ML19353B188

Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Implementation Considered Complete Where Activities Performed to Satify Assumptions Made in NRC Technical Resolution of Particular USI

ML19353B188
Person / Time
Site:	South Texas
Issue date:	12/04/1989
From:	Mcburnett M HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR GL-89-21, ST-HL-AE-3302, NUDOCS 8912120141
Download: ML19353B188 (6)

Text

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.y- 't The Light P.O. Box 1700 llouston, Houston Lighting & Power -. - ~- -- - -- - -~ 'li xas 77001 - - - -(713)

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~ ~ ~ 9211 December 4, 1989 ST-HL-AE 3302 >

File No.: G03.08 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Units 1 and 2 Docket Nes. STN50-498, STN 50-499 Status of-Implementation of Unresolved Safety Issue Recuirements (Generic Letter 89-021) s

Reference:

Letter from James G. Partlow (NRC) to G. E. Vaugha (HL&P) dated October 19, 1989-Houston Lighting & Power Company (HL&P) has reviewed the request in the referenced letter for the status of implementation of unresolved safety issue

-(USI) requirements. An extension of the original 30 day response time was granted November 30, 1989 by Messrs. D. M. Ilunnicutt of NRC Region IV and r

G. F.' Dick NRC llQ. As requested, the list of items provided by your letter has been annotated (C-complete, NC no changes necessary, NA-not applicable or I-incomplete) and-is attached. Implementation is considered complete where activities have been performed to satisfy the requirements (or assumptions) made in the staff's technical resolution of the particular USI.

If you should have any questions on this matter, please contact Mr. A. W. liarrison at 512-972-7298.

k

. A. McBurnett f@

Manager Support Licensing MAM/SDP/n1

Attachment:

Annotated Status of Unresolved Safety Issue Requirements (Generic Letter 89-021) 8912120141 891204 PDR ADOCK 05000498 i- P PDC A1/013.N10 A Subsidiary of Ilouston Industries incorporated  %

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, Houston Lighting & Power Company ST.HL AE- 3302

- South Texas Project Electric Generating Station File No.: G03.08 Page'2

• cc:

Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory. Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 ,

Houston, TX 77001 4

George Dick, Project Manager

U.S. Nuclear Regulatory Commission INPO

-Washington, DC. 20555 ~ Records Center 1100 circle ~75 Parkway >

J. I. Tapia Atlanta, CA 30339 3064 Senior Resident Inspector c/o V. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission .

50 Bellport Lane P. O. Box 910 .

Bellport, NY 11713 Bay City,:TX 77414 ,

D. K. Lacker  !

J. R. Newman, Esquire Bureau of Radiation Control Newman'& Holt:inger, P.C. Texas Department of Health 1615 L' Street, N.W. .1100 Vast.49th Street Washington,-DC 20036' Austin, TX 78704  !

R. L. Range /R'. P. Verret Central Power & Light Company P. O. Box 2121 1

, . Corpus Christi,;TX 78403 J. C..Lanier

. Director of Generationc k e City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 A

R. J. Costello/M. T. Hardt City Public Service Board

-P. 0. Box 1771 San Antonio, TX 78296 Revised 11/15/89 L4/NRC/

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- ATTACHMENr ' 1 z to I ST-HL- AE-33021 ,

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Prge:1 of'4^

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y UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS SEEN ACHIEVED

USI/MPA _

REMARKS i NUMBER TITLE- REF. DOCUMENT APPLICABILITY STATUS /DATE*'

I A-1 Water Hammer SECY 84-119- All. C-2/88 -See NUREG-0781, and- "

'NUREG-09?7, Rev. 1  : letter ST-HL-AE--249S

'NUREG-0993, Rev. I dated 2/5/88 NUREG-0737 Item

.I.A.2.3 .

l SRP revisions Asyuunetric Blowdown NUREG-0609 PWR C-7/87 See NUREG-0781-.

A-2/

! MPA D-10 Loads on' Reactor Primary GL 84-04, GDC-4

' Coolant Systems Westinghouse Steam NUREG-0844 -W-PWR C-6/85 See-letter ST-HL-AE-1285 :

A-3 Generator Tube Integrity SECY 86-97 dated 6/17/85- -

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'SECY 88-772 3

! GL 85-02 -

I (No requirements) .

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A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR N/A Integrity . SECY 88-272 '

GL 85-02 I ~(No requirements)

A-5 S&W Steam Generator NUREG-0844, SECY 86-97 88W-PWR N/A Tube Integrity SECY 88-272

. GL 85-02 I

(No Requirements) l E

'A-6 Mark I Containment NUREG-0408 Mark ~I-8WR N/A i Short-Terin Program

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

4 I - INCOMPLETE E - EVALUATING ACTIONS REQUIRED t

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ATTAQh NT 1 to ST-HL-AE-3302

• Page 2.of 4 7-USI/MPA REMARK 5 TTTLE REF. 110CUPENT . APPLICA31!T'". SJATDs/DATE*

NUMBER MUREG-0661 Marir I-9WR gjg A-7/ Mark I Long-Tern NUREG-0661 Sepp 1. I D-01 Program GL 79-57 NUREG-0808 Mark Il-BidR N//.

