ML19332E656

Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Action Re USI A-17, Sys Interactions Expected to Be Completed by Oct 1992

ML19332E656
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	11/28/1989
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
TASK-***, TASK-OR GL-89-21, NUDOCS 8912110024
Download: ML19332E656 (9)

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November 28, 1989 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 'I and 2 Braldwood Station Units 1 and 2 Response to Generic letter 89-21 BBC_Doche.t_Hm_50-454 / 455_anL50-456 / 452

Reference:

Generic Letter 89-21 Request for Information Concerning Statut of Implementation of Unresoived Safety Issue (USI) Requirements

Dear Dr. Murley:

Generic letter 89-21 was issued as a part of the NRC's continuing effort to validate staff understanding regarding implementation of unresolved safety issues (USIs). An important aspect of this effort is to ensure-that the Itcensee and the NRC agree on the status of USI resolution implementation at each facility.

This letter presents Commonwealth Edison (Edison's) response to Generic Letter 89-21, for the Byron and Braldwood Stations.

Byron and Brairk:ood stations have reviewed the guidance provided in l

the Generic Letter. The attached of USIs tables (Enclosure 1 from the generic l

letter) have been updated to reflect the current status of USI implementation.

The generic letter's guide for updating USI status was utt11 red for this process. Accordingly, Attachments "A" and "B" of this letter provide the status-of the efforts at Byron and Braidwood Stations, 4

respectively.

Pleae direct any questions regarding this response to this office.

Very truly yours, 4

h (Y

l S.C. Hunsader Nuclear Licensing Administrator F'

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PNU 1.

/sc1:0351T:28 Attachments: A-Byron Station B-Braidwood Station Olf cc:

A.B. Davis-RIII i

'1 4l Resident Inspectors-BY/BH L. 01shan-NRR S. Sands-NRR

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. BYBon STATION ENI WRESOLVED SAFETY ISSUES FOR Ifff08 A FfML TEDEBICAL RESOLUTiflW IWLS BEEN ApffETES USI/MPA litRWER TITLE REF. BRCWENT APPLICABILITY STATUS /ORTE*

RUWIARS t

A-1 Water Hammer SECY 84-119 All c to/s1 3Yaon sER i

IIUREG-0927, Rev.1 yg 13-24 IIURE4-0993. Rev..I j

NUREG-0737 Item i.A.2.3 SIIP revistens i

A-2/

AsymumetrfC Rieudoun NUREG-0609 PWR C UI 3/37 BYaon SER i

MPA D-1H Loads on Reector Primary GL 84-04, GOC-4 v2 11/s6 ssCTIon 3.9.2.4 i

Coolant Systems 1

A-3 Westinghouse Steam IIUREG-0844 W-PWR C UI 6/s5 anC ACCEPTANCE I.YR.7,;

i Generator Tube Integrity SECY 86-97 v2 11/s6 dated s/22/s5 SECY 88-772

. R MM (no regsfrauents)

A-4 CE Steam Generater Tube IIUREG-0044, SECY 85-97 CE-PWR Integrity SECY 88-272

2. 85-02 l

l (IIe requirements)-

i 1

I A-5 88W Steen Generator IIUREA-n844. SECY 86-97 8mi-PNP "A

t i

Tube Integrity SECY 88-272 GL 85-02 l

(IIe %eguirements) i E

l

'K 6 Mart I Contefament IIUREG-0408 Part I-8WR m

Short-Tene Program i

• C - COMPLETE Y

IIC - 100 OWWIGES IIECESSARY NA - ROT APPLICA9tE I - IIICOMP!.ETE i

E - FVALUATING PCTIONS REI)tifilED

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l USI/MPA fMcEP TITLE REF. DOCIMDIT APytICMitITY STAT 115/MTE*

RDWIARS 4

i A-7/

Mark I Long-Ters MUREG-0661 Mark I-ONR nA D-01 Progran NUREG-0661 Seppl. 1 E 79-57 A-8 Mark II Centafament NUREG-0808 Merk II-8tm nA 1

Pool Dynamic Leeds NUREG-0987. Suppl. 1/2 NUREG-0802 i'

SDP 6.2.1.lC GBC 16 2

i r

i A-9 Anticipated Transtants NUREG-0460. Vol. 4 All I U1-3/90 scarnet.s l

Without Scram 10 CFR 50.62 v2-10/90 suuntrrEn 2-15-89 l

A-10/

ONR Feeduster Mozzle NUREG-0619 SNP nA j

]

