ML20004C141

Environ Qualification of Safety-Related Electrical Equipment,Ie Bulletin 79-01B, Technical Evaluation Rept

ML20004C141
Person / Time
Site:	Prairie Island
Issue date:	11/17/1980
From:	Jablonski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20004C142	List: ML20004C141
References
IEB-79-01B, IEB-79-1B, NUDOCS 8106010616
Download: ML20004C141 (17)

Text

-

o' 1

ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED 9

ELECTRICAL EQUIPMENT IEB 79-01B TECHNICAL EVALUATION REPORT DOCKET No. 50-282 DATED: November 17, 1980 y

AY Licensee: Northern States Power Co.

3 Type Reactor: W PWR i

Plant: Prairie Island Unit 1 Prepared by F. J. Jablonski Engineering Supp4rt Section Reactor Construdtion and Engineering Support Branch, RIII 2

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CONTENTS l

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Introduction 1

Background and Discussion 1

Summary of Licensee Actions / Statements 1

Syste:n Comparison 2

4 Equipment Evaluation 2-4-8 Caveat 2

Conclusion 2

Attachments:

1.

Referenced Test Reports 2.

Onsite Inspection Report 3a.

Generic Issues 3b.

Site Specific Issues 4.

Licensee System List i

5.

NRR's System List 6.

Category Criteria t

7.

LER's 8.

Unresolved Generic - Specific Issues 9.

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Introduction II This report is submitted in accordance with TI 2515/41 for 'ise as input to the Safety Evaluation Report on qualification of Class IE eleGrical equipwnt installed in potentially " harsh" environmental areas at this facility.

Background and Discussion IE Bulletin No. 79-012/ required the licensee to perform a detailed review of the environmental qualifica ion of Class IE equipment to ensure that the equip-ment would function under (i.e. during and following) postulated accident conditions.

The Technical Evaluation Report (TER) is based on IE's review of the licensee's submittal for conformance with the DOR guildelines or NUREG-0588, a site inspec-tion of selected system components, to EQB's review of component test reports.prify accuracy of-che submittal, and Licensee submittals were received on March 13, 1980, May 12, 1980, May 23, 1980, July 10, 1980 and October 31, 1980.

The site inspection was completed on September 26, 1980.

Generic and site specific guidance was requested from IE/NRR headquarters Summary of Licensee Actiona/ Statements Based upon evaluation of Class IE equipment, licensee believes he has complied with the requirements of Bulletin 79-01B. Licensee believes that with the completion of the action items nated, there will exist no outstanding items which would preclude the continued safe operation of Prairie ' Island Unit 1.'

3 Replacement of solenoid valves, limit switches and other instruments is being ff accomplished as material is received and scheduled for installation during J

the next outage. Unit I replacements and modifications which were not com-he#

pleted during the last outage, will be completed when material js__ received.

and operations permit or during the next scheduled outage; in any event, all modifications wtIl be completed by June 1982.g 1/ Technical Evaluation Report (TER) On Results Of Staff A tions Taken To Verify Reactor Licensee Response To IEB 79-01B And Supplemental Information.

2/ Environmental Qualification of Class IE Equipment.

3/ Attachment 1.

4/ Attachment 2.

[/ Attachments 3a and 3b.

_1

System Comparison A comparison was made between the system 9Ilist provided by the licensee 6/

and a similar list provided to IE by NRR-during a meeting in Bethesda, MD on September 30, 19S0. The following systems were not included in the li-censee's submittal.

Pressurizer Spray Emergency Power Control Room Habitability

}

Safety Equipment Area Ventilation Equipment Evaluation Class 1Eeggpmentwasevaluated,thatis,placedintofiveseparate categorie).- Result of the evaluation follows:

(See pages following)

Caveat Test reports and other documentation which licensees referenced as estab-lishing environmental qualification were reviewed for acceptability by NRP, Environmental Qualification Branch.

(Reference Attachment 3a, memorandum dated June 20, 1980 Mayes to Jordan.)

This TER does not include information about sei:::::ic of fire withstand capability.

It should therefore not be inferred that Category I equipment meets all necessary qualification requirements.

Conclusion

~

BasM on IE's review of the licensee's submittal, the site inspection, and licensee'ii proposed actions, it cannot be concluded that there is reasonable assurance all components inst'alled at the Prairie Island Unit I are environ-mentally qualified and installation methods of environmentally qualified components would not contribute to the failure of such components during a potential accident.

