ML19353A864

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Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. Issue for Which Final Technical Resolution Achieved Encl
ML19353A864
Person / Time
Site: Beaver Valley
Issue date: 11/27/1989
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8912080001
Download: ML19353A864 (5)


Text

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'$"EMYuoc4..,c,ou, iatai e43-uss November 27, 1989

'U. S.: Nuclear Regulatory Commission

! Attn: Document Control Desk Washington,.DC 20555

Reference:

. Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Generic Letter 89-21  ;

Gentlemen:

Attached is our. reply to Generic. Letter 89-21 " Request for Information Concerning Status of . Implementation of- Unresolved Safety ~ Issue. (USI) Requirements" which provides a. marked-up copy of Enclosure I :of Generic Letter 89-21. The attachment provides

-the- status of implementation of USIs at- Beaver Valley Power

< Station Units 1 and 2. This information was compiled based on -

, input 1 received from our. Project Manager, Mr. Peter S. Tam, and review of our records on the subject USIs.

If you have any questions concerning this response, please contact my office.

Vary truly yours, J. D. Sieber N Vice President Nuclear Group J Attachments cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator

, Mr. P. Tam, Sr. Project Manager

. .Mr . R. Saunders (VEPCO) m g2cggiMhp

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- p LENCLOSURET 1-UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVE 0' -

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NUMBER TITLE REF. DOCUMENT 2 APPLICABILITY: .- STATUS /DATE* . REMARKS A-I Water Hammer SECY 84-119 .

All .BV-1 c' 2/79 Letter..A. Schwencher to NUREG-0927,'Rev.-1 NUREG-0993,:Rev. 1 C.::N.'Dunn dated 2/12/79 NUREG-0737 Item BV C 5/87 NUREG-1057 I.A.?.3 SRP revisions A-2/ Asymmetric Riowdown NUREG-0609 MPA D-10 Loads on Reactor Primary .GL'84-04, GDC-4 PWR BV-1 C- 6/8' ' . Letter J. D. Sieber to NRC-Coolant Systems dated 6/12/87 BV-2 C 3/87 NUREG-1057, Supp. 4..

A-3 Westinghouse Steam NUREG-0844 4-PWR 'BV-1 C 1/86 Letter J. J. : Carey to NRC '

Generator Tube Integrity- SECY 86-97.

SECY 88-772 ~

dated 6/14/85 BV-2 C 1987 Letter.J.iJ. Carey to NRC GL 85-02 dated 6/18/85.

(No requirements) Program?

implemented afterffull A-4 power. license.

CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR BV-1 NA Integrity SECY 88-272 BV-2 NA GL 85-02 (No requirements)

A-5 BAW Steam Generator NUREG-0844. SECY 86-97 '88W-PWP BV-1 NA Tube Integrity SECY 88-272 BV-2 ~ NA

E X-6 Mark i Containment NUREG-0408 Park I-BWR BV-1 NA Short-Term Program BV-2 NA o C - COMPLETE NC - NO CHANGFS NECESSARY ~

Nsl - NOT APPLICABLE I - INCOMPLETF F - EVALUATING ACTIONS REQUIRED

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' :. p USI/MPA NLHBER TITLE REF. DOCIFENT APPLICABILITY STATUS /DATE* REMARKS A-7/ Mark I Long-Term NUREG-0661 Mark I-BWR sy-1..NA- - ..

0-01 Program NUREG-0661 Suppl. 1- BV-2 NA

- GL 79-57 -

A-8 Mark II Containment- NUREG-0808 Mark II-BWR BV-1 NA Pool Dynamic loads NUREG-0487, Suppl. 1/2- BV-2 NA NUREG-0802 SRP 6.2.'1.1C GDC 16-V A-9 Anticipated Transients- NUREG-0460, Vol. 4 All BV-1 c; 2/88 Letter P. S. Tam to.

Without Scram 10 CFR 50.62- BV-2 C 5/89 'J. D. Sieber dated 5/31/881 A-10/ BWR Feedwater Nozzle NUREG-0619 BWP BV-1 NA MPA P-75 Cracking Letter-from DG Eisenhut BV-2 NA dated-11/13/80 GL-81-11 A-11 Reactor Vessel Paterial. NUREG-0744, Rev. 1 All 'BV-1 'NC Toughness 10,CFR 50.60/ BV-2 NC

. 8?-26 A-1? fracture Toughness of NUREG-0577, Rev. 1 PWP BV-1 NC' Steam Generator and SRP Revision BV-2: NC Reactor Coolant Pump - 5.3.4 Suppor+s A-17 Systems Interactions Ltr: 'DeYoung to All BV-1 NC-Itcensees - 9/77 BV-2 -NC NUREG-1174, NL' REG ..

