ML17319A774

Forwards Second Set of Responses to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Also Forwards Summary Table of Equipment Qualification Status of TMI-related Equipment & Info Re Cold Shutdown Equipment

ML17319A774
Person / Time
Site:	Cook
Issue date:	02/03/1981
From:	Maloney G INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
AEP:NRC:0356D, IEB-79-01B, IEB-79-1B, NUDOCS 8103230354
Download: ML17319A774 (39)

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INDIANA IIt MICHIGAN ELECTRIC COMPANY

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P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 February 3, 19 p

'NRC: 0356D '4

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Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 IE Bulletin 79-01B/Environmental gualification of Class lE Equipment Mr. James G. Keppler, Regional Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

/

Dear Mr. Keppler:

This letter has three purposes. The first purpose is to fulfill the commitment we made in Reference 6 in response to References 4 and 5 in the area of TMI Action Plan equipment. Attachment 1 to this letter contains a summary table describing the equipment qualification status of all TMI-related equipment. As the qualification information for this equipment becomes available we will submit it to you as supplementary responses to IE Bulletin 79-01B.

The second purpose of this letter is to revise our second set of responses to IE Bulletin 79-01B which was contained in Reference 1 and amended by References 2 and 6. In this regard, the equipment qualification charts contained in Attachment 2 to this letter should be inserted in Attach-ment 5 of Reference 1. These few pages might have been inadvertently omitted from Reference 1 during the reproduction process and are being sent to you to insure the completeness of your copy of the subject documentation.

The third purpose of this letter is to further respond to the require-ments for "cold shutdown" equipment contained in References 4 and 5, as clarified in Reference 7. You will note that in Reference 6 we responded to these requirements while at the same time taking exception to the manner and approach of Reference 3.

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Nr. J. G. Keppler AEP:NRC:0356D Our position still remains that the inclusion of equipment necessary to achieve cold shutdown, even as described in Reference 7, represents a major change to the licensing basis of the Cook Plant and accomplishing such changes through Orders, Supplements to Bulletins and letters detracts from the stability of the regulatory process. Nevertheless, in order to demonstrate our commitment to the issue of environmental qualification we have re-reviewed our initial response effort, focusing on the equipment needed to proceed from safe (hot) shutdown (present Cook licensing basis) to cold shutdown following a LOCA or High Energy Line Break. It is the conclusion of our plant operating staff and AEPSC engineering personnel that except for the few pieces of equipment discussed in Attachment 3 to this letter, all equip-ment needed to achieve cold shutdown and potentially exposed to an adverse environment, has already been included in our IE Bulletin 79-01B response effort (References 1, 2 and 6). Therefore, aside from Attachment 3 to this letter, no additional information in this area needs to be submitted.

Very truly yours,

. P. Mal ney Vice'Pres den cc: (w/attachments)

N. C. Moseley - NRC D. V. Shaller - Bridgman NRC Resident Inspector at Cook Plant - Bridgman F. Jablonski - NRC Region III cc: (w/o attachments)

R. C. Callen G. Charnoff John E. Dolan R. W. Jurgensen

'1 4

REFERENCES

l. Letter AEP:NRC:0356A, R. S. Hunter to J. G. Keppler, dated May 7, 1980.

2. Letter AEP:NRC:0356B, R. S. Hunter to J. G. Keppler, dated June 5, 1980.

3. Order for Modification of License attached to S. Varga's letter to J. E. Dolan dated August 29, 1980 and revised in D. G. Eisenhut's letter to J. E. Dolan dated September 19, 1980.

4. Supplement No. 2 to IE Bulletin 79-01B dated September 30, 1980.

5. Supplement No. 3 to IE Bulletin 79-01B dated October 24, 1980.

6. Letter AEP:NRC:0356C, G. P. Maloney to J. G. Keppler dated October 31, 1980.

7. Clarification letter from D. G. Eisenhut to All Operating Plants and License Applicants dated January 19, 1981.

ATTACHMENT 1 TO AEP:NRC:0356D

TMI Lessons Learned Items The equipment and/or systems itemized in this Attachment are being designed and installed in a manner consistent with our correspondence in response to your requests arising from the TMI-2 Lessons Learned effort.

The equipment and/or systems have been specified for the anticipated service conditions of the plant where the environment could be influenced by an accident or its consequences. *However the documentation such as qualification reports, for most items, is not presently available. When documentation is available the appropriate "qualification chart" will

'uch be issued as supplements to our earlier submittals.