A positive conclusion cannot be made until:

J 1.

All matters referred to IEHQS/NRR have been satisfied.EI 2.

The 4 systems c:issing from the licensee's submittal have been evaluated by NRR.

(Page 2) 3.

The negative equipment evaluations have been reviewed by NRR.

(Pages 4, 5, 6, and 8.)

6/ Attachment 4.

7/ Attachment 5.

8/ Attachment 6.

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WCAP Th10-L Motorized Valves 2.

WCAP 77hh Motorized Valves 3

FIRL F-C3271 Motorized Valves h.

Limitorque Project 600h56 Motorized Valves 5

ACME Cleveland Test Plan 8-31-77 Limit Switches 6.

Letter 5-12-80 USP-:mC Limit Switches 7

WCAP 7829 Fan Motors 8.

Joy MFG X kil Fan Motors 9

ASCO Test Report AQS 21678/TE -Rev. A Solenoid Valves 10.

Honeywell Catalog 50, Page E-2 Limit Switch 11.

Engineering Test Lab, Bulletin 6 Limit Switch 12.

Letter 3-25-80 E/M-NSF Motor 13.

Letter 9-29-80 NSC-NSF Motor / Fuse Holder ik.

WCAP 85h1 Transmitter 15 Mapetrol TR 9306 Trans=itter

16. Letter 11-30-79 3SP-3&W Accelerc=eter

17. WCAP 9157 RTD 18.

Letter 3/80 USP-NRC Signal Converter 19 Letter 3/78 NCP-NRC Limit Switch 20.

Letter 7/80 NSP-IGC Limit Switch 21.

WCAP 875h Motor 22.

WCAP Th10-C Transmitter 23 MIL-STD-202D Fuse Holder 2h.

Letter 2-7-80 Mobil Oil-NSP Lube Oil 25 Letter 10-30-79 Chevron USA-NSP Grease

26. Letter 1-19-77 W -Wis/Minn Pcver Grease 27.

Letter 11-21-78 GE-NSF Epoxy Varnish 28.

Letter 8-T-78 GE-GE Epoxy Varnish 29 GE Insulating Materials Products Data, Epoxy Varnish TkO10A Epoxy Resin and Th010 Epoxy Catalyst; Effect of Radiation on Materials 30.

Okonite Test Procedure Cable 31.

Letter 8-31-78 Ckonite-NSP Cable

32. WCAP Tklo-L Vol. II Cable 33 FIRL F-C2737 Cable 3k. Kerite KPT-LVC-1 Cable i

35 3IW 3901 Cable l

36. BIE 390h Cable l

37.

D.G. O'Brien C19QA053 Penetration l

38. Letter 6-20-78 Fluor-Picneer-WPS Penetration 39 D. G. O'3rien ER-192 Penetration h0.

LOCA Qualification of Kerite 1000v Splice Kits FR Insulated, FR Jacketed Cables 3-10-80 kl.

Qualificatien Tests of Electrical Cables Splice Kits Under Si-n!ated Pcst-Accident Rx Cat =t Service Cond. R-C2737 h-15-70 h2.

ACME Cleveland Test Plan 7-2h-78 Limit Switch h3 Nuclear Radiation and Switch Applications Limit Svitch kh.

PINGP's ICCS Actuation Study Mov h5.

Nu=erous Tests on Various Ins. Mat'l Motor i

Test Reports ATTACHMENT 1 l

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ad 9s Me d a, ff.......l UNITED STATES l

.,.7 1

NUCLEAR REGULATORY COMMISSION r

i REGION lil 7se noostytLT noao

,e*

oLEN ELLYN. lLUNois 00137 September 26, 1980 MEMORANDUM FOR:

E. L. Jordan, Assistant Director, Division of Reactor Operations Inspection, IE:HQ THRU:

d. Piorelli, Chief, Reactor Construction and Engineering Support Branch 1

I FROM:

D. W. Hayes, Chief Engineering Support Section 1

SUBJECT:

SCREENING REVIEW OF LICENSEE RESPONSE TO IEB 79-015 AND

SUMMARY

OF INSPECTION OF INSTALLED SYSTDIS AT PRAIRIE ISLAND 1 AND 2 - DOCKET NOS. 50-382;.50-306 i

Frank Jablonski has completed the inspection phase at Prairie Island Units 1 and 2 in response to IEB 79-01B. A walkdown was conducted on September 17, 1980 to inspect installed components associated with the systems listed on the attach==nt.