1229, NUREG/CR-3922, NUREG/CR 8?61,.NUREG/

CR-4470,'GL 89 (No requirements)

A-?4/ Ocalification of Class NUREG-0588, Rev. 1 .All- .BV-1 -C 11/85 Letter S.A'. Varga to-.

PPA F-60 lE Safety-Related SRP 3.11 .J.J. Carey dated 3/7/85.

Equipwnt 10 CFR 50.49 NRC-Inspection 50-334/86-12

'GL 82-00, Gl; 84-24.. dated 10/31/86 GL 85-15 BV-2. C 5/87- NUREG .1057, Supp 5 Sect.3.1

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NUMBER TITLE REF. DOCUMENT - ' APPLICABILITY' STATUS /DATE+ RFMARES -

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A-26/' Reactor Vessel Pressure DM' Letters to .PWR' BV-1 C 10/85 ~ T.S.' Amend.H96' MPA B-04 Transient Protection -Licensees 8/76- dated 9/6/85-NUREG-0224 BV-2 C 8/87: T.S2 Section 3.4.9.31 NUREG-0371 NUREG-1057,:Section 5.2 SRP 5.2 GL 88-11  ;

A-31 Pesidual Heat Removal NUREG-0606 All OLs After BV-1 NC Shutdown Requirements RG 1.113, 01/79. -BV-2 C- 5/87: - NUREG-1057, Section 5.4.7-

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RG 1.139 SRP 5.4.7 A-36/ Control of Heavy Loads NUREG-0612 All

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BV C :12/84' Letter S.A. Varga to C-10, Near Spent Fuel SRP 9.1.5 J. J. Carey ' dated 12/20/84'-

C-15 GL 82-07, GL 83-42, BV-2 -C 5/87 NUREG-1057, Section 9.1.5.'

GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR .BV-1 .NA Pool Dynamic Loads NUREGs-0763,0783,0802 -BV-2 NA and Pressure Transients NUREG-0661 SPP '6.2.1.1.C.

A-40 Seismic Design SRP Revisions,.NUREG/ All BV-1 NC Criteria CR-4776, NUREG/CR-0054, BV-2 NC .

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 i BV-1 NA-MPA B-05 Water Reactors 'NUREG-0313, Rev. 2 BV-2 .NA GL-81-03, GL 88-01

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NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* REMARKS +

A-43 Containment Emergency 'NUREG-0510; All BV-1 NC Sump Perfomance NUREG-0869,.Rev.:1 BV C- 5/87 - NUREG-1057, Suco.5, NUREG-0897, R.G.I.87: section 6.2.2-(Rev. 0),-SRP 6.2.2' . . ,

GL 85-22 No Requirements, - -

A 44 Station Blackout RG 1.155 All- -BV-1-& -2: I 6/92- Letter J. D.'Sieber to NRC.

NilREG-1032 dated.4/14/89. . Committed to:

NUREG-1109 Alternate AC via-BV-1 6.2 cr ss-tre emergency buses 10 CFRiSO.63 to be implemented'2 years.

A-45 Shutdown Decay Heat SECY 88-260 All gy_1 ye Removal Requirements NUREG-1289 BV-2 ~ NC NUREG/CR-5230l SECY 88-260 (No requirements)

A-46 Seismic Qualification NUREG-10?O All BV-1 I 12/92 Letter J.D. Sieber to"NRC dated 10/7/88. Perform seismic.

of Equipment in NUREG-1211/

BV-2 NC verification walkdown by-end Operating Plants GL 87-02,'GL 87-03 of 2nd refueling af ter NRC ,

issues final safety evaluation of CIP.

A-47 Safety Implication NUREG-1217, NUREG- All 'BV-1 E 3/90 of Cor. trol Systems 1218 BV-2 E 3/90 GL 89-19 A-46 flydrogen Control 10 CFD 50.44' All, er. cept BV-1 NA Measures and Effects SECY 89-I?? PWRs with BV-2 NA of Hydrogen Burns large' dry on Safetv Equipment containments J

A-49 Pressurized Thermal PGs 1.154, 1.99 PWR BV-1 C- - 8/86' Letter NRC-to J. J. Carey; chock SECY H2-465 -

dated 8/11/86' SECY P.3-288- BV-2 C 5/87** Subalt ted ' in fo in FSAR, ~

SECY 81-687 Amend. 17, dated 5/1/87..

~10 CFR 50.61/ Awaiting NRC staff review.

GL 88-11

    • DLC action couplete. . awaiting NRC staff review- ,

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