MPA B-?S Cracking Letter from DG Eisenhut dated 11/13/80 i

E 81-11 A-11 Reactor Vessel Material NUREG-0744. Rev. I All c UI-Io/s4 sYnon ssen #4 Toughness 10 CFR 50.60/

U2-11/86 Pc. 5-3 I

a2-26 l

A-12 Fracture Toughness of NUREG-0577. Rev. I pWP c 2/s2 sYace sEn Steam Generator and SRP Revision c-13 Reactor Coelant Pemy

. 5.3.4 l

i Supports i

i A-17 Systems Interseffens Ltr: BeVeung to All E 10/92 cL 88-20 1lconsees - 9/72 IPE mEsrensE NUREC-1174. NISEG-svanITTED 10/27i05 1229. NURES/CR-3922, i

NURES/CR-4761. NUPEG/

CR-4470. E 89-18 (No iregetruments) 1 A-24/

Qualificatten of Class NUREG-0598, Rev. 1 All c v1 10/s4 synon sEn sECTIOu MPA S-60 IE Safety-Related SRP 3.11 U2 11/s6 3.11 Equipment le CFR 50.49 armoussEn #5 E 82-09. E M-24 ssen #6 E 85-15 5sEn #7 t

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USI/MPA.

WIMRER TITLE REF. SOCWENT APPLICASILITY STATUS /SETE*

1. 9mRR$

i OCR Letters to PWI

.c ul-10/s4-sYnon sEm-A-26/

-Reector Vessel Pressure NPA 8-04 Transfest Protectfen j-Licensees 8/70 U2-11/86 sacTIon 5.2.2.2-NUREG-0224 NUREG-4371 SitP 5.2 ^

i.

GL 88-11 i

S A-31 Resfdual Neat Neuseel NUREG-0606 All Ols After c 2/82 sYnow sEm sacTIon' l

Shutdown Negufm ments NR 1.113, 01/79.

11/8s 5.4.3 WG 1.139 (NATURAI CIRCULATION)

SAP 5.4.7 A-36/

Control of Neevy Loads NUREC-0612 A1)

C-FRASE I i-C-10, Near Spent Fuel SRP 9.1.5 U1-1o/s4-sYaos sEn jl C-15 GL 81-07. E 83-42, U2-11/86' SECTIoK 9.1.5 E 85-11 nYann Ssta f5 Letter from DG c-FHASE II sYRoR SSEa #6 Etsenhet dated.

Pc. 9-1 12/22/80 A-39 Deterefnetten of SpV mmEG-0802 Ole NA l

Pool Dynantc Loads NUREGs-0763,0783,0002 and Pressure Transtents NUREG-0661 l

SPP 5.2.1.1.C t

A-40 Sefsmic Design SRP Revistens, NURES/

All c 2/s2 sYnow sEn Criteria CR-4776. NUREG/CR-0054, c-14 & 15 NUREG/CR-3400, NURES/

CR-1582. NURES/CR-1161,

.NUREG-1233. NUREG-4776 NUREG/CR-3OO5 NUREG/CR-5347 NUREG/CR-3509 A-42/

Pipe Cracks in Sof11n9 mmEG-0313. Rev. 1 SNR NA MPA B-05 Water Reactors NUREG-0313. Rev. 2 Y

E 81-03, E 88-01

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USI/ PPA MSWER

' TITLE REF. OnciperY APPLICA8ILITY STATUS /0 RYE' ROMRRS l

A-43_

Contatenent Emergency NUREG-0510..

All c v1 10/s4 WYnon sam c-15~

Sump Performance NUREG-0859. Nov. 1 U2 11/s6

,a c-16; avaan IWWEG-0897. R.G.1.87 -

sssa #5, rg. 6-4 (Rev. 0). SRP 6.2.2 et 85-22 4

No Neguirenants A-44 Station Blackout' RG 1.155 All I (Implement i nesponse MIREG-1032 year siter nec review)subettted l

NUREG-1109 4/17/s9 10 CFR 50.63 A-45 Shutdown Decay Heat SECY RS-260 A))

E 10/92' Analysis remains Removal Requirements NUREG-1289 to be completed.

i NUREG/CR-5230 cL ss-20/ Irs-SECY 88-260 Resoonse==bettted (Norequirements) 10/27/s9.