Observations:

Motor Operated valves (MOV's) r MOV Nos. MV-32132 and Mv;32135 'were.limitorque, type SMB-000 with Reliance motors, Class "B" insulation; MOV No. MV-32068 was-limitorque type SMB-00 with a Reliance laptor, Class "HP" insulation-The-referenced qualification documentatiogwas Project Number 600456 which qualified motors with "RE" insulation.

MOV No. 32020 was limitorque type SMB-00 with a Reliance ntor, Class "B"-

l insulation. Class "B" is suitable outside containment. The referenced l

qualification <'.ocumentation was WCAP 7410-L and 7744 which meet or exceed outside cont =f n=ent duty.

In all cases the MOV's were installed in accordance with manufacturer's recommendations. Both power and control cable were installed in flexible I

metallic conduit.

l

• Below flood level.

1 Doce Recirculation Fan The fan unit was a Joy Axivane series 1000, Model No. 018-1Y-3450, Serial No. SF27974-1, Motor No. 600277-69. The referenced qualification Onsite Inspection Report ATT!. CEMENT 2

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l E. L. Jordan September 26, 1980 l

documentation was Joy Manufacturing Report No. X-411; that test report I

was for Motor No. 600277-69.

All requirements appear to have been met.

Solenoid Valves All of the solenoids listed on the attachment were scheduled for replace-ment, however, discrepancies existed between solenoids listed on the component evaluation sheets and those actuany instaned. For example, solenoid Nos. 33374 and 33377 were listed as EHT832427; type RET 8321A1 ingtalled Similar discrepancies existed with solenoid Nos. 33440

(

and 33441 In an cases the instanation met manufacturer's recomc:endations, i.e.,

installation in any position was acceptable. Cable was installed individuany or in combination rigid steel / flexible metal conduit.g' Terminations were made in standard handy boxes, i.e., without gasketed cover; open to atmosphere.

(Refer to Terminations, below).

Limit Switches Limit Switch _Nos..CD-34074 and CD-34078 were NANCO Model EA-180.

i Qualification reference document was AQfE-Cleveland Test Plan, August 31, 1977. The licensee is considering the instauntion of hermetic sealing units at the interface of the. limit switch and flex / rigid

(

conduit.

[j Component evaluation sheet for switch No. CV-31107, a NAMCO n l

was not shown to be qualified for aging, operating time, or pressure.

t l

Instruments 1

Instrument Nos.16796* and 23015, containment sump level and main steam -

flow respectively, will be replaced. The installed instrument models were Magnetrol A-153FEP/VPIT-TDM and Barton 384.

s

} The incore thermocouple reference junction boxes, ETI Model K81, used in conjunction with the subcooling meter will be replaced.

E/P signal converter, No. SC35029, used to control a steam generator power

. cperated relief valva (PORV) was identified by the licensee as not being l

! environmentally qualified. The converter was a Fisher Controls type 546, 1

contained in a NEC Class 1, Group D enclosure. The converter for the other power operated relief valve was located on the opposite side of the i

same room. Based on the information contained on page 2 of licensee ATTACF2EIT 2

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E. L. Jordan 3-September 26, 1980 1 I letter to NRC dated March 13, 1980, it could not be concluded that the signal converter for at least one PORY was adequate to effect an orderly cooldown, i.e., survive the specified environment of 210 F, 15.2 psia and 100% RR.1 i

• Below flood level.

t Terminations Various component ter=ination devices were opened for inspection.

Penetrations were terninated on Alan Bradley No.1492 terminal blocks installed in large junction boxes with covered panels; with Okonite splices; or covered with what appeared to be Scotch 27 tape. The latter two types were not protected by junction boxes. The Okonite splices were qualified by test.

Other components such as solenoid valves and limit switches were terminated in junction boxes or handy boxes; however, no environmental credit was given to any protection which might be offered by the enclosures. The terminations were stated to have been covered with three layers of Scotch No. 70 tape, three layers of Permasel' fiberglas

( tape and then a repeat of Scotch No. 70 tape.

. r fNCTE: A componegt evaluation worksheet was not included with the submittal.

Conclusion Except as reported above, motor insulation, solenoid valves, signal converterm and terminations, the equipment descriptions provided by the licenses on the system component evaluation worksheets for the systems identified were complete and accurate.

be licenses was made aware of these discrepancies.