A-8 Mark II Containment NUREG-0487, Suppl. 1/2 Pool Dynamic Loads NUREG-0802

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SPP 6.2.1.1C

' GDC 16 NUREG-0460. Vol. 4 ATI c-10/89 see letter ST-HL-AE-3253 A-9 Anticipated Transients dated 10/11/89 Without Scram 10 CFR 50.62 .

NUREG-0619 BW gf4

! A-10/ BWR Feedwater Nozzle MPA B-25 Cracking ..

Letter from DG Eisenhut l

i dated 11/13/80 ,

GL 81-11 1 NUREG-0744. wev. I All N/C A-11 Reactor Vessel Material Touchness 10 CFR 50.60/

P2-26 o

NUREG-0577, Pev. 1 PW8 N/C i

A-12 Fracture Toughness of Steam Generator and SRP Revision i

Reactor Coolant Pump 5.3.4 I Supports Ltr: DeYoung to A33 gfc I

A-17 Systems Interactions licensees - 9/77 NUREC-II74. NL9EG-1229. NUREG/CR-3922 NUREG/CR e?6I, NUREG/

CR-4470, GL 89-18

• (No requirveents) see NifREG-07st, MUREG-0588. Nev. 1 All c-7/87 A-24/ Ovalification of Class supp1 4-(Unit U PPA B-60 IE Safety-Nelated SRP 3.11 10 CFR 50.49 suppl 6-(Unit 2)

Equipment GL 82-09 GL 84-24 ra as-is

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ATTAcimENT 1 to ST-HL-AE-3302 '

rune 3 or_4 ,

USI/MPA R9stRF.

NUNRER TITLE REF. 00CtmENT A*PliCABILITY STATUS /DATE*

- A-26/ Reactor Vessel Pressure DOP Letters to PWR N/c MPA B-04 Transient Protection Licensees 8/76 NUREG-0224 NUREG-0371 SRP 5.2 GL 88-11 A-31 Pesidual Heat Removal NUREG-0606 All Ots After N/c Shutdown Requirements RG 1.113, ,'

01/79.

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

C-10, Near Spent Fuel -

SRP 9.1.5 C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated .,

12/22/80 NUREG-0M2 BWR 3f3 A-3? Determination of SRV Pool Dynamic Loads NUREGs-0763,0783,0002 '

and Pressure Transients NUREG-0661 SPP 6.2.1.1.C .

SRP Revisfons. NUREG/ All N/c A-40 Seisaic Design Criteria CR-4776. NUREG/CR-0054, NUREG/CR-3480. NUREG/

CR-1582. NUREG/CR-1161 NUREG-1233 NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 .

NOREG/CR-3509 Pipe Cracks in Bollfeg NUREG-0313. Rev. I ' 8WR gfg i A-42/ ~

MPA B-05 Water Rektors NUREG-0313. Rev. 2 l

GL 81-03 EL 88-01 t

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ATTACHMENT 1 to ST-IIL-AE-3302 -

1 Page 4 of 4 ,

USI/ PPA

_NU"BER TITLE REF. DOCUMENT APPLICAB!t.ITY STATUS /DATE* REMA'KS A-43 Con'ainment Emergency NUREG-0510.. All Sump Performance C-4/89 See. letter ST-HL-AE-3061 dated MU#EG-0869. Rev. 1 04/12/89 Nt/#EG-0897. R.G.1.8?

(Pev. 0). SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout PG 1.155 All MtrREG-1032 I-12/89 See letter ST-HL-AE-3045 dated MU#EG-1109 04/17/89. This letter is 10 CFR 50.63 '

under NRC review.

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A-45 Shutdown Decay Heat SECY AP-260 Removal Requirements NUREG-1289 "? All I-8/92 The DHR requirements have been NUREG/CR-5230 incorporated into the STP SECY 88-260 design. See letter ST-HL.AE-(No reqvfrements) 3244 dated 09/29/89 for the A-46 IPE co71etion schedule.

Seismic Qualificatfon NUREG-lo?O 411 of Equipment in N/A NUREG-1211/

Operating Plants GL 87-02. GL M7-03 A-47 Sa fety Impi f ca t f an NUREG-1217. Mtprg. A11 o' Control Systems I?In N/C HL&P is preparing a response GL 89-19 to GL 89-19. 'This subject is already addressed in the A-4C Hydrogen Control 10 CF# 50.44 STP FSAR.

A11. except Measures and E'fects SECY 89-177 3f4 of Hydrogen Burns PWRs with on Safetv Equfrment isrge dry containments A-49 Pressurized Thermal RGs 1.154. 1.99 PWt Fbock N/C SECY 82-465 SECY R3-288 SECY 81-687 10 CFR 50.61/

i c PA-11

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