ML17331B173

LER 93-005-01:on 930420,10CFR50,App R Cable Tray Routing & Compliance Strategy Concerns Noted.Caused by Personnel Error.Appropriate Sections of Ssca & Fire Protection Program Manual revised.W/931230 Ltr

ML17331B173
Person / Time
Site:	Cook
Issue date:	12/30/1993
From:	Blind A, Mangan P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-005-01, LER-93-5-1, NUDOCS 9401100174
Download: ML17331B173 (9)

Text

ACCELERATED DISTRIBUTION DEiVIONST$MTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)

ACCESSXON NBR:9401100174 DOC.DATE: 93/12/30 NOTARIZED: NO I DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION MANGAN,P.C. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 93-005-'01:on 930420,10CF50 APP R cable routing &

compliance stategy conerns identified. Caused by personnel error. appropriate sections of SSCA & fire protection program D manual revised.W/931230 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ( ENCL I SIZE:

TITLE: 50.73/50.9 Licensee Event'eport (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB, 1 1' NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 1 1 NRR/DSSA/SRXB 1 1 1 1 RES/DSIR/EIB 1 1 1 1 EXTERNAL EG&G BRYCE i J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHYiG A ~ 1 1 NSIC POOREiW ~ 1 1 NUDOCS FULL TXT 1 1 D

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE'DOCUMENT CONTROL DESK, ROOii'I Pl-37 (EXT. 20079) TO ELliVIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28

Indiana Mi~"'qan Power Co:,'ook Nucle~ Plant One Cook Place Bridgrnan, Ml 49106 616 465 5901 INQlANA NlCHIGAN PQMfM December 30, 1993 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-74 Docket No. 50-316 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort S stem the following report is being submitted:

93-005-01 Sincerely, A. A.

~ ~ Blind ~

Plant"Manager

/sb c'.

Attachment B. Martin, Region E. E. Fitzpatrick P. A. Barrett III R. F. Kroeger M. A. Bailey Ft. Wayne NRC Resident Inspector B. A. Wetzel NRC J. R. Padgett G. Charnoff, Esq.

D. Hahn INPO S. J. Brewer B. A. Svensson rigelij j) Q

~ ~

~~

9401100174 93}230 PDR ADOCK 050003i6 S PDR

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMIS APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH TH'IS INFORMATION COLLECRON REOUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENTBRANCH (MNBB 7714), U.S. NUCLEAR REGUlATORY COMMISSION, WASHINGTON, DC 205554001, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME (1) DOCKET NUMBER (2) PAGE (3)

Donald C. Cook Nuclear Plant Unit 2 05000 316 1OF 7 TITLE (4) 10CFR50 Appendix R Cable Routing and Compliance Strategy Concerns DATE 5 LER NUMBER 6

'VENT REPORT NUMBER 7 OTHER FACILITIES INVOLVED 8 SEOUENTIAL REVISION FACIUTYNAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY, YEAR 05000 FACIUTYNAME DOCKET NUMBER 04POPOVER20 93 93 005 01 12 30 93 05000 OPERATING THIS REPORT IS SUBMITTED PURSUA NT TO THE REQUIREMENTS OF 10 CFR %: Check one or m ore) 11 MODE (9) 20.402(b) 20.405(c) 50.73(a) (2) (iv) 73.71(b) 20.405(a) (1) (i) 50.36(c) (1) 50.73(a) (2)(v) 73.71(c)

LEVEL (10) 100 20.405(a) (1) (ii) 50.36(c)(2) 50.73(a) (2) (vii) OTHER 20.405 (a) (1) (iii) 50.73(a) (2) (i) 50.73(a) (2)(viii)(A) (Specity In Abarract beiour and In Terd, NRC 20.405(a) (1) (iv) 50.73(a) (2) (ii) 50.73(a) (2) (viii)(8) Form 366A) 20.405(a) (1) (v) 50.73(a) (2)(iii) 50.73(a) (2) (x)

LICENSEE CONTACT FOR THIS LER 12 NAME TELEPHONE NUMBER 9ndude Area Code)

P. C. Ltngan - Appendix R Coordinator (614) 223-2020 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES NO SUBMISSION 61 yee, complete EXPECTED SUBMISSION DATE)

DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single. spaced typewritten lines) (16)

This is a follow-up report to LER 93-005-00.

