ML19261A842

In Response to NRC ,Forwards Summary Rept Re Qualification Requirements & Status of Qualifications for 125 Volt DC Sys Mod Related Equipment

ML19261A842
Person / Time
Site:	Oyster Creek
Issue date:	02/05/1979
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Office of Nuclear Reactor Regulation
References
TASK-03-12, TASK-3-12, TASK-RR NUDOCS 7902080225
Download: ML19261A842 (22)

Text

$~ _ _,

Jersey Centra! Power & Light Company f4" ( )

Madison Avenue at Punch Bowl %ad

. 4 Morristown, New Jersey 07960 (201)455-8200 February 5, 1979 Director Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

Subj ect : Oyster Creek Nuclear Generating Station Docket No. 50-219 125V DC System Equipment Qualifications Your letter of December 22, 1978, requested a summary report des-cribing the qualification requirements and status of the qualifications for the following 125 DC system modification related equipment:

1.

The Battery 2.

The Battery Racks 3.

The Battery Charger 4.

The Motor Control Center In response to your letter, enclosed is the requested summary report.

Part 1 of the report presents a discussion of the equipment qualifi-cation requirements invoked by Jersey Central Power f, Light with respect to the 125V DC system modification.

Part 2 of the report presents a discussion of the status of equipment qualifications with respect to invoked equipment qualification requirements, and the appendices present documentation pertinent to the equipment qualifications.

We have prosided the enclosed summary report in an effort to be responsive to your request.

Since thi2,g;pdification was accomplished under the provisions of 10 CFR 50.59(a), the associated safety evaluation and specific documentation has been filed and is available for examination by your Office of Inspection and Enforcement.

Please note that Appendix IV is extracted from IE Inspection Report 50-219/78-35.

Very truly yours b///

/

[/Ivan R. Finftpck,.Jr.

Vice President cp

(

Enclosure 7 9 0 2 0 8 OM51 t

Jersey Central Power & Light Company is a Member of the General Pubhc UtMt:es System

Page 1 of 6 PART 1 EQUIPh!ENT QUALIFICATION REQUIREh1ENTS INVOKED BY JCPSL WITil RESPECT TO 125V DC SYSTEh! FIODIFICATION Final Requirements: A description of the then proposed modification, and the modification related equipment design criteria, were included in the enclosure to a letter to the Director of Nuclear Reactor Regulation from I. R. Finfrock, Jr.

dated April 4, 1978 Re: bbdification to 125V D. C. Power System. Within that document it was stated that "All new 125V DC system equipment will be class IE, meeting the requirements of IEEE Standard 323-1974."

In addition to the require-ments of this standard and those additional standards referenced by this standard, other standards and codes were--as a matter of good engineering practice--invoked.

A list of all of the standards and codes which have been invoked for the subject equipment is attached as Appendices I, II, and III (Note: Appendix I covers both the batteries and the battery racks),

Further, in that the requirements of many of these standards are somewhat general more specific requirements were specified to the respective equipment vendors in the form of detailed procurement specifications.

Jersey Central Power 6 Light 's Quality Assurance and Engineering Departments were, and continue to be, involved with the vendors in assuring they meet the requirements of those procurement specifications which provides adequate assurance that the intent of all the invoked codes and standards will be met.

In this same regard, the NRC Region I Office of Inspection and Enforcement has inspected many of the documents which make up this over-all management control system, and their efforts are documented in pages 8 through 13 of their Inspection Report 50-219/78-35. As noted

Page 2of 6 in this docementation (See Appendix IV), no items of noncompliance were found to exist.

Equipment Qualification Interim Requirements:

As was also stated in the cover letter of the referenced April 4, 1978 transmittal to the Director of Nuclear Reactor Regulation, "Becau;a of the short lead time available for this modifi-cation, it may not be possible to obtain all of the class 1E equipment identi-fied in the enclosed modification description. Should that be the case, we will complete the modification by the required date using the most qualified equipment availabic at that time, and install the IEEE 323-1974 qualified equipment when it becomes availabic and plant operating conditions permit."

