ML17334B109

Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components:Cook 1 & 2, Final Informal Rept

ML17334B109
Person / Time
Site:	Cook
Issue date:	04/30/1987
From:	Vanderbeek R EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML17334B107	List: ML17334B106 ML17334B109
References
CON-FIN-D-6001 EGG-NTA-7329, GL-83-28, TAC-53661, TAC-53662, NUDOCS 8706080115
Download: ML17334B109 (26)

Text

TECHNICAL EVALUATION REPORT

'.CONFORNNCE:TO GENERIC LETTER 83-28, ITEN 2;2.-'l-,-

.. '.EgUIPNENT 'CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COHPONENTS

COOK-1 AND -2 Oocket Nos 50-315 and 50-316 R. VanderBeek Pub11shed Apr11 1987 Idaho Nat1onal Eng'1neer1ng Laboratory EG&6 Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for the 4

41" U.S. Nuclear Regulatory Coam1ss1on Mash1ngton, D.C. 20555 Under OOE Contract No. OE-AC07-76I001570 FIN No. 06001

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ABSTRACT i 1 Th1s EQM Idaho, Inc., report prov1des a rev)m of. the subilttals'-from'onald C. Cook Nuclear Poser Plant, Un)t Nos. 1 and 2 for,'conformance to Generic Letter 83-28, Item 2.2.1.

Oocket Nos. 50-315 and 50-316 TAC Nos. 53661 and 53662

V FOREWORD

.This',report=5s-supp15ed.as par4 of the program for conformanci to.Gener5c Letter 83-28 "Requ1red Act1ons evaluat1ng'15censee/appl5cant Based on.6erier5c.. Impl5cat1ons of Salem ATMS Events." Th1s work,5s.-be1ng

. conducted.,:,for,-the'U;S.; Nuclear Regulatory Cone5ss1on, Off1ce of Nuclear Reactor Regulat1on, 01v1s1on of PMR L1cens1ng-A, by EG&G Idaho, Inc., NRR and I&E Support Branch.

The U.S. Nuclear Regulatory Conm1ss1on funded th1s work under the author1zat1on B&R No. 20-19-10-11-3, FIN No. 06001.

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'ocket Nos. 50-315 and 50-316 TAC Nos. 53661 and 53662

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. CONTENTS ABSTRACT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 00 ~ ~ ~ ~ ~ 00 0 ~ ~ 0 ~ ~ 000 ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ 0 ~ 0' ~ ~

~ ~ .000"0"o ~ ~ ~ . 'll" F OREWORD ........................................... 1 ~ 1 ~ 00 ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ 0 111 INTRODUCTION .....-..-... - -.- .-. -. . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~

2. REVIEM CONTENT AND FORHAT ............-..--.. " ~ 0 ~ ~ ~ ~ 0 ~ 00 ~ ~ ~ ~ 0 ~ ~ ~ ~

3. ITEH 2.2.1 PROGRAH ...... - -. - -. - - - - - .. " ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 3.1 3.2 Gu )dellne ................................ ~ ~ ~ ~ ~ 000 ~ ~0 ~ 00 ~ ~ ~ 0 ~ 3 E valuation ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ ~ 0 ~ ~ 0 ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ \~~0~~~~ 3 3.3 C onclus)on \ ~ 0 ~ ~ ~ ~ ~ ~ 0000 ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ ~ 00 ~ ~ ~ ~ 0 ~ 0 ~ 00 ~ ~ 01 ~ 00 ~ 00 ~ 1 ~ 3 ITEH 2.2.1.1 IDENTIFICATION CRITERIA ......... 0 ~ ~ ~ ~ 0 ~ 0 \~0~~~~~~0~

4.1 Gu )delhne ................................ 1

~ 0 ~ ~ ~ 0 0 ~ ~ ~ 04 ~ ~ ~ ~ 1 ~ ~ 4 4.2 E Va1 ua0 on ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 1 ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 0 ~ ~ ~ 4 4.3. C OncluS)On 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 0 ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ 0 ~ 4 ITEH 2.2.1.2--INFORHATION HANDLING SYSTEH ..... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

5.1 G u1delhne ................................ ~ ~ ~ ~ 1 ~ ~ \\0 ~ ~ ~ ~ ~ ~ 1 ~ 1 5 5.2 E valuation ............................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ 5 5.3 C onclushon ...............................; ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 1 ~ ~ ~ 0 ~ ~ ~ 5