Upon completion of certain design changes in 1986, RCS loop temperature indications and pressure indication were routed through the LSI panels to the Control Room. Thus, a potential fire which could fail all of the LSI panels would also fail this indication in the Control Room, thereby not complying with the requirements of 10 CFR 50 Appendix R. Such a fire was possible in any fire zone where both the normal and alternate power supply cables to the LSI panels were routed. This condition was corrected in 1990 with the completion of design chahges which provided additional control Room RCS temperature and pressure indication which was not routed through the LSI panels.

This update to the original LER is being submitted to appraise you of the results of the evaluations that have since been performed. The evaluations have resulted in a number of changes to the safe shutdown equipment database.

However, no additional cases of non-compliance with Appendix R were identified.

NRC FORM 366 15-92)

NRC FOAM 388A U.S. NUCLFAA AEGULATOAYCOM APPROVED DMS NO,3(500)DS (6()8)

ESTIMATED BVRDFN PFR RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN FS'TIMATE TO THE RECORDS TEXT CONTINUATION AND REPOATS MANAGEMENT BRANCH IP.530), V.S, NUCLEAR AEGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3(500(OS). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME ((I DOCKET NUMBER QI LER NUMBER IS) PAGE I3)

YEAR w% SEOUENTIAL ,,H REVISION ssUsse(R NUsSOFR Donald C. Cook Nuclear Plant Unit 2 p 5 p p .p 3 1 6 9 3 0 0 5 0. 1 02 or0 7 TEXT (It mare saese is seoeeed. use edde'oas(iVRC Arm3$Li'sl l)TI Descri tion of Event Zn 1992 a multi-discipline team of engineers was chartered to ensure that Cook Nuclear Plant meets and can demonstrate compliance with the requirements of 10CFR50 Appendix R. As part of the process of reviewing and updating the cook Nuclear Plant Safe Shutdown documents it was 'discovered that we had requested and received authorization from the NRC to. change the automatic aspect of Capabilities'ssessment the CO2 suppression system to manual operation in Fire Zones 23, 24, 26, and 27. On 4-20-93 our documentation indicated that these fire zones should have been categorized in the Appendix R strategy of ZZI.G.2.c, whi.ch requires automatic fire detection and suppression.

The subsequent investigation concluded that the condition reported on 4-20-93 is not reportable because the requirements of Appendix R IZI.G.l are met i.n Fire Zones 23, 24, 26 and 27 wi.thout automatic fire suppression. Therefore, the condition is not reportable per 10CFR50.72(b)(ii)(B).

An interim LER was submitted because our investigation of the 4-20-93 condi.tion identified new conditions that were still preliminary in nature and under review. The conditions described in this LER occurred in the past and do not reflect the current conditions physically in place at Cook Nuclear Plant.

Since the interim report, these conditions have been evaluated. This evaluation involved an extensive revt.ew of all electrical circuits associated with the safe shutdown instrumentation for both units. As a result, a number of changes were made to the safe shutdown equipment database. These changes included adding cables and correcting errors in cable routing. The fact that these cables were not previously in the database, or in some cases, had an incorrect routing listed, was also evaluated for impact on Appendix R compliance. No additional cases of non-compliance with Appendix R were identified.

1. Cable Routin The Safe Shutdown Capability Assessment (SSCA) was first submitted to the NRC in 1983. In 1983, AEPSC had recognized the need to provide additional. instrumentation at the LSI panels, as well as to provide an alternate source of power to the LSI panels from the unaffected unit.

The 1983 SSCA included proposed modifications (RFCs 02-2684 and 02-2683)

,which would implement these improvements. RFC 02-2684 included adding a new panel, LSI-4, and providing RCS loop temperature indication at the LSI panels. RFC 02-2683 provided the alternate power supply to the LSI panels from the opposi.te unit.

Upon completion of RFCs 2683 and 2684 in 1986, RCS loop temperature indications and pressure indication were routed through the LSI panels to the Control Room. Thus a potential fire which could fail all of the LSI panels would also fail this indication in the Control Room, thereby not complying with the'requirements of Appendix R. Such a fi.re was possible in any fire zone ~here both the normal and alternate power supply cables to the LSI panels were routed.