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A-46 Sefsofc Quaitffcatf a NUREG-1030 All I~

sgoc previded of Equipuent fn NUREG-1211/

seneric implement-Operetin9 Plants E 87-02. R 87-03 ation, new. O on l

6/o3/ss; sER re-:

l A-47 Safety Inp1fcation NUREG-1217. NUREG-All s 3/90 ceived 7/29/ss. sqeE of Control Systems 1218' new. I sobettted E 89-19 12/88, Rev. 1 under nRC l

A-48

',:._g. Control 10 CFR 50.44 All. except NA review.

Measures and Erfects SECY 89-172 PWRs wfth of ::,/..g.

8 erns large dry on Safety Equfpment contafements A-49 Pressurized Thermal RGs 1.154, 1.99

' PWR c ut 1/s6 sY si sen 11/s6 shock SECY 82-465 I v2 For v2 NRC review SECY R3-288 in progress or-i SECY 81-687 1/17/86 subetttal.

10 CFR 50.61/

E 88-11

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WWESEVED SAFETY ISSWES FOR tmICN A FIML TECMICAL RESENTIM MS BEEN ACNIEVES USI/MPA i

MMBER TITLE KF. SRCWENT APPLICMILITY STATUS /ONTE*

_ROUWR3 j

A-1 Water Hammer SECY M-119 All' c 11/83 syron,sRa pg.

NUREG-0927, Nev. I NUREG-0993. Nev. I 13-24 staid ood NUREG-0737 Item sua pg. c-1 2

t.A.7.3 SRP revisions A-2/

Assumetric Niewdeun NUNEG-0609 PWR c 11/83 MPA D-10 Loads on Neoctor Primary GL' M-04. - 60C-4 syron sEm pg.

3-34 staidwood l

Coolant Systems sua pg. c-1 i

A-3 Westinghouse Steen NUREG-0944 4-PWR c 11/89 commeitsents in Generator Tube Integrity SECY 86-97 response to cL 85-02 !

SECT 84-772 completed.

l GL 85-02 i

I (Norequirements) l A-4 CE Steam Generator Tube NUREG-0044. SECY 85-97 CE-PNR na lategrity SECY 88-272 GL 85-02 (Norequirements)

A-5 R8W Steam Generator NURES-0844, SECY 85-97 NW-PWR NA f

Tube Integrity SECY NS-77' j

GL 85-02 (No Nequirements)

E 3-6 Mark I Containment NUEG-04n8 Park T-8NR NA Short-Tem Program

• C - CONPLETE NC - NO CHANGFS KCESSARY i

NA - NOT APPLICABLE r

I - INCOMPLETE-E - FVALU4 TING ACTIONS REQUIRED

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USI/MPA NUMBER TITLE REF. 00CtpfW

_ADPLICm tLITY STATWWTE*

REDWIRR$

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l A-7/

Mark I long-Ters NUltEG-0661 Mark I-8NR MA D-01 Program HullEG-0661 Suppl.1 E 79-57 i

A-8 IIsrk-Ili Contatiment NUREG-0808 Mort II-Olet NA

~j Pool Dynamic Leeds NullEG-0487 Suppl.1/2 i

NUREG-0802 SPP 5.2.1.1C j

GBC 16 i

i A-9 Anticipated Transients IIUREG-0460. Vol. 4 All I U1-3/91 schedule setettted l

l Without Scram 10 CFR 50.62 v2-3/90 2-15-s9 A-10/

OUR Feeduster Nozzle NUREG-0619 ONR NA staidwood SER pg.

f MPA B-25 Cracking Letter frum DG Eisenhut C-1 i

dated 11/13/80 R 81-11 f

A-11 Reactor Vessel Material IIUREG-0744. Rev.1 All C 9/ss staidwood sEn Toughness le CFR 50.60/

supp. 1 pg. 5-4 i

82-26 t

A-12 Fracture Toughness of IIUREG-0577, llev.1 PNP NA l

Steam Generator and SRP llevision Ileactor Coolant Ptsy 5.3.4 l

Supports l

A-17 Systems Interactfens Ltr: DeVeeng to All E 10/93 CL 88-20 l

licensees - 5/72 IpE Response IRREG-1174. NINEG-subettted 10/27/s9 l

1229, IIllRES/CR-3922

-l IIUREG/CR-4761. IIUPEG/

i G?-4470. E 89-18 l

(no requframents) t A-24/

Ovalification of Class IllNIEG-0508. Rev.1 All c 10/s6 staidwood :;za MPA B-60 IE Safety-Related SRP 3.11 y

supp. 2 pg. 3-16,17 l

Equipment 10 CFR 50.49 E 82-09. E 84-24 l

E 85-15 t

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USI/MPA I

MMRER TITLE REF. SOCWENT

- APPLICASILITY STATU5/BRTE*

R9mmt5 A-26/'