6. 'ITEH 2.2.1.3 USE OF EgUIPHENT CLASSIFICATION L ISTING ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ,6 6.1 G u1del)ne ................'................ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 6.2 E valuat)on ............................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ 6 6.3 C onclus1on ............................... ~ ~ ~ ~ 1 ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ 0 0 ~ 6 7- ~ ITEH 2.2.1.4 HANAGEHENT CONTROLS -.----.--.-... ... . ~ ~ ~ -~- ~ ~ ~

0 7.1 Gu1de11ne ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ \~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 7

7. 2 E va lua t1on ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 7 7.3 Conclus1on ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ \~~~~0 ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 7

8. ITEH 2.2.1.5 DESIGN VERIFICATION AND PROCUREHE N T 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

8.1 Gu)delhne .................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ 0000 8 8.2 Evaluat1on ................... ~ ~ ~ ~ ~ 001 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 0 8 8.3 Conclusion ................... ~ ~ 0 ~ ~ ~ ~ 0 ~ 0 1 ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 8

9. ITEH 2.2.1.6 "IHPORTANT TO SAFETY'OHPONENTS ............;.....

9..1 Gufdel1ne ..................................................

10. CONCLUSION .......... ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 REFERENCES ........................ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

'- ONF R C '@ERE IC83~28'<- N 2.2.

UIPHENT CL'ASSI CAT ON .OR.ALL'4THER SAFETY-RELATED COMPONENTS:

COOK'*1 "AND -2

1. INTRODUCTION On February 25, 1983; both of the scram c1rcu1t breakers at:Un1t 1 of the Salem Nuclear .Power Plant fa1led to open upon an automat1c reactor tr1p s1gnal from '.the Pea'ctor pre'eat)on'4ystea.-'h1s- 1nc1dent was term1nated:

manually::by 'themperato'r ab'out'30'econds wfter 'the"1n1t1at1on of the automat1c'r1p'<1gnal She fa41ure"'of %he x1'rcu1t breakers i>as determ1ned to be related'-to 'the's't'1ck1rig 'ofthe Under Voltage Cr1p attachment. "Pr1or to th1s 1nc1dent;-on February 22; 1983, at Un1t 1 of 'the Salem Nuclear Po~er Plant, an automat1c tr1p s1gnal was generated based on steam generator'ow-low level dur1ng plant startup. In th1s case, the reactor was tr1pped manually by the operator almost co1nc1dentally w1th the automat1c tr1p.

Follow1ng these inc1dents, on February 28, 1983, the NRC Execut1ve D1rector .for Operat1ons (EDO), d1rected-the NRC staff to 1nvest1gate and report on the gener1c 1mpl1cat1ons of these occurrences at Un1t 1 of the Salem Nuclear Po~er Plant. The results of the staff's 1nqu1ry 1nto the.

gener1c 1mpl1cat1ons of the Salem un1t 1nc1dents are reported 1n NUREG-1000, "Gener1c Impl1cat1ons of the ATMS Events at the Salem Nuclear Power Plant." As a result of th1s 1nvest1gat1on, the Comn1ss1on (NRC) requested (by Gener1c Letter 83-28 dated July 8, 1983 1 ) all 11censees of operat1ng reactors, appl1cants for an operat1ng 11cense, and holders of construct1on perm1ts to respond to the gener1c 1ssues ra1sed by the analyses of these two ASS events.

Th1s report 1s an evaluat1on of the responses subm1tted by Ind1ana and H1ch1gan Electr1c Company, the 11censee for the Donald C. Cook Nuclear Po~er Plant, Un1t Nos. 1 and 2 for Item 2.2.1 of Gener1c Letter 83-28. The documents rev1ewed as a part of th1s evaluat1on are 11sted 1n the references at the end of th1s report.

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2p'f'REVIEW 'CONTENTS" AND'jORNJj

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V ~ p Item 2.2.l of Generic Letter 83-28 requests the licensee or applicant to submit, for the staff rev1ew, a descr1pt1on of their programs for safety-related equipment class1f1cat1on 1ncluding support1ng 1nformat1on, 1n cons1derable detail, as 1nd1cated 1n the guidel1ne sect1on for each sub-item within this report.