NAC F asm 358A (8891

NRC FORM 366A US. NUCLEAR REGULATORY CO N (6 $ 91 APPROVED OMB NO. 31500104 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP430(. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 30555, AND TO THE PAPERWORK REDUCTION PROJECT (31500(04I, OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 30503. ~

FACILITY NAME (11 DOCKET NUMBER (3( PAGE (31 LER NUMBER (Sl YEAR pgg EEOVENTIAL NVME'ER '44 REVISION r..(B NVMEER Donald C. Cook Nuclear Plant Unit 2 p 5 p p p 3 1 6 9 3 0 0 5 0 1 03oF07 TEXT (6 moro rpooo ro rOOwwd. FJO ~ ErroorM(FVRC Form 3664'4( l(TI Descri tion of Event Cont'd Fire Zones 22, 23 and 24 contain both the normal and alternate power supply cables for Unit 2 LSI panels. Fire Zone 22 was in non-compliance with III.G.2.c .since detection and automatic suppression were not installed in the Zone. Fire Zones 23 and 24 were in non-compliance with III.G.2.c since neither the normal or* alternate power supply cable were wrapped in these Zones. The non-compliance for Fire Zone 24 was reported by LER 90-10.

Compliance with Appendix R was restored in 1990 with the completion of RFCs 2900-8.04 and '3053. These RFCs provided additional Control Room RCS temperature and pressure indications which were not routed through the LSI panels. Therefore, a fire in Fire Zones 22, 23 or 24 would not affect the ability to safely shut down from the Control Room.

2. T S Submittal On February 2, 1989, AEPSC requested a change to T/S to allow conversion of the CO, Suppression Systems in Zones 23, 24, 26, and 27 from automatic to manual. This change could only be granted III.G.l, III.G.2.a or III.G.3 criteria was implemented for these zones if Section since these criteria do not require automatic suppression systems. The SSCA was used to determine the compliance strategy for these zones.

Consequently, the submittal stated that these zones were in compliance with III.G.1 when, in fact, the zones were intended to meet III.G.2 (Zones 23 and 24 also failed to meet this intent at this time).

The NRC granted the T/S change on 02/01/90 and the installation of the modification to the CO3 System was initiated in October 1990 and completed in July 1991 by PM 12-1085. From February 1990 to December 1990,.when RFC 12-3053 was completed, the T/S allowed less stringent requirements for the C03 System than what was required by Appendix R; Our initial investigation of the installation sequence for PM 12>>1085 determined that the automatic CO. Suppression Systems were converte'd to manual operation in Fire Zones 23, 24, 26 and 27 after December 1990.

RFC 3053 was implemented to provide RCS pressure indication in the Control Room in the event of a station blackout event. These instruments were not recognized at the time as required safe shutdown equipment in the SSCA list of SSD equipment nor were they called out in the emergency remote shutdown procedure. However, this indication was called out in EOPs concerning station blackout. Therefore, the operators were aware of the indication in the Control Room and would us it if needed. The cable for one of the pressure transmitters does not run through any of the fire, zones associated with the LSI panels or their power supply cables. As a result of the completion of RFC 3053, none of the normal or alternate power supply cables to the Unit 2 LSI panels needed to be wrapped and the compliance strategy for the fire zones containing the LSI panels and their power cables meets the requirements of III.G.1. The SSCA will be updated to reflect this change.

N4C Form 356A (6491

NAC FORM366A I EBS I t

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION U.S. NUCLEAR AEGULATORY COM N APPROVED OMB NO. 31504104 ESTIMATED BUAOEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50i) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP.530), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT l3)500)04). OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON. DC 20503.-

FACILITYNAME 11) DOCKET NUMBER I2) LEA NUMBER I6) PAGE I3)

>~<A sEQUEMTIAL i'teal t)Evls>ott YEAR 4% NUMS64 i:~ NVMSEtt I

Donald C. Cook Nuclear Plant Unit 2 o 6 0 0 o 3 1 6 9 3 0 0 5 0 0 4 QF 0 7 TEXT Iilmam rprtr it rrortrtf. urr eddeevel HRC Fomt 366A'r I I I 2 )

Descri tion of Event Cont'd Two other documentation inconsistencies were identified as part of the condition report investigation. LER 90-10 identified that an RCS pressure transmitter was available to the operators as a mitigating means to the event of a fixe in Fire Zone 24. Although this particular transmitter was actually not available there were other means available to the operators to access this information and the conclusion of safety significance in the LER remains unchanged.

LER 92-10, submitted on 12/23/92, reported that surveillances required by the T/S for fire-rated assemblies was not performed in Fire Zone 22.

At the time of the report, the Appendix R compliance strategy did not require cables -in this fire zone to be wrapped with one-hour fire barrier material. Both LER 92-10 and LER 90-10 will be reevaluated and revised as necessary.