As the situation continued to evolve, it became apparent that the above referenced equipment qualification final requirements could not be met on all the equipment by the end of the 1978 refueling outage, and in those situations equipment was utilized which was the most qualified available at the time.

As indicated in Part 2 of this report,.lCPf L is proceeding with measures to assure that all equipment will be qualified to IEEE 323-1974.

If the currently installed equipment can not be qualified it will be replaced with qualified equipment as it becomes available and plant operating conditions permit.

Page 3 of 6 PART 2 STATUS OF EQUIPMENT QUALIFICATIONS WITH RESPECT TO INVOKED EQUIPMENT QUALIFICATION REQUIREMENTS Qualification Status of Batteries and Battery Racks:

With Respect to Final Requirements:

The currently installed new battery "C" and associated battery racks were designed, constructed and installed so as to meet all the Appendix I referenced codes and standards. At this time, however, a shake test pursuant to the guidance of IEEE 323-1974 and IEEE 344-1975 has not yet been completed. This test is currently scheduled for April 1979.

Assuming this test is successful, after JCPSL's receipt and approval of these test results, the new battery "C" and its associated battery racks (as they currently exist at Oyster Creek) will be fully qualified per the Appendix I referenced final codes and standards.

Interim Requirements:

Based on a review of the documentation which exists to describe the existing battery "A" and its associated battery racks, it has been con-cluded that the new battery "C" and its associated racks are of a quality which is greater than that of the existing battery "A" and its associated racks, when new; therefore, installation of the new battery "C" and its associated racks as it was. performed during the 1978 refueling outage both (a) enabled the 125V DC system modification project objective (i.e. provide increased separation in the 125V DC system) to be achieved by the end of the 1978 refueling outage, yet (b) did not give rise to an unreviewed safety question as defined by 10CFR50.59.

Page 4 of 6 Qualification Status of Battery Static Chargers:

With Respect to Final Requirements:

Except for the following open items, both of the subject static chargers (as they are currently installed at Oyster Creek) meet all of the Appendix II referenced codes and standards:

a.)

Although the 460V AC input breakers to, and the 125V DC output breakers from, the chargers are physically identical to the breakers which will eventually be installed as 1E qualified breakers, the currently installed breakers lack QA documentation.

The breakers which we anticipate installing as 1E qualified breakers recently arrived at Oyster Creek and, provided the QA documentation is in order, they should be installed within the month.

b.)

A shake test was perfomed pursuant to the guidance of IEEE 323-1974 and 344-1975, and on Friday, January 19, 1978, the test report was received by JCPSL. This document is currently being reviewed by JCP6L, the review should be completed within the month.

In summarizing the static chargers equipment qualification status, following installation of the above noted IE qualified breakers, and JCPSL review and approval of the shake test report, both static chargers will meet all the requirements of the Appendix II referenced codes and standards.

With Respect to Interim Requirements:

Based on a review of the documentation which exists to describe the existing battery "A" chargers and physical examinations thereof, it was concluded that the new static chargers are of a quality which is greater than that of the existing chargers (i.e. MG set charger and static charger ); therefore, installation of the new static chargers as it was performed during the 1978

Page 5 Of 6 refueling outage both (a) enabled the 125V DC system modification project objective (i.e. provide increased separation in the 125V DC system) to be achieved by the end of the 1978 refueling outage and yet (b) did not give rise to an unreviewed safety question as defined by 10CFR50.59.

Qualification Status of Motor Control Center:

With Respect to Final Requirements:

The only motor control center added with the subject modification is desig-nated DC-2 on the drawings which were forwarded in our April 4, 1978 submittal, and except for one open item, the motor control center as it is currently installed meets all of the Appendix III referenced codes and standards.

The one open item relates to a timing relay which failed in a test of a"fype" unit. The cause of failure at this time appears to be related to the relay's having been thermally aged at an excessive rate.

The test procedures for the subject type test are still being reviewed and it is currently anticipated that thermal aging at a slower rate (while still achieving the same cumulative amount of thermal aging) will result in the relay!s qualifying per the requirements of IEEE 323-1974.