As-previously .ind1cated, each of the six sub-items of. -Stem 2;-2;l: is evaluated in a separate. section in which: the guideline -is:,presented; =.yn evaluation -of .the. licensee'slapplicant':s response 1s. made; and.conclusions about the programs of the.l4censee or applicant for. safety-.relaied. " .-.

equipment. class1f1cation are dram;.

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" O':ITN"2 2;3='. PROGRAM; .

3. l Guideline L1censee and applicants should conf1rm that an equipment classification program 1s in place which will prov1de assurance that all safety-related components are des1gnated as safety-related on plant documentation such as procedures, system descr1ptions, test and ma1ntenance 1nstructions and in 1nformat1on handling systems so that personnel performing act1vities that affect such safety-related components are aware that they are work1ng on safety-related components and are gu1ded by procedures and constraints. Licensee and.applicant: 'afety-related responses which:address the:features of this program are evaluated.in the remainder of th1s report.

3.2 Evaluation The l1censee for the Donald C. Cook Nuclear Power Plant, Unit Nos. 1 and 2, responded.to,,these:requirements w1th submittals -dated 4

November 4, 1983, 2 March 30. 1984, 3 and December 19, 1986. These subm1ttals include information that describes their existing safety-related equipment classification program. In the review of the licensee's response to th1s item, it was assumed that the information and documentat1on

.supporting this program is ava1lable for audit upon request.

3.3 Conclusion The staff concludes that all the bas1c requirements of the equipment classificat1on program are in place and address the concerns of the 1tems of Item 2.2.1 of Gener1c Letter 83-28.

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~ -4. ITN 2;2!'i';O'-".-'XOENXFICATXON CRITERIA 4.1,6ui del1ne The applicant or licensee should confirm that their program used for equipment class1ftcation includes cr1teria used for identify1ng components as safety-related.-.

4.2- 'Evaluation The *licensee's response states:Chat the cr1teria for determining safety-related:structures', systems, and components are contained in the present corporate procedures. The criteria ~ere 1ncluded 1n the response and conform v1th the definit1on vith1n Item 2.2.l of Generic Letter 83-28.

4. 3 Conc 1 us 1 on We find that the cr1ter1a used in the identificat1on of safety-related components meets the requirements of Item 2.2.l.l and are acceptable.

~~ i--" 5. -'. XTNi2 2.1.2 'XNFORNATTDN HANDLING SYSTEM~

5.1 '.Gu1del1ne The 11censee or appl1cant should conf1rm that the program for equ1pment classificat1on 1ncludes an informat1on handl1ng system that 1s used to ident1fy safety-related;components. The response should confirm that:this information hapd)4ng;system includes- a l1st:.of saf ety-related equipment and that".procedures.exist- which,. govern:1ts development and validation.

5.2 Evaluation c ~

The licensee's response states that safety-related components (w1th known exceptions) are entered in a computer1zed list known as the N-L1st.

Structural items and p1ping are entered as a s1ngle line 1tem. Electr1cal 1tems such as relays, switches, conduit, fittings, and trays also are covered by single line 1tems.

The licensee.has confirmed that,a new classification program has been 1mplemented. Jhis new program consists of a new computerized component class1ficat1on record which lists-all:.plant components, their safety class1fication and the1r procurement and gA requ1rements. Cross-references ta draw1ngs and relevant plant and corporate procedures w1ll ensure that the safety role of a component 1s kept 1n focus whenever a component is taken out of service, bought, ma1ntained, replaced or returned to serv1ce.

The fob control classification w1ll rely on the record.

5. 3 Conc 1 us 1 on The licensee's response for th1s item is considered to be complete and is acceptable.

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6. 'JTBl 2l2 1S-":4SE OF-:KgUIPNENT CLASSIFICAHON t/STING-';1 Guideline The licensee's or applicant's description should conf1rm that the1r program for equ1pment classification 1ncludes cr1ter1a and procedures governing the use of the equ1pment classification information'.handling, system-.to determ1ne that an activity 'is-'safety-related and'what procedureS'or maintenance, surveillance, parts replacement'<and other-activit1es.':

def1ned in the introduction to 10 CFR 50, Appendix B, apply to.

safety-related components.