NUREG-0737 NUREG-0578 SYSTEM/EQUIPMENT'TEM PLANT ID EQ NUREG REFERENCE , AEP : NRC NO. ITEM NO. NAME RE(EUIRED COMMITTMENT LETTER , OR EQ CHART OF AEP : NRC : 00356A I I.B. 1 2.1. 9 RCS Vents NSO-21 to 24. YES AEP:NRC:00253 & 253D NSO-61'o 64 AEP:NRC:00334 & 3348 AEP:NRC: 00398 II.B.3 2.1.8A Post Accident To Be Established NO NUREG-0660 Sampling Clarification 3.C II.D.3 2.1.3.a Valve Position QR 107 YES NUREG~0737, Clarification 3 Indication Limit Switches EQ Chart LS-1 for Limit.

on NRV-151,152,153 Switches II.E.1.2 2.1.7.b AFM Flow Indication FFI-210,220,230, 'YES NOREO D737, IZ.E.I.2'arh ,b I 240 AEP:NRC:00253 EQ Charts I4 (Unit 2)

& I5 (Unit 1)

II.E.4.2.3 New Additional CT Requirement Isolation Signals TO BE ESTABLISHED

'I.F.1.1 2.1.8. b Noble Gas Monitor To Be Established .NO NUREGw0737, Table XX.P; 1-1 II.F.1.2 '.1.8.c Iodine Monitor NO NUREG-0737,'able XX.P. 1-2 II.F.1.3 2.1.8.b Post Accident CT Vm-lool, 1002 YES NUREG 0737,, Table II.F.1-3 High Range Monitor 2001.,2002.

Upper. CT Area VRS-1101, YES AEP:NRC:00295B Monitor 1201'103,

. 23.01.

II.F.1.4 ACRS Item CT Pressure PPP-300 to 303 YES EQ Charts I29 8 I30 PPA-310 to 313 NO NUREG-0737,Attachment, 4 (II.F.1.)

II.F.1.5 ACRS Item CT Water Level NLA-310 'ES NUREG-0737, Attachment 5 (II.F.l)

NLI-311, 320, 321 II.F.2.1 2.1.3.b. b Subcooling Meter NTR-110 to 140, YES EQ Chart I28 (NTR's)

(pressure & 210 to 240

.temperature inputs) NPS-121, 122 EQ Charts I23 (Unit 1) & I24 (Unit 2) (NPS's)

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NUREG-07+ -- NUREG-0578'SYSTEM/EQUIPMENT PLANT ID EQ . NUREG REFERENCE, AEP:NRC ITEM NO. ITEM NO. NAME ~RE UIRED COMMITTMENT LETTER, OR E CHART OF AEP:NRC:00356A II.F.2.3 2.1.3.b.c Level Instrument-ation NLI-110 to 130 ill to-131 YES NUREG-p737 II.F.2 Clarification l I I.G. 1 2.1.1.b 8I Power Supplies to NRV-15l to 153 YES NUREG-0578 Clarification letter 2.l.l.c PZR Relief Valves, NMO-151 to 153 EQ Charts Sll-1 (NRV's),

Block Valves, and NLP-151 to 153 V9-1 (NMO's), and I18 (Unit 2)-

Level 5 I19 (Unit 1) (NLP's)

II.K.3.1 NA Auto PORV Isola- NMO-151 to 153 'ES EQ Chart V9-1 tion II.K.3.5 . NA Auto Trip of Reactor Coolant NA t To Be Established Pumps I I.K.3.12 New . Anticipated Trip P-7 NO NUREG-0611, Recomnendation Require- on Turbine Trip 3.2.4a ment III.D.3.4 Additional Control Room Require- Habitability To Be Established ment

ATTACHMENT 2 TO AEP:NRC:0356D.

Additions to Attachment 5 to AEP:NRC:0356A

0 DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 DOCKET NO. 50-315 LIC EH S E H 0. D P R-5 8 ENVIROHMENT-. DOCUMFHTATION REF.>> QUALIFICATION OUTSTANDING EQUIPMENT DESCRIPTION PAR AMETER SPEC. QUAL SPEC. QUAL. METHOD ITEI<IS gee. Qdoa I SYSTEM. ~Aaio v~ Operating Time I o>> Ql,/a 5;~~l ~

7d& o'h A'P PLANT ID NO'/8 Temperature

( F) yea. ag-(,L Sr~0 L ~

COMPONEN T: d wrao~ Cgag.g 7 sew'~ a rib~

Pressure (PSIA) rice / /~K 7 Sr-u L .

MANUFACTURER FIG z.

Relative MODEL NUMBER: 8aac.e V 6R nrem>+ robe 4 T Vhc M ES Humidity (%) ro 0 FUNCTION:

Chemical oooo 34 0< 1; 5.

Spray pp /0+ 8 3/f+ Z Z. S vL.

ACCURACY: SPEC: ir p/g, fi 6 DEMON: gA 'gCh" N~

QJ 2e SERVICE: f/r~ipcps Radiation (106 rads)

~p8~ 4 7 4~~-t.

l I So < I(ry grr 3, 'gL.