Currently, we are attempting to complete these additional tests by the end of March,1979, and should these tests be accomplished satisfactorily, the motor control center will oc qualified per the requirements of all the Appendix III referenced codes and standards.

With Respect to Interim Requirements:

Based on a review of the documentation which exists to describe the existing motor control center DC-1 and physical examinations thereof, it was concluded that the new motor control center is of a quality which is greater than that of motor control center DC-1; therefore, installation of motor control center DC-2 as it was performed during the 1978 refueling outage both (a) enabled

Page 6 of 6 the 125V DC system modification project objective to be achieved (i.e.

provide increased separation in the 125V DC system) by the end of the 1978 refueling outage, yet (b) did not give rise to an unreviewed safety ques-tion as defined by 10CFR50.59.

APPENDIX I

Ehe.ro *:peellicatlou ?HH-il l h;r.co lh r.

O

. /.? 3/ 7M Storage Hat tery

.f cp t;;,

p,. v. o ifg3773 2.

STA: DARDS A:;p rolill (Cont 'd)

ANSI - A& r ican ::at ional 9tandards Institute ANSI C1

-lons. - ::ational Electric Code - Article No. 480 ANSI C18.1-193 - Specifications for Dry Cello and Batteries I;E;iA - National Elec t rical :tanuf acturers' Association NEMA 1B1-1971 - Definitions for Lead-Acid Storage Batteries IEEE - Instituto of Electrical and Electronics Fncineers IEEE 450,lp } - Recommended Practice for !iaintenance Testing and Replacement of Larl;e Stationary Type Power Plant and Substation Lead Storage Batteries IEEE 484 g - Recomnended Practice for Installation Design and Installation o f Large Lead Storage Batteries for Generating Stations and Substations In addition to the above, all Class IE and Seismic Category I equipment are designated Class I F. in accordance uith IEEE 308-197a

- " Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations" and shall comply with the following standards:

ANSI - American hational Standards Inst it ute ANSI N45. 2. 2 1972 - Packaging, Shipping, Receiving, Storage and llandling o f Items for Nuclear Power Plants IEEE - Incritute of Electrical and Electronics Encineers IEEE 323-1974 - Standard for Qualifying Class lE Electric Equipnent for Nuclear Power Generating Stations IEEE 344-1975 - Recommended Practices for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations NRC - Nuclear Regulatory Commission Regulatory Guide 1.38 1976

- Quality Assurance Requirements for Packaging, Shipping, Receiving, 9torage, and liandl ing of Items for Water-Cooled Nuclear Power Plants 2

9 APPENDIX II

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.lCI't l thw i s i on 0,

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' l'l.1:11 'I'Al'lth,.'l5-71 l. It nW ) )

i

'; t.i t i on !;. i t t c r y C h i r y,r r gtI A1. l F I C u l o:: nic CI.A% IE l.qli f i' :!:t: r

't he equ i;oient described in t h i r, Specification i: designated Cla-1; in accordance with IEEE Specification 333 - IEEE criteria tor Clat IE electric systtms f or nuclear poser generatin2; itations.

The Seller shall be totally responsible for tiie performance testing and quality control necessary to qualily, the Ba t te ry Ch arger:, a nd a ll associated caterial covered by this Specification as Class IE equipment in accordance with the following.

Ebasco Spec 860-78

- Quality Control for Supplier's of Equipment and Services.

IEEE 323-74

- General Guide for qualifyine Class I Electric Equipment ior Nuclear Poacr Generating Stations.

IEEE 3' 4-75

- IEEE Recoana n led Practice for seismic Qualification of Class I E Equ ip.nent for Nuclear Power Generatin,;

Stations R1dialinn This equipment will be subject to radiation exposure. All mtterial and components w'aich would not normally require earlier replacement shall be designed for 40 years of normal plant operation plus one year of Post Accident Operation, during which ti:re they will be exposed to a f

max. integrated radiation dose of 1 x 10* Rads.

The Seller shall submit a list of any components which will not meet with this requirement and will therefore require early replacement.