6.2 Evaluat1on The licensee's response 1ndicates that respons1ble stat1on personnel use the N-List and corporate procedures to des1gnate the safety class1f1cation of the equ1pment and the procedures required to perform the work. The safety classification and procedures are indicated on the Job Order form used for all repa1r and modification work performed at the plant; If any'one within the'plant is unsure of" the class1f1cation of a component,-he 4s required to check.with'he responsible American Electr1c Power Serv1ce. Company (AEPSC) cognizant engineer.

6. 3 Conc lus 1 on The licensee's response for this item is considered to be complete and is acceptable.

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',7','.1TEH 2.2.1.4 NNAGEHENT CONTROLS H

7.1 Guideline The appl1cant or 11censee should confirm that the management controls used to ver1fy that the procedures for preparat1on, val1dat1on and routine utilizat1on of the information handling system have been followed.

e'.2 Evaluat1on The licensee's response states that the equality Assurance Department I

performs audits of act1vit1es covered by the plant instruct1ons and procedures and notifies appropriate plant management of any def1ciencies noted. Thus, the audit program provides add1t1onal ver1fication of the rout1ne ut1lization of the 1nformat1on handling system.

7.3 Conclus ion The licensee's response to this item 1s cons1dered to be complete and is acceptable.

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ITN 2.2;1-5 C

8- OESIGN VERIFICATION'AND PROCUREHEHT

8. l Gu1del1ne The appl1cant's or l1censee's subm1ttal should document that past usage demonstrates that appropr1ate des1gn ver1f1cat1on and qual1f1cat1on test1ng 1s spec1f1ed for the procurement of safety-related components and parts; The spec)f1catlons~should.1nclude qual1f1cat1on test1ng for expected safety serv1ce cond1t1ons and prov1de support for the appl1cant',s/1)censee! s rece1pt of test1ng,documentat1on to support the l1m1ts of 11fe recoaeended by the suppl1er. If such documentat1on 1s not I ~

avaflable, conf)rmat1on that the present program meets these requ1rements should be prov1ded.

8.2 f valuat1on The 11censee's response states that the current spec1f1cat1ons used to procure nm or replacement components 1dent1fy normal and acc1dent serv1ce cond1t1ons or reference appl1cable codes. gual1f1cat1on test1ng and performance.evaluat1on 1s requ1red for harsh env1ronments and test reports of th1s qual1f1cat1on test1ng are requ1red to meet the cond1t1ons of the spec1f 1ca t1ons.

Pr1or to future use for procurement, each spec1f1cat1on sub]ect to the requ1rements of 10 CFR 50.49 w1ll be rev1sed to 1nclude the requ1rements that the vendor establ1sh serv1ce l1fe by test or performance evaluat1on and requ1re the vendor to supply documentat1on 1n support of the serv1ce 11fe qual1f1cat1on.

8.3 Conc 1us1on The 11censee's response for th1s 1tem 1s cons1dered to be complete and 1s acceptable.

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ITEN 2.2 1- 6 '"IHPORTAHT, TO SAFETY'ONPONEIPS 9; 1 Gui del ine Generic Letter 83-28 states that the l1censee's or appl1cant's equipment classification program should include (in addit1on to the safety-related components) a broader class of components designated as "Important to Safety." However,.since the gener1c letter does not requ1re the licensee or applicant to t'urnish this 1nformation as part of their response, revim of this item vill not be performed.

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10. CDHCLUSION Sased on our revi~ of the licensee's response to the spec1f1c requirements of Item 2.2.1, ve find that the information provided by the licensee to resolve the concerns of Item 2.2.1 meet the requirements of Generic Letter 83-28 and is acceptable. Item 2,2.1.6 was not rev1eved as noted in Section 9;l.

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4 E ll. REFERENCES

l. NRC Letter, D. 6. Eisenhut to all Licensees of Operating Reactors, App11cants for Operat1ng License, and Holders of Construct1on Permits, "Required Actions Based on Generic Impl1cat1ons of Salem ASS Events (Generic Letter 83-28), July 8, 1983.

2. Indiana and H1chigan Electric Company letter, H. P. Alexich to D. 6. Eisenhut, NRC; November 4, 1983, AEP:NRC:0838A.

3; Ind1ana and Hichigan Electric Company letter, H. P. Alexich to D. 6. Eisenhut, NRC, Harch 30, 1984, AEP:NRC:0838B.

