ML19332D467

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Responds to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. Status of USIs Encl
ML19332D467
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 11/27/1989
From: Rhodes F
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR ET-89-0102, ET-89-102, GL-89-21, NUDOCS 8912040006
Download: ML19332D467 (5)
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W$LF CREEK 6

NUCLEAR OPERATING CORPORATION a.

r Fonest T. Rhodes

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November 27, 1989 ET 89-0102

- U. S. Nuclear Regulatory Coennission ATTN:

Document Control Desk

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Mail-Station Pl-137

--Washington, D. C.

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Subjects-Docket No. 50-482:. Response to Generic Letter 89-21,

' Request for Information.Concerning Status.of Implemen-tation of Unresolved Safety Issue (USI) Requirements' Gentlemen:-

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The purpose of this letter is to provide Wolf Creek Nuclear Operating Corporation's (WCNOC) response -to Generic Letter 89-21,

' Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements *. The. Generic Letter requests WCNOC to review and. report the status of' implementation of USIs-for which a final technical resolution

~has been achieved and which are applicable to Wolf Creek Generating Station (WCGS).- from the= Generic Letter has' been utilized, in accordance with the instructions provided,- and is provided as an attachment p

-to-this letter.

L The status provided in the attachment is based on a review of applicable generic ~ letters, NUREG documents, NRC Safety Evaluation Report for WCGS (NUREG-0881) its supplements and other correspondence between the NRC and the WCGS' Operating Agent.

1 If you have any questions concerning this matter, please contact me or l

_Mr. O. L. Maynard of my staff.

Very truly yours.

M4s n

Forrest T. Rhodes Vice President Engineering & Technical Services FTR/aem Attachment cc:

B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a 8912040006 891127 p

PDR fiDOC f 05000482 P

FDC I

P.O. Box 411/ Burhngton, KS 66839 / Phone; (316) 364-8831 An Equal opportunny Employer MF/>CVET

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Attachment to ET 89-0102 Page 1 of 4 e

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TABLE 1.

W5tESOLVED SAFETY ISSIES FGt WlICH A FINAL TECIMICAL RESOLUTIGI HAS BEEN ACHIEVED

  • i USI/WA REF. DOCIDEllT/ -

IItBBER TITLE GEIERIC LETTER APPLICABILITY STATUS /DATE*

ItDWIRKS A-1 Water Hamner SECY 84-119 All C-9/84 NUREG-0881 NUREG-0927, Rev. 1 NUREG-0881, Supp. 5 NUREG-0993, Rev. 1 NRC I.R. 84-27.

S/G Water W r NUREG-0737 Item test canpleted 9/84.

I.A.2.3 NRC I.R. 84-49 closes SER Open SRP Revisions Item 84-00-55.

A-2/

Asymmetric Blowdown NUREG-0609 PWR C-3/85 NUREG-0881, Supp. 5 Section 3.6.1.1 MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Coolant Systems A-3 Westinghouse Steam SECY 88-272 W-PWR NC NUREG-0881 and 10GJIRC 85-158 (6/14/85)

Generator Tube Integrity SECY 86-97 i

NUREG-0844 GL 85-02 i

(No Requirements)

I A-4 CE Steam Generator Tube SET 88-272 CE-PWR NA Integrity SET 86-97 NUREG-0844 (No Requirements)

A-5 B&W Steam Generator SECY 88-272 B&W-PWR NA Tube Integrity SECY 86-97 NUREG-0844 (No Requirements)

  • C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE j

E - EVALUATING ACTIONS REQUIRED

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Attcchment.to ET 89-0102

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Pags 2 of 4~

USI/WA REF. DOCtNUIT/

NtNEER TITLE GEIERIC LETTER APPLICABILITY

- STATUS DATE*

IIDWWIKS

_y A-6 Mark I Short-Term NUREG-0408

. Mark I-BWR NA~

Program A-7/

Mark I Long-Term NUREG-0661 Mark I-BWR NA D-01 Program NUREG 0661, Supp. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR NA' Pool Dynamic Loads NUREG-0487, Supp. 1/2 NUREG-0802 SRP 6.2.1.1C GDC 16 A-9 Anticipated Transients NUREG-0460. Vol. 4 All C-12/88

.NRC letter dated 12/6/87 issued SER on.

Without Scram 10 CFR 50.62 design. PMt 01858 installed AMSAC.

NRC I.R. 88-34 and 88-41 reviewed implementation.

A-10/

BWR Feedwater Nozzle NUREG-0619 BWR NA MPA B-25 Cracking Letter frcun DG Eisenhut dated 11/30/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All NC NUR M-0881 Supp. 5-'

Toughness 10 CFR 50.60/

82-26 A-12 Fracture Toughness of NUREG-0577.-Rev. 1 PWR NA NUREG-0881, Supp. 5 Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports A-17 Systems Interaction Ltr: DeYoung to All NC NUREG-0881. Internal Flooding to.

licensees - 9/72, be addressed in the IPE (G.L. 88-20).