Seller shall submit proof that the remaining, mtterial will not fail due to degradation resulting, from thin radiation exposure.

0 e

4 APPENDIX III

i b asco Speci fi ca t i on 210- 7.3 l,.h a s co Revision 0 - 3/'.1/ 78 B ot oi

(.

.t t o !

t.c i.t c : -

ti r D

N"VISI " U-1/19/73 Use in Central Pe wi "totion Pai' :u

- Specilic

o l i c ae n t -

(p:it.1 n ci:ist: n n i',', J r 1 ( H' l in

'.T 01

':T/J:!n :%

'l h o equip 'nt describal in thit Specil;catial i: de;3"nated Clon IC in ac co rdac.ce wi t h I CI C Si.;tification 30, - I t' : c r i t e ria for Cla > 'JC elec-ior nuclea r pzer genera tion >tations.

tric syrt..

'l h e Selle c nhall be totally responsible f or the pe r f o r. u n e, testing and quality control necessaty to qualify, th< notur contin) cent e r and oli as Clar' 1!: e q u i pt..e n t in ascociatr d uaterial co /e red by. t h1 S p e c i f i ca t l'on accordance with the following:

1:basco Spec 860-7S - Quality Lontrol for Supplier's o f E q u i pr.e n t and Servi ct:.

l!:!:C 323-74

- General Guide for Qual i f y m, Cl a:.s I Electric Equipment for. elc a r Pe...f r Ce n' a c i n stations.

II:1:C 3 'e 5 - 7 5 ICLE P.ecou en b d Pcactic. for n irric Quali ficaticn m

Class 1E r:q m p: 2nt far.ucle a r rove r Genc i a t i ny, S tati c as si,i o31 n:, Hoceluing, 9 to r ve ene! P'ndlin-N'S I S45.2.2-1972 pa ct:a"i n:,

i o f i t e :.a f o r ' u c ic a r i'u.ze r 1,'l a n t; (Luvel L).

02 RA DIa.TT m This equipr-ent vill be subject to radiation cuposure.

All ruterial and coa-r e pl a i :.c a t

t. ball be desi: nod ponents chich would not normal 1y require eat 1 i( r f or 40 years of nutral plant operatina plus -ne vear o f P e. t -Je: c i s'. nt tw t:lioa, 1 to a total ints, t.l radiition du-:e during which t in - t he y t,ill be e::pos of 1x 10* Rade.

The Selle r shall subc.i t a list o f :. n :, c c..pene n t s chich vill not -eet eith this regni re: 2nt and will t h..re fore rcquite earl: replaett at.

? ! l e t-that'.

.aiait proof t hat the remaining :n t e r ial v i ll not fail Ju-tm 1 m dition resultin, from this radiation exposure.

, U.U.I FI CATI o.N panCRA't Q

03 Seller shali furnish an outline o f hi n qua li fi ca t i c,n p rograt i (..h i c h c c e.p l i e r.

with t.h<

reqeiren.:ntr. of II:1:C 32 3 and J El:C 34'; S t aad a i L. ) ui t h ti e hil for pur-chasers re viev a nd cot. :.ie n t s.

Selle r shall f urnish t he full prova., for par-chacers review a f te r contract auard.

I has co Sneci ri, cat i on 210-7; I:basco Revision 0 - T/ Tl/ 78

!:o t o t Control La.ttc.

ar

'I CP I' h NOVISI"" O ~ 4/19/78 l'a e i n Cer.t ra l Pu.er Station Part 'lu o - C.neral 1cepiire ats 1.

ScoPI:

This 1:. Part 'Iv o o f a Upecifit at ion enverin., Control Centes s and acrociat ed eq u i p r.e n t for m:c in Centrd Pawer St u ion.

., nel Pa r t Two which are teatually

.1 This speeli'catica tannists of h it One depenJent.

Beth pait, are c'..e nt ial for correct.ad complete interpretatien.

Part Oae cove:s si e c i f i c r e w i r e r"_ ' t - an! in :1u !ca an iter.ized list of eqci l-r..e n t to be turnished.