4. Indiana and H1chigan Electric Company letter, H. P. Alexich to H. R. Denton, NRC, December 19, 1986, AEP:NRC:0838M.

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.I-- * -.. . CI,Y . - ,=. ", -" 'I,GGUCLIANOOOULATONTCOGNATION I. httOht IHNjNthTAHOMTST TIOC~ V&Nao H~

Sttt,Stot - ',; '= BIBLIOGRAPHIC:DATASHEET EGG-kA-7329 St t INSthUCTIONG ON THt IISVthtt .. ' ~ ~

S. TITLS AHO SUSTITLt 1 LSAVt SLAING CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.1 E(UIPMENT CLASSIFICATION FOR ALL OTHER SAFETY-RELATED COMPONENTS: COOK-1 AND -2 4. OATS httOht COLMLtttO MONtH YSAN

l. AUTHOAISI April 1987 R. VanderBeek t, OATS httOh t ISSUGO April 1987 T.tthtOHMIHOONQAHISATIONNAMSAHOMAILINOAOOhtSSI eWA CO%I L GNO3SCTITASIUWIÃNCUIHT NUMSth EGSG Idaho, Inc.

P. 0. Box 1625 IN Idaho Falls. ID 83415 D6001 I IL SKNCCOAIHO ONQANISATION NAMt ANO MAILINO AOOhtSS Division of PWR Lfcensfng - A

(~ ZM O94al 11e, TY1t IÃ httOht Offfce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission IL tCHIOO COVthtO IlaAeeoeAIHI Washington, 'DC 20555 It SUtf LSMGNTANYHOTSS

13. ASSTNACT QOG aw& or Heel This EGI* Idaho, Inc., report provides a review of the submittal from the Indiana and Mfchfgan Electric Company regarding conformance to Generic Letter 83-28, Item 2.2. 1 for the Donald C. Cook, Unit Nos. 1 and 2.

I~ OOCUMtHT ANALYSIS ~ HSYWOIIOSIOSSCNPTOIIS IS AYAILASILITY STATtMGNT Unlimited Distribution IS SGCUAITY CLASSIAICATION

e. IOSNTI>lthaOPCN4HOGOTSNMS Unclassified ITIINneWd Unclassified

17. HUMSth

'l Distrib~- "'on:

Docket. ~es w/o Encl~

P. Kreutzer D. Wigginton PD III-3 1/2 August 7, 1987 DOCKET NO(S) . 50"315/316 H'r. John Dolan, Vice President Inaliana and Michigan Electric Company c/o American Electric Pamr Service Corporation 1 Riverside Plaza Columbus, Ohio d+3216 SUB JECT: DGNALf) C. COOK NUCLEAR PLAHXS The following documents concerning our review of the subject facility are transmitted for your information.

Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating Li cense, dated Bgis tH d C id ti,d gg Bi-Weekly Notice; Applications and Amendments d J129 to Operating Licenses Involving No 8g f33 Exemption, dated Construction Permit No. CPPR- , Amendment No. dated

+ Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation

Enclosures:

As stated cc: See next page 0FFiCEQ

'URNAggEJ ~~

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NRC FORM 318110/801 NRCM 0240 OFFICIAL RECORD COPY

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Distrib 'on:

Docket es P,';eQtzer D. Wigginton PD III-3 r/f July 27, 1987 DOC~ET NO(S). 50-315/316 Mr.. John Dolan, Vice President Indiana and? hchigan Electric Company

@'o American Electric Pamr Service Corporation 1 Riverside Plaza Columbus, Onio 43216 SUB JECT: II~T C. COCK EJCLEIt R PLANXS The following documents concerning our review of the subject facility are transmitted for your information.

Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding, of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License or Amendment to Faci 1 i ty Operating Li cense, dated Q Bi-Meekly Notice; Applications and Amendments to 0 crating Licenses Involving No Significant Hazards Considerations, dated July, 8rsee page(s) 3 Exemption, dated Construction Permit No. CPPR- , Amendment No. dated Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation

Enclosures:

As stated cc: See next page OFFICE/

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SURNAME/

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DATE/ 07/@/87 ~ ~ ~ ~ ~ ~~~~ ~~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~~ ~ ~ ~~~ ~~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~~ ~~ ~ ~ ~ ~~ ~ ~ ~~~ ~

NRC FORM 318 (IOIBOI NRCM 0240 OFFICIAL RECORD COPY

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