- Reactor Vessel Pressure

- DM Letters to '

Pug c.11/s3 syron sua pg. 5-4 i

MPA B-04 ' Transient Protectfen Licensees 8/76 staidwood su -

1 i

MIREG-0224-Pg. c-1 NUREG-0371 SrP 5.2 GL 88-11 I

A-3!

Residual Neat Nemeval NUREG-0606 All Ols After c 11/s3 syren sEn pg. 5-2 Shutdown Regufruments NG 1.113 01/79.

11/88 (natural 23,24 staidwood RG 1.139 cire=1stion) saa pg. c-1 SRP 5.4.7 i

i A-36/

Control of Neevy Leeds NOREG-0612 All c 9/86 staidwood sua i

C-10 Near Spent Feel SRP 9.1.5 sopp.1 pg. 9-1 i

C-15 GL 81-07. GL 83-42 GL 85-11 Letter,from OG Eisenhet dated 12/22/80 A-39 Determinetten of SRV MmEG-0002 OIR NA Pool Dynamic Loads NUREGs-0763.0783.0802 and Pressure Transtants MUREG-0661 SRP 6.2.1.1.C I

A-40 Sefsofc Design SRP Revistems. MG/

All c 11/83 syron SER pg.

Criteria CR-4776. NUREG/CR-0054 C-l15 NUREG/CR-3900. NURES/

staidwood su CR-1582. NUREG/CR-1161 Pg. c 1

{

NUREG-1233. NUREG-4776 NUREG/CR-3OO5 NUREG/CR-5347 NUREG/CR-3509 A-42/

Pipe Cracks in So111n9 MREG-0313. Rev.1 Olnt NA MPA B-05 Water Reactors NUREG-0313.'Rev. 2 GL 81-03. E 88.

+ -

USI/ PPA NipatER TIYLE REF. OnCESENT APPI.ICASILITY STATUS /ORYE*-

ROMR$

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' Con +ainannt Emergency IRIREG-0510 All c.t1/s3 syrem saa c-15 Sump h NgNEG-8859. Rev. 1 IRIREG-8097. R.G.I.8?

c-16 g sym sem F5 Pg. 6-4, Braid e d, (llev. 0)..SRP 5.2.2 E 85422.

SER C-1 l-IIe lleguframents l

A-44 Statten Blackout' RG 1.155~

All I (Implement 1 year Response; submitted.

i M EG-1932 after nec review) 4/17/s, IIUREG-1109 j

10 CFR 50.63 A-45 Shutdown Dec.ay IIeat SECT 88-260 All E 10/93 Analysis re=eins f

IIemoval llequirements NUREG-1289 to be completed.

l NUREG/CR-5230 CL ss-20/Ips Response ;

i SECY 86-250 sub=1tted'lo/27/s, l

(llerequirements) l A-46 Sefsmic Que11fication M EG-1930 All I

sgoc provided generte of Equipment in NUllEG-1211/

implementatson REY o Operating Plants E 87-02. E 87-03 on 6/3/ss; sua received 7/29/88. Sqsc i

A-47 Safety implicatfen

~ NUREG-1217. NupEG-All E 3/90 Rev 1 sabettted 12/ss l

of Control Systems 1213 under nec review E 89-19 A-48

",/. ;;; Centrol 10 CFR 50.44 A11. except

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Measures and Effects SECY 89-172 PNRs with of Hydrogen Ourns large dry

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on Safety Egufpment containments A-49 Pressor 1 red Theruni RGs 1.154, 1.99 PIR I

Av.tting m review i

S SECY M 4 5 of submitted j

gggy g3g dated 01/17/s6 SECY 81-687 10 CFR 50.61/

E 88-11 l

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