ML17326B348

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LER 87-024-00:on 871229,deficient Design Discovered Which Could Result in Failure to Provide Proper Local Shutdown & Indication Panel Fuse/Breaker Coordination.Caused by Improper Application of Selectivity ratios.W/880314 Ltr
ML17326B348
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 03/14/1988
From: Beilman T, Will Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-024, LER-87-24, NUDOCS 8803220251
Download: ML17326B348 (5)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSIOM NBR: 8803220251 DOC. DATE: 88/03/14 NOTA ZED: NO DOCKET FACIL~ 50-315 Donald C. Cook Nuclear Power Planti Unit ii Indiana 5 05000315 AUTH. NAME AUTHOR AFFILIATION BEILMANiT. P. Indiana Michigan Poeer Co. (formerly Indiana 5 Michigan Ele SMITHi W. G. Indiana Michigan Poeer Co. (formerly Indiana ~~ Michigan Ele RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-024-00: on 871229'uses installed to provide electrical isolation resulted in potential for fire. Caused bg improper application of selectivitg ratios for sizing installed f uses. Procedure revs issued. W/880314 1tr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL 'IZE:

TITLE: 50. 73 Licensee Event Report (LER) i Incident Rpti etc.

NOTES:

RECIPIENT COPIES RECIP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 STANGi J 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER .2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS7E4 1 0 NRR/DEST/CEB8H7 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEBT/ I CSB7A 1 1 NRR/DEST/MEB9H3 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSBSD1 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 NRR/DLPG/HFB 10D 1 1 NRR/DLPG/GAB10A 1= 1 NRR/DOEA/EAB11E 1 1 NRR /DREP /RAB 10A 1 1 NRR/DREP/RPB10A 2 2 NR~DRTB7WQB9A1 1 1 NRR/PMAS/ ILRB 12 1 1 02 1 1 RES TELFORDi J 1, 1 RES/DE/EIB 1 RES/DRPS DIR 1 1 RGN3 FILE 01 1 1 EXTERNAL: EG8cG GROHi M 4 4 FORD BLDG HOYLE A H ST LOBBY WARD 1 1 LPDR NRC PDR 1 1 NSIC HARRISi J NSI C MAYS. G 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 355 ~ U.S. NUCLEAR REGULATORY COMMISSION (94)3) ~

APPAOVED OMB NO. 31504104 EXPIRES: SI31ISS LICENSEE EVENT REPORT (LER)

FACILITYNAME (1I DOCKET NUMBER (2) PAGE 3 D. C. COOK PLANT UNIT 1 o s o o o 3 1 5> oF 0 3 e z.caen esxgn esu s z.n e az. ure o rove. e roper oca u own and Indication Panel Fuse/Breaker Coordination.

EVENT DATE (5) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (5)

MONTH DAY YEAR YEAR SEOVENTIAL ate REVE~ MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(s)

NUMBER NUMBER D. C. Cook Unit 2 o 5 o o o 3 1 6 1 2 0 2 4 0 0 0 3 1 '4 8 8 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REOVIREMENTS OF 10 CFR (Ir (Ctrees one or more ol the IoriovtlnPI (11)

MODE (9) 20.405(c) 73.7 lib)

(Ir ) 50.73(e) (2) (Iv)

POWER 0('0.402 20A05(e I (I)(I) 50M(c) l1) 50.73(e) (2)(v) 73.71(c)

LEVEL (10) 20.405(e) )1) (5) 50.35(c) (2) 50,73( ~ ) l2)(v5) OTHER ISpeclly In Abrtrect

$4ri'yi 20.405(e)(1)(SII 50.73(e I (2) I I) 50.73(e) (2) (vill)(A)

Below end In Text, IIRC Form JSSAI 20A05(e l(1)(iv) 50.73(e) (2)(II) 50,73( ~ ) (2((vill)(Bl I c 20,405( ~ l(1)(vl 50.73(e l(2 I (ill) 50.73( ~ )(2)(xl LICENSEE CONTACT FOA THIS LEA (12)

T.P. Beilman AREA CODE TELEPHONE NUMBER Instrumentation and Control Department Superintendent 6 1 6 4 6 5 5 9 0 1 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAG REPORTABLE MANVFAC. REPORTABLE CAUSE SYSTEM COMPONENT TUBER TO NPRDS SYSTEM COMPONENT TURER TO NPRDS SR'53NI oMME PP~)

SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SU 5 MISS IO N DATE'15)

YES IIIyer, complete EXPECTED SUB4IISSION DATEI NO ABsTRAcT (Limit ro 1400 rpecer, l.e., epproxlmetely fifteen elnole tpece typewritten liner) (15)

As a result of the condition reported in LER 50-315/87-0023, fuses were installed to provide electrical isolation between the various sets of local shutdown and indication (LSI) panels (Unit,l installation completed

-12/29/87, Unit 2 installation completed 12/30/87). The problem described herein was discovered 1/28/88, during final design verification of the as-built drawings.

As part of this design verification, a coordination analysis was performed for the fuses and upstream breaker. The analysis shawed that. full coordination could not be assured. Consequently, the potential existed for a fir'el in either unit, to result in the loss of pawer and indication at the LSI panels and indication of T-HOT and T-COLD and one of four channels of pressurizer level in the affected unit's control roan. Imnediate actions taken follawing site notification involved establishing fire watches for the areas containing the LSI panels (2/3/88). The fire watches were terminated on 2/8/88 following issuance of procedure revisions providing steps required to manually reestablish pawer to the LSI panels.