A detailed review will be made by the licensee and the response amended.

1 1

l'.., aLCof(L-j DLW. Hayes, Chief Enginee' ring Support Section 1 l

l

Attachment:

As Stated cc:

J.G. Kappler G. Fiorelli C. Fierabend, Res. Insp.

V. D. ThomaJ, IE:HQ m2

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ATTACHMENT t

LIST OF COMPONENTF e

NUMBER UNIT GENERIC NAME SYSTDi INSIDE OUTSIDE MV-32132 1

Motor Operated valve CL -

X l

M M 2135 1

Motor Operated Valve I CL I

~

MV-32068 1

Motor Operated Valve SI -

I MV-32020 2

Motor Operated Valve MS- -

1 4

11'(DRF) 1.

Dome Recirculation Fan ZC -

I' SV-33374 1

Solenoid valve ZC X

SV-33377 1

Solenoid valve

' IC I

SV-33440 1

Solenoid Valve

,ZP -

I SV-33441 1.

Solenoid Valve ZP 7,

SV-33261.

2 Solenoid Valve-MS I-SV-33265 2

Solenoid Valve MS X

CD-34074-1 Limit Switch ZC I

CD-34078 1

Limit Switch

, ZC I

CV-31107 2

Limit Switch r MS I

16796 1.

Level Transmitter i CS -

I 23015*

1*

Flow Transmitter jHS I

15456 1

Junction Box iRC -

X, SC35029 2

Signal Converter

+MS I

1 Terminations ALL X

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• g e-REcint ni 799 moostvgLT ROAD g, -*... j' claw sttvN. ituhois sour July 23,1980 MEMORANDUM FOR:

E. l.. Jordan, Assistant Director, Division of Reactor Operations inspection, IE:HQ THRU:

G. Floreill, Chief, Reactor Construction and Engineering Support Branch FROM:

(

D. W. Hayes, Chief Engineering Support Section 2

SUBJECT:

IES73-018 (A/l F03067180)

Attached is a copy of a memorandum dated July 17, 1980 received from Frank Jablonski relative to IEB 79-018.

It is being forwerded for your Information and solicited guidance.

The question of identification of safety related systems and components (paragraph No. I of the memo) is an old one.

I disagree with Frank in that I feel that this identification is a responsibility of the Ilcansee, not the NRC.

He must know his plant.

I do agree, hwever, that more guidance is needed for our inspectors in this area. This,is espeelally important for those inspectors that have not had reactor operating experience.

The significant differences in master lists that Frank discusses in paragraph two does raise questions. Ve can only compare these IIsts against the SAR. Review and evaluation beyond this is assumed to be an NRR function, in regard to Frank's question - should we assume the licensee's response to IEB 79-01B to be complete and correct - I have told him yes. Further, that if he identifies significant incompleteness in the response, or incorrect Information during his reviews, to bring these to my attention so appropriate action can be recommended.

Corrrnents and further guidance is requested concerning matters discussed in paragraphs 3 and 4 of Frank's memo.

I D. W. Hayes, Chief Engineering Support Section 2 Generic Issues ATTACHMENT 3a TcbIWG.3

E. l.. Jordan 2

July 23, 1980 1

8

Attachment:

F. J. Jablonski Memo to D.W. Hayes dtd 7/17/80 cc w/ attachment:

. G. Keppler, Alli V. D. Thomas, I E:HQ A. Finkel, Rt R. HardwIck, Ril D. Mcdonald, RIV J. Elin, RV R. F. Helshman, Rl li

-> F. J. Jablonski, Alli

.u.

ATTACHMENT 3a i

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A UNITED STATES j

NUCLEAR REGULATORY COMMJSSION e

REGION 111 I

799 ROOSEVELT ROAD

,e cLEN ELLYN. ILLINols 60137 July 17,1980 S MEMORANDUM FOR:

D..W. Hayes, Chief, Enginee-ing Support Section 1 FROM:

F. J. Jablonski, Reactor inspector

SUBJECT:

FORMULATING TECHNICAL EVALUATION REPORTS (TER) -

REVIEW OF IES79-01B RE: MEMO TO YOU DATED JUNE 16, 1980 - SAME SUBJECT Since the review of IEB 79-01B 1s continual, new discrepancies continue to show up; discrepancies are not necessarily the licensees'. As you know, there is no specific nuclear power plant design required by NRC.