Anal sis of Events Analysis of these events shows that apparent errors involved with the design and implementation of RFC 2683 in 1985 (alternate power supply) may have led to a period of non-compliance with Appendix R. These errors also led to a failure to provide the NRC with the correct information when requesting a change to T/S affecting Fire Zones 23, 24, 26 and 27. Cables in Zones -23 and 24 were not wrapped as required to meet III.G.2 and dete'ction and automatic suppression were not pr'ovided in Zone 22, even though general instructions were provided in the RFC packet to protect one of the cables when both the normal and alternate power supply cables ran through the same zone. No documentation is included in the RFC packet which would indicate that the engineer performing the engineering work was involved in the determination of which specific cables require wrapping. There was no procedure in place to ensure, such involvement.

LER 90-010 submitted on 9/2/90 reported the discovery of one of these errors. The lack of cable protection in Zone 24 was identified and corrected at this time. It is not clear why the investigation for the problem report associated with this LER did not also identify that the same problem existed in Zone 23 for the same two cables. Documentation included in this problem report showed that Cable 1-1936R, the alternate power supply from Unit 1, ran through both Zones 23 and 24, and that the cable routing in the Safe Shutdown System Analyses (SSSA) failed to include these zones.

Failure to propeily record the cable xouting of Cable 1-1936R probably led to the incorrect cable routing being included in the SSSA data base.

The error in the SSSA data base was identified and corrected due to the walkdowns, but the cable and conduit schedule was not updated at this time.

NRC Form 366A )569)

NAC FORM366A U.S. NUCLEAR REGULATORY COMI N (669) APPROVEO DMS NO.31500106 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT {LER) INFORMATION COLLECTION REQUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENTBRANCH IP.530), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. OC 20503.

FACILITY NAME I) I DOCKET NUMBER Ill LER NUMBER (6) PAGE (3)

YEAR SEOUENTIAL REVISION NVMSEII NUM8E II Donald C. Cook Nuclear Plant Unit 2 o 5 o 0 o 3 1' 9 3 0 0 5 0 10 oFo 7 TEXT N moIs S>>cs is ssEund. uss PFI(u>>us( )YRC Ferns 366A's) I Il)

Anal sis of Events Cont'd The failure to provide the NRC with correct information when requesting a change to T/Ss can be attributed directly to a failure to update the SSCA following the completion of RFC 2683. Table 1-1 of the SSCA lists the Appendix R compliance strategy for each fire zone. At the time of RFC 2683 development and implementation, the SSCA listed compliance strategy for Zones 23, 24, 26 and 27 as being III.G.1. Although the documentation in the RFC clearly shows that the intent was to meet III.G.2 for these zones, the SSCA was not updated to reflect this change.

Design changes associated with Control Room indication made to establish III.G.1 compliance for the zones covered by our 4/20/93 it possible LER. These design changes'ffects were unknown at the time of reporting in April 1993. The present listing of manual COl Systems in the T/S for these fire zones is therefore correct. No action is requ'ired with respect to changing T/S 3.7.9.3 or T/S Table 3.7-6. In addition, the COl Suppression Systems addressed by this T/S for Zones 23, 24, 26 and 27 should be considered operable and no report need be made per 10CFR50.73.

Present Need for Wra in Unit 2 Power Su 1 Cables This investigation shows that total loss of power to the Unit 2 LSI panels would not affect the ability to safely shut down from the Unit 2 Control Room. The LSI panels provide alternate safe shutdown capability for a fire in the Control Room or Control Room Cable Vault. Since the alternate power supply to the Un'it 2 LSI panels is not routed through any fire areas which potentially require shutdown from the LSI panels, none of the LSI power supply cables in Zones 5,'22, 23, 24, 26 or 27 needs to be wrapped. Therefore, the TSI material is no longer required and fire watches are not necessary in these zones.

Cause Descri tion No procedure existed at the time RFC 2683 was performed that would have ensured Appendix R cables were properly protected. The engineer assigned to develop RFC 2683 specified that redundant power supply cables routed through the same fire zone were to be protected in accordance with Appendix R Section III.G.2. There is no evidence that the assigned engineer verified that this requirement was carried out.

The Electric Plant Section Checklist completed by Design personnel marked Item 8P "Appendix R Requirements considered" as complete.

However, several cables were not wrapped as required and the Cable and Conduit Schedule was not correctly updated to show the routing for Cable 1-1936R.