NURG-1174. NUREG-Letter dated 10/31/89 indicates IPE 1229 NUREG/CR-3922, will be completed 9/92.

NUREG/CR-4261, NUREG/

CR-4470, GL 89-18 (No Requirements) 4 m

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H Atts.chment to ET 89-0102 e

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'USI/fFA REF. D00tBEllT/

IIINEER TITLE GEIERIC LETTER APPLICABILITY STATUS DATE*

RBIRRKS i

A-24/

Qualification of Class NUREG-0588, Rev. 1 All C-11/85 License Condition'2.C(4). SIJEtC 85 MPA B-60 IE Safety-Related SRP 3.11 (11/29/85) and NRC letter dated 3/17/86 l

Equipnent 10 CFR 50.49 closes License Condition. NRC I.R.~87-24 l

GL 82-09, GL 84-24 GL 85-15 A-26/

Reactor Vessel Pressure DOR Letters to PWR C-12/86..

License Condition 2.C(13). NRC letter MPA B-04 Transient Protection licensees 8/76' dated 10/14/86 accepts proposed design.-

NUREG-0224 PPEL implemented during first ' refueling..

NUREG-0371 NRC I.R. 87-18 reviewed implementation of.

SRP 5.2 USI A-26 GL 88-11 A-31 Residual Heat Removal NUREG-0606 All OLs After NC NUREG-0881, Section 5.4.3' Shutdown Requirements RG 1.113, 01/79.

RG 1.139 SRP 5.4.7 A-36/

Control of Heavy Loads NUREG-0612 All C-3/85 NUREG-0881 Supp. 5. Section 9.1.4.

C-10, Near Spent Fuel SRP-9.1.5 SER Open Item 84-00-132 closed in NRC C-25 GL 81-07, GL 83-42, I.R. 85-04.

GL 85-11 Letter frce DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR NA Pool Dynamic Loads NUREGs-0763, 0783, 0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/

All C-9/89 NUREG-0881. NUREG-1233. NRC letter.

Criteri a CR-4776, NUREG/CR-0054, dated 3/25/89 and ET 89-0076 (9/22/89).

NUREG/CR-3480 NUREG/

CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CP-3805 NUREG/CR-5349 NUREG/CR-3509 W

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" Attachment to ET 89-0102 Pcge 4 of 4.

USI/WA

~ REF. DOCINENT/

NtsBER TITLE GEIERIC LETTER APPLICABItITY STATUS DATE*

RDMAKS M

l A-42 Pipe Cracks in Bolling NUREG-0313, Rev. 1 BWR NA t

MPA B-05 Water Reactors NUR E-0313. Rev. 2 l

GL 81-03, GL 88-01 l

A-43 Containment Emergency NUREG-0510.-

All C-1/85 NUREG-0881, SER Open Item 84-00-56 l

Sump Performance' NUREG 0869, Rev. 1

. closed in NRC I.R. 84-49.

l NUREG-0897, RG 1.82 (Rev. 0), SRP 6.2.2 GL 85-22 l

No Requirements A-44 Station Blackout RG 1.155 All Evaluation C-4/89 NO 89-0072 (4/17/89)

NUREG-1032 Procedures I-10/91 Procedure revisions to be c e pleted' NUREG-1109 6 months after NRR acce s SBO 10 CFR 50.63 evaluation. Current s ule is' for NRR to issue SER 4/91.

A-45 Shutdown Decay Heat NUREG-1289 All NC NURE-0881.

Subsumed into the IPE Removal Requirements NUREG/CR-5230 (Generic letter 88-20). Ietter SECY 88-260 dated 10/31/89 indicates-IPE will' (No Requirements) be completed 9/92.

A-46 Seismic Qualification NUREG-1030 All NA NUREG-0881, Supp. 5 of Equipnent in NUREG-1211/

Operating Plants GL 87-02, GL 87-03 A-47 Safety Implication NUREG-1217, NUREG-All E-3/90 NUREG-0881. Generic Letter 89-19.

of Control Systems 1218 GL 89-19 A-48 Hydrogen Control 10 CER 50.44 All, except NA NUREG-0881, Supp. 5 Measures and Effects SECY 89-122 PWRs with of Hydrogen Burns large dry containments A-49 Pressurized Thermal RGs 1.154, 1.99 PWR C-11/88 NUREG-0881 Supp. 5 KMIJIRC 86-015 Shock SECY 82-465 (1/23/86) and MM 88-0290 (11/7/88).

SEX:Y 83-288 SECY 81-687

.10 CFR 50.61/

GL 88-11 4

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