Further, the designation of safety related systems is somewhat arbitrary and inconsistent.

In fact, the NRC places responsibility for classifying safety related systems on the IIcensee.

i i

Action item No. I of 79-018 requested each licensee to provide a " master ilst" of all ESF syste.ns in their respectirs p.lant required to function during a postulated accident. Appendix A to 79-018 IIsts " typical" equipment / functions needed for mitigation of an accident. A comparison of master ilsts was made of four IIcensees with similar Westinghouse PWRs, (see Attachment 1). Arbitrary selection and non-standard nomenclature i

of systems makes evaluation of the master IIsts extremely difficult.

NRC 1 requested each IIcensee to submit the Information under oath.

Shouldthek information therefore be assumed complete and correct?

l

/

It is extremely frustrating to review responses which vary so much in attention to detall, depth of review, etc. As stated previously in the i

.i draft TER for D.C. Cook, because I as a principal reviewer lack detailed l

systems / operations experience, further guidance is requested.

t I

i Another TER related matter is motorized valves equipped with Limitorque I

i operators (see Attachment 2). As can be seen, each test report is for a !

specific unit type including motor type and Insulation class. Almost all licensees refer to the various test reports as qualification documentation for all series of operator types; never is name plate data l s

j provided.

For example, test report No. 600456 (SMB-0-40, Reliance Motor j

with Class RH Insulation) may be listed for all operators from series j

SMB-000 to SMB' 5; motor name plate data not provided. Vithout the name plate dsta and the basis for extrapolation, a meaningful evaluation j

cannot be made.

I g

ATTACHMENT 3a p

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D.W. Hayes 2-July 17, 1980 It is requested that this memorandum be forwarded to IE:HQS as an addition to A/l F030,67180 with the same copy distribution.

l

\\

d j

F. J. Jablonski Reactor inspector Attachments:

1.

Comparison of Master Lists 2.

Motor Operated Valve Tests cc:

J. G. Keppler G. Flore111 ATTACHMENT 3a m

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ATTACHMENT 1 SYSTEMS Pi-(p,Qg, E

PT. scH.

Aux. F.W.

X X

X Chem. & Vol. Cont.

X 2

X X

Cntmt. Air Hndtg.

X X

X Cntet. H Cont.

X X

2 Cntet. Sp.

X X

1 Main Stm.

X X

X Aux. Stm.

X Stm. Dump X

Rx CLnt.

X X

X X

Res. -Ht. Sm.$

X 2

X 3

Saf. Inj.'

X 2

X X

CLg. Water X

Esnt ' t. Se rv. Wat.

X Comp. CLg. Wat.

X 3

Aux. CLnt.g CLg.2 Emerg. Cor 1

X 1

X Cntmt. Purge X

Rx. Bldg. Vent X

Inst. & Prot.

X Rx. Trip. Act.

X Rx. Cont. & Prot.

X Rad. Monit.

X Rx. Hot Samp.

X Stn. & Inst. Air X

i Stm. Gen.BD X

Post Acc. Monit.

X

'em. Sht. dn. Monit.

X Cntmt. Isol.

X X

Mn. Stm. Isol.

X Mn. FW Isol.

X l

l ATTACHMENT 3a t

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ATTACHMENT 2 MOTOR OPERATED VALVES MOV's 1.

There are basically two type series of Limitorcue operators:

SMS and SB. The operators arc sized from 000 (smallest) to 5 (Largest) as follows:

SMS-000_,

SMS-00 3

SM3/SB-0

~})Thisseriesmay SM3/SB-1 This series may also also include WB SMB/SB-2 >

include SB SMB/SB-3 SMB/SB-4

~

This series may SMB-5 be suffixed "T" 2.

Test Reports include:

'+

Report No.

Date Unit Type Environment hote.- Type Insulation l

a. 600198 1-2-69 SMB-0-15*

PWR Relicnce Special Hi No Radiation Temo

b. 600426 4-30-76 SMB-0-25*

BWR Peerless H

7 (B-0009) 1x10 R DC 340*

c. 600376A 5-15-76 SMB-0-25*

BWR Reliance RH

(

FIRL F-C 2x108i i

3441

~

d. 600456 12-9-75 SMB-0-40*

PWR Reliance RH g

2x10

e. 600461 6-7-76 SMB-0-25*

Outside Reliance B

Cntmt 7 2x10 i

f. WCAP7410L 12-70 SMB-00 8

7744 8-71

• denotes foot pounds of torcue only SMS-0 has been tested seismically Re: a,b,c

.se ATTACHMENT 3a

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UNITED STATES

!~

j NUCLEAR REGULATORY COMMISSION 1

a wasmucTow, n. c. 2 ossa SSDiS #6820 JUI.