Part 'f u o c o v._ r u cc:nq al rcquirerents, rhich are o r d L.' t r -

ily uni f o ru f o r all ro j e c u.

'.!he n r equ i r. '.c at s o f t he tya parts c on f l ic.t,

those vi Ias t One shali gavi.rn.

.2 It is not the intent to.:peci f y details of c;esign and cons truction ex-cept where necessary te establish nerformance requ iceu nt s, nor f r.

it intended to set fetth those p e r f o r:ian ce requirenents which are adequately specifieJ by applicable standards 2

_STA?:DAngj.

applicable published All equi pmnt shall neet the requirements of the la t.

u s tanda rJ a o f A:. 5 tandards ]nstitute, I ns ti tt.t e of Electrical and Electrc.ic Enginec r;,

ational Elec tric Cade, Unde ruri t e rs laboratories U! F53 and 'D ti caal Elec t ri cal 'Onu f ac tu re rs '

soc ati on, in tha above Order of pre fe ct uco.

Material; anJ cervice, hereunde r chall cei ply ui th the latesc revisions c f t h.

Occ upa tional % fe ty an.1 i!e al t h Ac t of 1970 and all applicable :tandar'; tl.ci,_e m h.

3.

BASIS OF RAT!'C All equipr.ent shall be suitable fer the ratcd laad current and short-circuit currents at rated valtar,e (as specified in Part One of this Specification).

.1 Seller shall carefully revicw Purchascr's selection of breakers, starters, as well as ratine,, space requirenanta, trip elcrents

..n.1 a l l other conNr..at..,

e c, and advis: P;rchaser af any equiprent vaich may not tw c t the functicnal requirement; af this $pecificitian eller cupply and be respor;ible for a It i r, the Purch mer's intent that c conpletely

'rtiina*ud breaker, starter, ani theral overicx '; sten whica tect..

pr otec t t !.c m tors frc. ev t-vill permit c ea t i nuou.,.. p e r a t i c. n,

Joadi; utcessfull: li: connect the

.urce or pwer - act all short-circuit specificJ in Part one; vi ll e,

ra t.

preerly und - Lla supply cc a -

conditi as a,

dition s pe c i fi c o in Part One, l a t a r, ca ph.'. 0,

.it..t J.-

.y to tlc oceakera

d starte s not inclecin:; the rmal ove r l oad he a te r e let ten ts.

I I b:rico I:ev i i.m 11, 3/';/1'M I h.r'. co ' pe c i l'i.11 i on

'l.

71

. h 'l' T,1, keyinion 0, 1/lq/7p Stailon Ita t t. iy Chainer 1.

The purpo.e of thi: Specification it to desetihe tin-re-SCol'!:

quirements for 2

12) vol t static battery charging rectifiers.

(numhcr)

The bat t e r y cha r no r: shall h: complete in all respect,.nu! he fur-nished with all required acci sories, whet he r or not t h e :, are detailed herein.

.1

'lha Seller shall furnish alI the equipment necessary to perform tho 5.u n c t i en s described in thi, Speci fi calica.

In this respect, the Seller's r e:, pon s i b i l i t y shall include but i<. not limited to the specific i t t m:; of equipnont listed in t h i r, Specification.

All itema sup-plic3 most he compatible.

2 It is not the intent to ;pecify details of design atal cen-striction cxcept 'ci.e re ne ce tary to e;tablish perfotrance requirements; not is it in t en led t o se t forth those pe r fo rua nce t equi rer.e nt s whi ch art adequat c h speci fied by applicable standards.

2.

'Ih e design of the ;tation hattery charner and accessories as STANDARDS we I as t he ru te ria l t used in their construction shall be as recormended by Feller unless specitied hs Purchaser.

'I b e hat tery charner shall comply witl all cpplicabl. r e',u l a t io ns, n a t e t sj co les, ;peci f ica tionn and standards, acknowledged and accepted incl uding applicable t e clin i c al de fini tions as in the 2 ndust r,.

'l h o is ;ue date or revinien ut the standards and code:

shall be as indicated below.

