844, SECY 86-97,     CE-PWR          NA Integrity                SECY 88-272, GL 85-02 (No requirements)
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*
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)
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-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
A-44 Station Blackout RG 1.155, All Refer to our letters 88-414, 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 1 OCFR50.63(C)(3).
* LEGEND:
e A-45 Shutdown Decay Heat SECY 88-260, All Will be addressed in IPEs. 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)
C - NECESSARY CHANGES COMPLETE NC   - NO PHYSICAL CHANGES NECESSARY NA   - NOT APPLICABLE I - NECESSARY CHANGES INCOMPLETE E - EVALUATING IF ACTIONS REQUIRED
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*
ATTACHMENT 1 (Cont'd)
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.
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
on Safety Equipment containments e A-49/ Pressurized Thermal RG 1.154, RG 1.99, PWR NC 12/7/87 SER. Updated 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 A-1 Water Hammer SECY 84-119, NUREG-0927 Rev. 1, NUREG-0993 Rev. 1, NUREG-0737 Item I.A.2.3, SRP revisions A-2/ Asymmetric Blowdown NUREG-0609, MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 A-3 A-4 A-5 A-6 Coolant Systems Westinghouse Steam NUREG-0844, Generator Tube Integrity SECY 86-97, SECY 88-272, GL 85-02 (No requirements)
Cycle 10 - current forecast for Units 1 and 2 is Fall 1990 and Spring 1991, respectively.
CE Steam Generator Tube NUREG-0844, SECY 86-97, Integrity SECY 88-272, GL 85-02 (No requirements)
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 -
B& W Steam Generator NUREG-0844, SECY 86-97, Tube Integrity SECY 88-272, GL 85-02 (No requirements)
submittal forecast 12/15/89.
Mark I Containment NUREG-0408
Unit 2 - > 50 ft lb for 40 year OL. Unit 1 - 18 EFPY with program to evaluate flux reduction. Participation in e
* LEGEND: C -NECESSARY CHANGES COMPLETE NC -NO PHYSICAL CHANGES NECESSARY NA -NOT APPLICABLE I -NECESSARY CHANGES INCOMPLETI;:
BWOG Materials Group.
E -EVALUATING IF ACTIONS REQUIRED APPLICABILITY STATUS/DATE*
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.
REMARKS All NC 6/76 SER, NUREG-0053.
Supports ATIACHMENT 1 (Cont'd)
Full member of National Academy for Nuclear Training -INPO accredited.
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)
e PWR NC 12/15/88 SER -Amendment Nos. 107/93. ' W-PWR NC Refer to our letter 85-300, 6/17 /85. 10/23/87 and 12/11 /87 SE Rs for SGTR. CE-PWR NA B&W-PWR NA Mark 1-BWR NA ATTACHMENT 2 (Cont'd) USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE*
NUREG-0588 Rev. 1,               A II          C address electrical aspect.
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.
3/12/88 SER for EQ program.
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 NUREG-0577 Rev. 1, PWR NA Resolution applies only to e Steam Generator and SRP 5.3.4 Revision CP issued after 10/83. No Reactor Coolant Pump backfit requirements.
e MPA B-60  1 E Safety-Related      SRP3.11,                                               NRG letter, dated 2/16/88.
Supports Deletion of min/max temperature limits acceptable in accordance with NUREG-0577 -6/7/84 SER -Amendments 58/40.
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 -
USI/MPA NUMBER A-17 A-24/ MPA B-60 A-26/ MPA B-04 A-31 A-36/ MPA C-10, C-15 A-39 TITLE Systems Interactions Qualification of Class 1 E Safety-Related Equipment Reactor Vessel Pressure Transient Protection Residual Heat Removal Shutdown Requirements Control of Heavy Loads Near Spent Fuel Determination of SRV Pool Dynamic Loads and Pressure Transients ATIACHMENT 2 (Cont'd) REF. DOCUMENT Ur: De Young to licensees
MPA B-04  Transient Protection    Licensees 8/76,                                       Amendment Nos. 56/55.
-9/72, NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/CR-4261, NUREG/ CR-4470, GL 89-18 (No requirements)
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
NUREG-0588 Rev. 1, SRP3.11, 10 CFR 50.49, GL 82-09, GL 84-24, GL 85-15 DOR Letters to Licensees 8/76, NU REG-0224, NU REG-0371, SRP 5.2, GL 88-11 NUREG-0606, RG1.113, RG 1.139, SRP 5.4.7 NUREG-0612, SRP 9.1.5, GL 81-07, GL 83-42, GL 85-11, Letter from DG Eisenhut dated 12/22/80 NUREG-0802, NUREG-0763, NUREG-0783, NUREG-0802, NUREG-0661, SRP 6.2.1.1.C APPLICABILITY All All PWR All OLs After 01/79 All BWR STATUS/DATE*
Letter from DG                                        being addressed separate Eisenhut dated                                        from this generic activity.
REMARKS Internal flooding aspect will be addressed in IP Es. Per our letter 89-654, 10/30/89, IPE to NRC in 12/91. USI A-46 addresses seismic aspect. USI A-44 and Gl-128 address electrical aspect. e C 12/11/84 SER. NRC letter, dated 2/16/88. NRC Inspection Report 50-338, 339/88-20, 8/2/88, closed issue. C NAPS 1 -12/28/79 SER, Amendment No. 16. NAPS 2 -SER (NUREG-0053)
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)
Supplement 10, 4/80. NAPS 1 -NA NAPS 2 -SER (NUREG-0053)
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.
NAPS2-NC Supplements 10 (4/80) and 11 (8/80). C 5/25/84 SER. Ongoing e program self-assessment to identify and resolve deficiencies, which are being addressed separate from this generic activity.
NUREG/CR-3480, NUREG/
NA ATTACHMENT 2 (Cont'd) USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE*
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.
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)
NUREG-0897, RG 1.82 (Rev. 0), SRP 6.2.2, GL 85-22 (No requirements)
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 letters 88-414, 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).
A-44 Station Blackout RG 1.155, All Refer to our letters 88-414, 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 10 CFR 50.63(C)(3).
Will be addressed in IPEs.
e A-45 Shutdown Decay Heat SECY 88-260, All Will be addressed in IPEs. 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)
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.
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.
(No requirements)
ATTACHMENT 2 (Cont'd) USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS/DATE*
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 -
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 large dry containments.
current forecast for Units 1 and 2 is Spring 1992 and Winter 1993, respectively.
e on Safety Equipment containments 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 }}
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 letters 88-414, 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
                                                  }}

Latest revision as of 21:53, 2 February 2020

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)
v • d • e


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

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