3 1980

. MEMORANDUM FOR:

Z. R. Rosztoczy, Branch Chief. Equipment Qualification Branch, Division of Engineering, NRR M

THRU:

[ '

E. L. Jordan Assistant Director for Technical Programs, Division of Reactor Operations Inspection. LE ~

FROM:

V. D. Thomas, Task Manager, Review Group, IEB 79-01B, Divisit. of Reactor Operations Inspection, IE

SUBJECT:

REQUEST FOR NRC POSITIONS ON REVIEW QUESTIONS OF IEB-79-OlB LICENSEE RESPONSES In accordance to our verbal agreement, we would be happy if you would provide positions on the questions noted in the enclosed memorandi.

Since it is essential to establish a unifonn approach to the review effort' to obviate the questions being generated in the on-gof.ng review of licensee responses, we will be happy to meet with your staff to discuss these concerns to expedite resolution of the issues.

b VincentD.ThomasITask' Manager

~

Review Group, IES79-01B

Enclosures:

1.

Memo D. W. Hayes to G. Fiorelli, RIII dated June 20, 1980.

2.

Memo F. Jablonski to D. Hayes, RIII l

dated Jun 16, 1980.

3.

Memo F. Jablonski to D. Hayes, RIII DATED June 10, 1980 cc: w/ enclosures E. L. Jordan, IE V. S. Noonan, NRR G. Fiore111 'RIII I

D. W. Hayes, RIII A. Finkel, RI R. Hardwick, RII i

?. Jablonski, RIII D. Mcdonald, RIV J. Elin, RV dUl 71980

%00%O703M

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c UNITED ST ATES

[ ;.,., ',

,~,j NUCLEAR REGULATORY COMMISSION r

REGION lli

[

790 ROossysLT ROAD g

,e

GLsN sLLYN, ILLINOIS 60137 June 20, 1980 MENORANDUM FOR:

E. L. Jordan, Assistant Director, Division of Reactor Operations inspection, IE:HQ hA. Flore111, Chief, Reactor Construction and THRU:'

Engineering Support Branch v

FROM:

D. W. Hayes, Chief. Engineering Support Section 1

SUBJECT:

lEB 79-018 (A/l F03067180)

Attached are two memoranduns from one of my inspectors, Frank Jablonski.

The first Is dated June 10, 1980 and the second June 16, 1980. Both memos raise basic questfons for whIch we require guidance to complete our re elew of responses to IEB 79-015.

By this memo I also would like to confirm our understanding that NRR (Environmental qualification Branch) will re.'lew for acceptability all test reports and other documentation which IIcensees reference as i

establishing environmental qualification of Instrument / electrical equipment.

In connection with this, we are sending under separate

/

cover test reports, etc. In our possession to be forwarded to the l

Environmental qualification Branch.

(We further understand that the I,

IEB 79-01B task group, on a volunteer basts, may agree to review some i

of these documents).

The status or schedule for site Inspections and review / evaluation of the final reports is also attached. Please note that every IIcensee has asked for some sort of time extension to submit their first report. We understand that the other regions have had slmllar reporting pretlema.

Assuming that all our IIcensees meet their extended submitta' cates, we should complete our site inspections, reviews, and technical evaluation h

ATTACHMENT 3a

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E. L. Jordan June 20, 1980 2

reports by the end of December 1980.

Further delays In the submittals or any unforeseen events will hamper our ability to rneet the new February 1,1981 deadline.

/

<.s &

D. W. Haye, Chief Engineering Support Section 1 Attachments:

1.

Memo F. Jablonski to D. Hayes 6/10/80 2.

Memo Fs Jablonski to D. Hayes 6/16/80 3

Inspection Status / Schedule 4.