Eq u i pme r. t shall comply with but shall not be limited to the following:

I E_f:E - Institute of Elect rical and Elect ronics Encineers IEEE 59-62

- Semi conductor nec t i fier Component s NEi!A - Na t i onal Elect rical Manu fact urers Association t'EMA RI-2-66

- Gene ral Purpose and Communica tion lla t te ry Charge rs ANSI - Ar>orican National 4 t an da n!s institute ANSI N45.2.2-1972 packaging, Shipping, Receiving, Storar,e and llandling of Items for Nuclear Power Plants NRC - Nuc lea r Ec oul a t ory Comn i :, 4 i on Regulatory Guide 1.33-1976

- Quality As;atranco Requirements for Packanine,, Shipping, Receiving, Storaginn and ll.tudling of Itci, for Water-Cooled Nuclear Power Piants O

APPEtIDIX IV

1*

8 b.

Fire Detection Instrumentation Surveillance Requirements The inspector verified that procedures have been prepared for the following Fire Protection System requirements:

Fire Detection Instrumentation Fire Suppression Water System Spray and/or Sprinkler Systems Fire Hose Stations The inspector verified that the fire detection instrumentation procedures for each fire detection area / zone listed in table 3.12.1, 3.12.2, and 3.12.3 of technical specification amendment No. 29 requires testing to be performed 2s specified in section.

A review of the data for the listed proc :do es verified that r

the above table requirements were being :omplied with.

Fire Detection Instrumentation, Nc. 645.4.005 Fire Suppression Water System No. 645.4.001 - weekly No. 645.4.004 - mon thly No. 645.1.007 - yearly Spray and/ Sprinkler Systems - Preliminary i

I Fire Protection System - Pump and Isolation valve operability -

one/ month No items of noncompliance were identified.

8.