Aging LOCATION: 2e Q~g~gy~z~r (years)

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FLOOD LEVEL ELEV: 4 ABOVE FLOOD LEVEL: po Submergence TV'>

'Documentation

References:

4dO/Q'un Notes:

Sypr Corp Tes 7 P (7m g~ 7+~ 3>> ro - I)

) c v re.sg~ ~ a.

~wle~l~ LacA ~~+ ~,OQ.wla ~s, (Lleo, t 7 9Io L'F: l-'s S) ~W 5 i go aa vi r ~ ~ ~f-e oc M~l.

Page r~i-r

gualified by Linitorque Corp. Test Laboratory Pro ject -;r600198. s.ovemoer 1968 Type of Te t: simultan ous, steam chemical spray separate seismic test Type Profile:

2OoF 33 2oF 90 ps'g 70 p ig l

fo" hr for 2 hrs 287oF tp ps" g for 2 hrs 27loF) 20 p='-ig for l9 )as 25poF l5 ysig for 6 d"ys Chm~cal Spray-1+5) boric acid buffered with .",'a OH to a P.". of 7.67.

Seismic Test 8/20/79 Horizonta3 Force, 5, 3 G at 35 Hz Vertic..l for"e 5.3 G at 3>> Hz ho r sonance frey from 5 to 35 Zz

DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 DOCKET NO. 50-315 LIC"NSE NO. DPR-5":

ENVIRONMENT 0 0CUflEHTATION EgUIPIIIENT DESCRIPTION REF.>> gUALIFICATION OUTSTA IDINa PARAMETER SPEC. g'.JAL. SPEC. EQUAL.

METHOD ITEMS SYSTEM: QADI OVS Operating / ~

See. Alqye,/

Time a/C Wb1c 7 J=

PLANT ID ND: TP/$ Temperature

( F)

S acI, COMPONENT: <e<7+4< est/p Pressure

+CRrP.TrI/Qi IOQ P/Cp / 89. S~y flANUFACTURER: /I//gP (PSIA) Fi(~ g 7 f OD, Reiative IIlODEL NUMBER: dA"~

fi g~jcIc4TIOV PT rcglv+5 }tumidity (5) ADO FUNCTION:

Chemical ACCURACY: SPEC: AM Spray ~of ~p /JPo Wg DEMON: +A hlc.AP Radiation ygro-SERVICE: Vggioo~ (1G6 rads)

VO T-I Say I ($ 'I" c o 4 Aging LOCATION'

,tw + (years) '(es FLOOD LEVEL ELEV: b/rI' Submergence ABOVE FLOOD LEVEL: fa,w

'Documentation References". Notes:

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DONALD C. COOK NUCLEAR PLANT UNIT NO. I DOCKET NO. 50-315 LICENSE li0. DPR-58 DOCUMENTATION Eti VIROHMEHT REF.*

EQUIPMENT DESCRIPTION QUALIFICATION OUTSTAH DIN G PA RAN'ETER SPEC. jAL. SPEC. QUAL. METHOD ITEMlS Q

SYSTEM: P'IrO0 re Operating 5ce. Afc J ~ jP ~

Time ~ CN.bit'.

PLANT IO NO: /Y/Nl Temperature z3 SeI, COMPONENT: r'O~R'o( CNpgg'p Pressure

~~h'POIrAP~iinnl IAANUFAOTURNR:

(PSIA) /IR 7

~/Ul Relative MODEL NUMBER:

~~~I<'~<<>~'< Wr Ayggp uaZs rc Humidity (5) fdO ro c)

FUNCTION:

zoo o Z600 7.5, ACCURACY'PEC'EMON:

Chemical Spray pP ~t +~ ~Z 3/V $,4 3H<

A4 AC AP Radiation 1'lrO t.

SERVICE: Ir/4,sou~ (106 rads)

VON ISo< > Io<)i~

Aging LOCATION.1/ CoNl'qrNmE T (years) 9a~

FLOOD LEVEL ELEV: rTAt FLOOD LEVEL rtlO 0'BOVE Submergence

~bes .

'Documentation

References:

LI'~'iVorgoa Corp Pes f Eeporf'4ol98 z~. IP~.)~go Co rp 7cyk port 440376 A page 7d 9-/

TF VALVE OPERATORS CYCI.EO o INSULATION RESISTAIICES MEASURED 400 34D f/IDS PSIC (s3 f>>> PS IC) 1- 34D F/IDS PSIC ( )

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f/t) PSIC)

)2D'r/n PSIC (tb'r/sO PSIC)

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(42 f/tl PstC)

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3 Hour Drop to I6'2 F/D PSIC

2) Sec Itlse to )36 F/!08 PSIC, Tcnperocure Inc, to )4D F 4J In Less Thon 4 Hlnutes, I

200 ~ I I

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l9 Seci Hlse to 334 F/IID )SIC, Teoperoturo Inc. co )><I F In Less Thon 3 Hlnutes, IOO 0

START OF 8 e l

10 l2 I4 4 DAYS .

+ 6 IIR n

o (HR) I TISIE TEST c Figure 3. Actual Steam Exposure Profile

DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 DOCKET NO. 50-315 LICENSE NO. DPR-58 DOC Uf(lEHTATIOtf EQUIPMEtf T DESCRIPTIOH ENVIROtlfl'IEHT REF." QUALIFICATIOH t

OUTSTAIIDIH0 PARAhlETER SPEC. Qt'.AL SPEC. QUAI.. METHOD ITEhlS SYSTEM: yQg)~ Operating 5C.Ta. 3'e 4I Time

/pAp'g Sag.

PLANT ID ll0: 8!/I Temperature

( F) A./9-/

COfllPOHENT: <o&iHoL CIfgg ~

Pressure

~lQz, fcgnl > n~grl oh/

(PSIA) ~/ol RARUFADTllRER: +/g Relative hlODEL NUMBER: CP78gE

<<@>>~~~~TN< QT Pqgvpq Humidity (%) /od FUNCTION: a T,S.

ACCURACY: SPEC: ~/lf Chemical Spray RPOO 310

>/4%

f DEMON: 9/g odCRP Radiation

'fAfro~L SERVICE: VPAroaw (106 rads)

LJO L.

Aging tgo e r roohvt LOCATION:

~~ (years)

Co f-g.~

FLOOD LEVEL ELEV: 4,14 +~SUP'.

Submergence ABOVE FLOOD LEVEL'g ~rvbe5 Roles:g~~ v.7~+. V (/Ei)y l. @~M C4Q

References:

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SHEET TC-5 INTENTIONALLY OMITTED DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 DOCKET NO. 50-315 LICENSE HO. DPR-5 EHVIRONfilEHT DOCU'lEftTATION EQUIPMENT DESCRIPTION REF.~ QUALIFICATIOH OUTSTAft DING PARL')lETER SPEC. QLAL. SPEC. QUAL. ftIETHOD ITEhls SYSTEM: VSR) 005 Operating See./Jpf e, I Time lych> /.r m~ A t3 Se.g .

pLANT ID No: +jr Temperature Psalm

( F) 3<D le L3 Se.q.

COMPOHENT: doII/Tricot, egal8 Pressure

~r4 >

7cgpvttlvA r rOA'IANUFAOTUNEN:

~/jg (PSIA) p/c> t . .Its SQ),

Relative MODEL NUMBER: ~)o terror)r sp4c~o tb err;4prL)f)3 Humidity (%) /OO tOO pre ptoN FUN CTIOH:

Chemical pry f a 50 0 r e~~

f.5, 3/Vr $

ACCURACY: SPEC:  % Spray acro cf 3/4A 'Re).

I4 . Y~)

DEMON'4'ERVICE:

Radiation qqR<ou5 (106 rads) ~

I g v) Sty Aging LOCATION: (years) 6 +A~

FLOOD LEVEL ELEV: 5/r/ ~i.E)E)~

Submergence ABOVE FLOOD LEVEL: NO: g~beS

'Documentation Reterences: Notes:

)3 Mrrafrvrt ko)ps'rrar)rroR Teok Redo E)r~ <MA>> 832.

page T< 4'

ATTACHNENT 3 TO AEP:NRC:0356D

E ui ment Needed To Achieve Cold Shutdown The licensing basis of the Cook Plant is that equipment necessary for the mitigation of large LOCA and HELB design basis accidents, should be environmentally qualified t'o bring and mai'ntain the'Unit in safe (hot) shutdown. In accordance with the initial guidance given with IEB 79-01B, this licensing basis defined AEP's original response review

~

scope. The response effort has been re-reviewed win light of the recent Supplements to IEB 79-01B. Except for the two items discussed below, equipment exposed to a potentially adverse environment needed to achieve cold shutdown after occurrence of the DBA's mentioned above, has already been in the Cook Plant IEB 79-01B response effort.

l. N-31 and 32: These are source range neutron detectors. Since they do not generate any automatic protective function nor are they considered as DBA mitigat-ing equipment in the plant safety analysis, they were not included in our previous submittals.

They provide a confirmatory indication to the operator of the core's subcriticality. No qualification data is available for these items at this time.

2. WPI-705, 706, 707, 708: These are pressure indicators in the Essential Service Water System. They provide confirmatory information to the operator as to the operational status of this system. No qualification data is presently available. for these indicators.

No corrective action is required f'r these items since the loss of either function does not preclude the achievement of cold shutdown following a large LOCA or a HELB.

, ~ k I