Table 1-1 and Section 8 of the SSCA were not updated to reflect the impact of RFC 2683. This led to incorrect information being used as input for the T/S change. The T/S change submittal and PM 12-1085 were based on information associated with RFC 2683; therefore, the error for Appendix R was perpetuated.

N AC Form 366A (669)

NRC FORM 366A US. NUCLEAR REGULATORY COMM 1639) APPROVED OMB NO.3)504104 ESTIMATED BURDEN PER RESPONSE TO COMPI.Y WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTt 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH IP.530). U.S NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REOUC'TION PROJECT (3150010OI. OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON. OC 20503.

FACILITYNAME 11) DOCKET NUMBER 12) LER NUMBER 16) PAGE 13)

YEAR SEQUENTIAL REVISION ttUMOEII AU M o t II Donald C. Cook Nuclear Plant TEXT N moto tottoit IPOootd.

Unit 2 o 5 o o o 3 1 6 9 3 0 0 5 0 1 060F07 oto oddio'ontl HRC Fono 3SBA't I 1)T)

Cause Descri tion Cont'd NEP 5.7 and NDG 5.7 were approved on 1/17/90 and 3/25/91, respectively.

These procedures provide the necessary controls to ensure new Appendix R cables are properly identified, routed and protected. We believe these procedures (NEP 5.7 and NDG 5.7) would have precluded the above listed deficiencies.

Corrective 'Action b Jul 31 1993 Add NPS-110 and NPS-111 to the SSCA and SSSA as safe shutdown equipment.

NPS-110 and NPS-111 were identified as safe shutdown equipment by Change Sheet 1 to Revision 3 of the SSCA. This change was issued on July 30, 1993.

2. Revise the ERS procedures to recognize the use of NPS<<110, 111 in the event of the loss of both NPS-121 and NPS-122.

Procedure changes which recognize the use of NPS-110 and NPS-111 as safe shutdown equipment were issued for 1/2 OHP 4023.001;001 in July 1993.

3. Correct Drawing 1-2006-76 (Cable and Conduit Schedule) for Cable 1-1936R.

The drawing was corrected and issued on July 12, 1993.

4 ~ Revise the appropriate sections of the SSCA and Fire Protection Program Manual to reflect RFC 2683.

The appropriate sections of bhe SSCA were revised by Change Sheet 1 to Revision 3 issued in July 1993. At the same time, appropriate changes were made to the Fire Protection Program Manual (FPPM) which was in draft form. The FPPM was issued as a controlled document on December 15, 1993.

Preventive Action b December 30 1993 Verify correct and complete cable information is contained in the Unit 1 and Unit 2 SSSA data base for all LSI panels and all Appendix R required Control Room indication for both units.

AEPSC has reviewed the safe shutdown data base to ensure that all required cables associated with instrumentation have been appropriate identified and entered into the data base. As a result of this effortt over 100 cables associated with

'RC Form 366A IFr69) r

NRC FORM355A (d()S) t LICENSEE EVENT REPORT ILER)

TEXT CONTINUATION US. NUCLEAR REGULATORY COMM APPROVEO 0MB NO.31500104 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH 'THIS INFORMATION COLLECTION REQUEST: 500 HRS. FORWARD COMMEN'TS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, ANO TO THE I'AI'FRWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET> WASHINGTON. DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)

YEAR SEOUSNTIAL nvMOf II gd T: o:

REVISION NUMoon Donald C. Cook Nuclear Plant Unit 2 p 5 p p p 3 1 6 9 3 0 0 5 0 1 0 70" 0 7 TEXT IIIn>>to s>>toit totoonnL oto dddi'onol itRC Form 3ddA'tl (12)

Preventive Action b December 30 1993 Conttd instrumentation were added to the data base. The impact of not previously including these cables in the data base was evaluated for each. cable. In no case did the absence of these cables in the data base have any impact on compliance with Appendix R.

2 ~ Develop effective Appendix R screening criteria for use with design changes implemented as Plant Modification.

The Plant procedure for controlling, Plant Modifications (PMs) was revised to include a requirement to screen all PMs for fire protection and Appendix R impact. Procedure 12 PMP 5040 MOD.003, Revision 5 included this new requirement. This revision was issued after the events described in this LER and will ensure that design changes processed as PMs will receive appropriate reviews for Appendix R impact.

NRC Form 3ddA ISBQI