" Separate Cover" List (Test Reports Sent to IE:HQ)

- Separate' Cover: See Attachrent 4 cc w/attachr.ents 1, 3, s 4 enly:

J. G. Keppler G. Flore11I V. D. Thomas, IE:HQ A. Finkel, R1 R. Hardwick, Rif D. McDor.ald, RIV J. Elin, RV R. F. Heishman s

i ATTACHMENT 3a

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'g UNITED 5TATES i \\*

• h,$ ((f I

NUCLEAR REGULATORY cot.1 MISSION

. g S

,f REGION lli 7ss noossvsLT no4o gN oLEN ELLYN. ILLINOls 60137 June 10, 1980 MEMORANDUM FOR:

D. W. Hayes, Chief, Engineering Support Section 1 FROM:

F. J. Jablonski, Reactor Inspector

SUBJECT:

EFFECT OF PREVIOUS NRR REVIEW ON MATTERS RELATING TO IES79-018 In almost every licensee response to IES79-018 there is a subtle or direct reference to matters apparently reviewed by NRR.

Because of the referenced dates it is assumed by me that NRR has given either tt.it or direct approvat to the references; exanples follow:

1.

All Licensees refer to their FSARs for establishing the list of engineered safety feature systems and environmental data such as temperature, pressure, radiation, etc.

2.

One licensee, Wisconsin Public Service Corporation, states that "The AEC, in their " Safety Evaluation of the Kewaunee Plant", Section 7.5, issued July 24, 1972, concluded that our criteria and testing program for environmental qualification were adequate".

It is further stated that "Our FSAR, which was approved by the AEC, discusses at length the post accident conditions and required qualifi-l cations for applicable equipment.

(See Section 7.5 of the Kewaunee FS AR.)"

3.

Two licensees, American Electric Power and Wisconsin Public Service Corporation, have discussed the effect of components below flood level simply by referencing letters previcusly 9

subnitted to the NRC, c' FSAR questions / answers as follows:

• AEP

.- Letter dated 9-2?-75 from Tillinghast (AEP) to Kniel (NRC); FSAR question 40.10 Appendix Q.

• WPSC l

Letter dated 2-2-76 from James (WPSC) to Purple (NRC).

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o June 10,1980 2

D. W. Hayes My specific concerns are:

Is it to be assumed that the referenced FSAR parameters, No. 1 above, are correct, i.e. reviewed by NRR7

. If the answer is yes, then should it also be assumed that No. 2 above is likewise adequate?

(If the answer is no, then none of the Licensee responses which reference the FSAR can be assumed to be correct.)

Reference No. 3, even though a component may r.ot be required to operate subsequent to fleming, what effect will short circuits have on containment electrical penetrations? Was this considered by NRR7 I am requesting that these questions / concerns be forwarded to the Assistant Director, Division of Reactor Operations Inspection for resolution.

C&

r F. J. Jablonski Reactor Inspector cc:

J. G. Keppler G. Fiorelli

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ATTACHMENT 3a

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June 16, 1980

• MEMORAfiOUM FOR:

D. V. Hayes, Chief, Engineering Support Section 1 FROM:

F. J. Jablonski, Reactor inspector

SUBJECT:

FORMULATING TECHNICAL EVALUAil0N REPORTS (TER) -

REVIEW 0F IEB 79-01B in accordance with IEB 79-01B, an overall conclusion relative to the quali fication of instrument electrical equipment is to be made for each operating plant based on a screening review of all plant systems, and by a detailed review and observation of specific system components.

Unresolved concerns previously* Identified by Rill Inspectors during reviews of IEC 78-08 and IEB 79-01 along with subsequently identified concerns make it difficult for us to formulatis meaningful TERs for certain plants. The previous unresolved con 2rns are documented in the merorandums listed below (1,2,3) and are reiterated in Attachment A to th"O memo. Subsequently identified concerns are listed in Attachments B, C, and D.

To assure uniform evaluation, guidance is needed for these items. Please forward these concerns to IE:HQ.

1.

71 2515/13 - Qua3 f fication of Safety Related Electrical Equipment Florelli to Snie2ek,, 70/13/78 2.

Same title as I., Floreill to Klinger,12/78 3.

Review Status of Responses to IES 79-01, Hayes to Jordan 9/5/79 N f'm6(w ~

F. J. Jablonski Reactor Inspector

Enclosures:

As Stated t:c:

J. G. Keppler G. Florelli V. D. Thomas, lE:HQ A. Finkel, RI R. Hardwick, All D. Mcdonald, RIV J. Elin, RV ATTACHMENT 3a f~scoroyos#l"wumu/7u([ fd4 f474A f/

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