This event occurred as a result of improper application of selectivity ratios for sizing the installed fuses. To prevent recurrence Electrical engineers will be given guidance on the use of selectivity ratios .and their applications. This training will be completed 4/15/88.

880322025i 8803iEI ~ ~~~/

PDR ADQCIE, 050003iS 8 PDR NRC Form 345 (9 53)

NRC Poem 3SSA US. NUCLEAR REOULATORY COMMISSION IIMVV n LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3160&104 I EXPIRES: E/31/83 PACILITY NAME 111 OOCKET NUMSER 131 LER NUMIER ISI PACE (31

~A SSQVSNTIAL gw /ISVSIO/I gi4 NVM SR:;x5. NVM SA D.C. COOK UNIT 1 o coo o31587 0 4 0 0 0.2 QFO 3 TEXT ///mare epee'I nqukrd, Ver rcWo'one's//RC FemI 3SEAE/1131 Conditions Prior to Occurence (Conditions date of discovery)

Unit 1 - Axe 1 (Power Operation), 90 percent reactor thermal power Unit 2 - Mode 1 (Power Operation), 80 percent reactor thermal power Descri tion of Event As a result of the condition reported in LER 50-315/87-23, fuses (EIIS/FU) were installed to provide electrical isolation between the various sets of local shutdown and indication (LSI) panels, (EIIS/PL) [Unit 1 installation completed on December 29, 1987, Unit 2 installation completed on December 30, 1987]. The problem described herein was discovered on January 28, 1988, during final design verification of the as-built drawings that reflected the newly installed fuses.

As part of this design verification, a'oordination analysis was performed for the fuses and upstream breaker (EIIS/BKR) . The analysis showed that full coordination could not be assured since sane overlap existed between the installed fuses and the upstream breaker. Consequently, the potential-existed for a fire, in either unit, to result in the loss of power and indication at the LSI panels and indicat.ion of T-HOT and T-COLD (EIIS/AB-TI) and one of four channels of pressurizer level (EIIS/AB-LI) in the affected unit's control rocm.

Imnediate actions taken following site notification involved establishing fire watches for the areas containing the LSI panels (1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, February 3, 1988). With the exception of the subject LSI panels, there were no inoperative components, systems or structures that contributed to this event.

In a conversation between Mr. P.A. Barrett (AEPSC NSGL) and Mr. D.. Butler (NRC Region III Inspector) on February 29, 1988, Mr. Butler indicated that his management had granted an extension for the submittal of this LER to March 14, 1988.

Cause of Event This event occurred as a result of a design deficiency (improper application of selectivity ratios for sizing the installed fuses).

Anal sis of Event This report is being subnitted pursuant to 10CFR50.73 (a)(2)(ii) (B), a condition identified which is outside the design bases.

NRC P/IRM SSSA

$ 431

NRC Fooe BEEA US. NUCLEAR REOULATORY COMMISSION

))MLS LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3160&)04 EXPIRES: B/31/88 FACILITYNAME ll) DOCKET NUMBER )1) LER NUMBER IS) PACE I3)

YEAR INC: EEQVENTIAL ~

' IIEVI5ION NVM EII '. SI NVM EN D. C. COOK PLANT UNIT 1 o s o o o 3 1 5 8 7 0 2 4 0 0 0 3 QF TEXT ///more s/roos /s rsr/Nrr L Iree ~ Af///ooo//ltRC Fomr 3/ISAB/ l)TI Anal sis of Event Con't Due to the lack of coordination between the circuit protection devices, certain postulated fires in either unit could have lead to loss of power and indication at the LSI panels and indication of T-HOT and T-COLD and one of four channels of pressurizer level in that unit's control room. We believe, however, that LSI panels and those control room indications lost would not have been necessary in the event of a fire at any LSI panel location because adequate control capability and indication of required process variables would have been available in the same unit's control roan. Therefore, we believe the condition does not represent a significant risk to public health and safety.

Corrective Actions Operators were provided instructions for the steps required to manually reestablish power to the LSI panels. 'This was implemented by effecting change sheets to the appropriate procedures, and notifying the operators via an "Operating Menn". Once it was ensured that the necessary instructions were in place fire watches were terminated (2146 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.16553e-4 months <br />, February 8, 1988).

Electrical engineers working on the D.C. Cook Nuclear Plant will be given guidance on the use of selectivity ratios and their applications in designing circuit protection schemes. This training will Be completed by April 15, 1988.

Failed Co nent Identification None.

Previous Similar Events LER 50-315/87-23 NRC SIIRM BEEA IB45)

Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458 Bridgman. Ml 49106 616 465 5901 INOIAMA NICHIGiAN POWER March 14, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-315 Document Control Manager:

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

87-024-00 Sincerely, uter@

W. G. Smith, Jr.

'~~)

Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr.

A. B. Davis, Region M. P. Alexich III R. F. Kroeger H. B. Brugger R. W. Jurgensen NRC Resident Inspector J. F. Stang, NRC R. C. Callen G. Charnoff, Esq.

Dottie Sherman, ANI Library.

D. Hahn INPO PNSRC A. A. Blind P. A. Barrett/P. Lauzau