125 Volt DC Power System Modification

~~~

The new DC distribution system consist of one 60 cell battery (de-signated as Battery 6) two 100 percent capacity solid state battery chargers, and one distribution center C.

.. y; -

9 Soecifications, Purchase Orders, and Test Results a.

iF -

The inspector reviewed the following documentation associated i

with the 125 v DC modifications.

Station Battery Charger Specification, dated February 23, 1978, No. 213-71 Station Battery Charger Procurement Specification, dated July 10,1978, No. 210-77-7 Packaging and Shipping Manual Specification, dated May 9, 1978 No. 74-50 Storage Battery Specification, dated February 23, 1978, No. 288-77 Class IE Signal and Power Cable Specification, dated April 27,1978, No. 7024 Seismic Test Report for Station Battery Charger, dated October 16-17, 1978, No. 78-35-3 Material Conformance Identification Sheets Form No. 3005-01, dated December 7, 1977 Quality Data Record Receipt Inspection Form 4012-01, i

dated June 15, 1978 and PQA #7835, dated September 27, i

1978 j

Gould Test Log Data Sheets for the Batteries, dated t

October 19, 1978, Test No. 66 i'

Rockbestos Company Cable / Wire Certification of Confonnance, dated June 8,1978, reference P.O. No.19334.

No items of noncompliance were identified.

b.

Installation Data The inspector reviewed the following installation procedures and data associated with 125 volt DC Power System Modifications.

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10 Special Procedure 78-18, dated June 12 Fabrication and Installa tion.""125 v DC Syste suBNl n u t Surport SMF1-Revision 2, dated tiovember The turnover data pickage I

following documentation:

22, 1978, included the (1)

Conduit Runs, PVI File tio.78-002 drawings (2)

Condenser Bay Restraints Drawings (3) Weld History Records g

(4)

Hanger Data Sheets, and, (5)

Visual Inspection of Welds-Reports

d 1978, entitled, "C Battery Structural S c o er 23, the following documentation:

ncluding 9

(1)

Steel Repair Procedure tio. 78-48, da i

ructura l (2) gust 15,1978 Weld History Record and Data Sheets d

(3)

Quality Assurance Inspection Report, Recap Sh and Dispositions.

Pulling Procedures 78-26, dated June 301 y

f u t ng and megger data sheets attached j

, 1978, and pulling /

i 125 VDC System Modification"C" Battery Roo Steel Installation Procedure #78-20 m Structural

\\

including the following documentation: dated June 16, 1978, l

i (1)

Quality Assurance Inspection Report, Recap She

(

i and Dispositions l

(2)

Records and, Welding, Burning, and Grinding Work Pe m s Da ta (3)

Sketch SK-1, dated September for mounting of roof fan / duct supports, with torque values 25, 1978 on 23' 6" elevation and anchor plates

,, - ev : ::-

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S 11 125 VDC fiodification Heating and Ventilation Installation Procedure #78-79, dated September 25, 1978.

This procedure required penetrations of conduits in the following areas:

(1)

Panel 9XF, Control Room (2) 460 volt Unit Substation l Al, l A2, and 1A3, 460 Volt Switchgear Room (3)

Panel DC-F-460 volt Switchgear Room, (4)

Battery Charger C1 and C2 - 4160 volt Switchgear Room, and, (5)

Computer Supply Inverter - Chemistry Laboratory, Mezzanine.

Above penetrations were sealed with BISCO SF-20.

This is the same material that previous ~ penetration modifications were sealed with.

No items of noncompliance were identified.

c.

Drawings The following drawings were used by the inspector in performing installation inspection, verification, and equipment layout i

location of the 125 VDC Power System Modification:

Room Conduit Layout South, Bottom and Tcp Layer 4160 volt Sketch, dated July 17, 1978 460 volt Control Rocm to Condensor Bay, to 4160 volt, Sketch dated September 28, 1978 125 Volt DC System Modification Panel Modification and Installation Procedure No. 78-19, dated June 30, 1978 and data sheets for the following panels:

(1)

Control Room Panel 9XF - Sketch (2) 460 Volt /DC-F - drawing G-3111-0B q

2

--**;l~l,**

'll~***!.*

' " ~ ~

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e' e

12 (3) 4160 volt /HVAC - drawing G-3039-1B s

(4) 4160 volt /Cl - drawing G-3039-1B b..

(5) 4160 volt /C2 - drawing G-3039-1B (6) 4160 volt /DC-C - drawing G-3039-12C and, (7) 75' elevation /DC drawing 1339-12C Cabinet Outline Static Battery Charger Drawing No. D --

1571-3 (PCP) 3 phase SCP Controlled Battery Charger Drawing No. D --

1571-3(PCP) 35-130-500 Battery Charger Wire Diagram Drawing No. D --

1571W (PCP)

BISCO Redi-Kit-Bisco SF-20, Specification No. RK-03 made with DC3-6548.

No items of noncompliance were identified.

l d.

Testina The inspector reviewed the test procedures and data associated with the system verification of the 125 volt DC system modification.

The following listed procedure and associated data sheets were reviewed by the inspector.

Battery "C" Electrical Tie Ins Procedure #78 '.Co dated October 28, 1978.

This procedure instructed safety load i

transfers from existing 125 Volt DC system Battery "A" to i

the Battery "C" 125 volt DC modification system.

Section 6.0 of procedure entitled Testing, required verification of all class IE system on tne "C" battery bus to be tested prior to start-up.

Oyster Creek Station Battery "C" Charge and Discharge Test, Procedure #78-105 dated October 26, 1978.

Battery Room "C" HVAC System Check-Out and Start-Up Procedure #78-101, dated October 17, 1978, Revision 1,

=

FSR 303E1612, and attached data and chart sheets.

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c.---

4 a

13 Battery Room "C" Charger C1 and C2 Pawer Conversion Products Battery Chargers Check-Out/ Start-Up Procedure #78-99, dated October 17, 1978, Revision 1, FSR 303E 1512, and attached data and chart sheets.

MSA Combustible Gas Detection System, Series 500, and attached Instruction Manual and data sheets.

fio items of noncompliance were identified.

9.

Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations.

Unresolved items disclosed during the inspection are discussed in Paragraphs 2 and 6.a.

10.

Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection.

The inspector summarized the purpose and scope of the findings.

The licensee acknowledged the inspector's findings.

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