ML20085B263

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Responds to Requesting Review to Determine If Seismic Equipment Failure Would Adversely Affect safety-related Equipment Operability.Condenser Circulating Water Sys Has Greatest Potential for Flooding
ML20085B263
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/26/1972
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20085B259 List:
References
NUDOCS 8307080068
Download: ML20085B263 (2)
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U.S. NUCLEAR ?.ECtJLATORY CO:'?!SSICN OFFICE OF l':S?ECTION AND I::FCRCEF. INT Region I 3,,,; p 50-239/78-23 4 - a" r H 3 r:cT 037AIN* 3 f..-

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et 796 C

C?R-50 License No. nn.71 Priority Category up

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T1 ra. wit = M1md 'S cNr Sh tf on, Units 1 and 2 I.ispection at:

Middletcwn, Pennsylvania Inspecticit conducted:

Cecember 4-8 and 12-14, 1978 1/d-[M Ins;;ectors:

ate signed D. R. Haverkamp, Reacto/ Inspector L. P. M,--

r/v/ r9 case signec d./R. JohVsen, Reacec-Inspector Trainee

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C# 2 sis"*d P. D. 3:9.a;.e,. e-ster Ins;?ctor Trainee Apprcved by:

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f. R.'Kei:eff. thief, 3tteter Projects Section

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InspacMen on Deece-5er :-E and 12-1*,1973 (Co-bined Recert fics. 50-289/78-23 and L

50-32C/ 73-36) i Aress ins 2:ted: Routine, unanncunced inspection by three regional based inspectors I

of cianc c;eraticas including facility tcur during backshift; Technical Specificatica Safety Linits, Lf=iting Safety Systen Settings and Li siting Cenditions for Operation L;

cc ;1ian:e daring reactor operaticas (Cat: 2 cnly); ;1 ant cicantiness (Unit 2 cnly);

1 RPS gr:unding sy:tect testing; ste-1 c:unted limit switches enrircreantal qualifica-tic ; and pre ricuc in:;ection findings. The inspection involved 7 inspector-hours onsite for Unit 1 and 54 inspectcr-heurs onsite for Unit 2 by one NRC regional based U

inspector and ?t hcurs ensite by t.to inspector-trainees.

L Res'Mts (Unit 1): F:o items of nonccepliance were identified.

Results (Uni: 2): Of the five areas inspected, cae ite1 of nonco:-oliance was found in i

one arca Geficiency - failure to perfor surveillance of containment isolation valves located inside centairnent, Paragraph 4).

Y Regica I Fom 12 (Rev. A;ril 77) a-I B307080068 721120 PDR ADOCK 05000235 n R,;...;: ~

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Persons Ccntacted I,

Metreeofitan Edison Com:any

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.g 7. Lead Mechanics 1) Engineer-Mr. It. Sensel, Unit 2 Lead Electrical Engineer

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  • Fr. M. Bezilla Unit 2 PORC Secretary Fr. J. Chwastyk Shift Supervisor Mr. J. Floyd, Unit 2 Su;ervisor of Operations Fr. C. Hart.an, Unit 1 Lead Electrical Engineer Mr. J.' Hilbish, Station Lead f:uclear Engineer Mr. G. Hitz, Shif t Supervisor W. K. Hoyt, Unit 2 Shif t Foreman Mr. F. Huwe, Unit 2 Radiation Protection Forer.an
  • Mr. G. KI.r. der Unit 2 Superinterdent - s~tchnical Support
  • Mr. J. Logan, Unit 2 Sucerintendant Mr.11. Criar.di, Unit 1 Lead Instreentation and Centrols Eng!neer Fr. T. Porter, Unit 2 Lead Instreentatica and Controls Engineer
  • Mr. M. Ross, Unit 1 Supervisor of Operations e

Mr. F. Scheirsann, Jr., Unit 2 Shift For.an Mr. J. Seelfr:ger, Unit 1 Superinetadent Pr. M. Shat::, Un1t 1 PCT.C Se:retary 7.r. R. '.Carren, dnit 2 Lead yachanical Enginear Pr. 2. Zewe. Shif t Supervisor l

Gem-af %-7 fc 'Jtitities Swiict i'cr cration

.?. C. Gatts Lead ?echanical Test Engineer l

Y.r. R. Tcola. Test St.perinterdent 77 s ins;sc or af sc intervie. sed several ether ifcensee erpicyees ducirg the inspectica. They included c:ntrol roc 1 operaters, technical and engineering staff perscncel, and general office l

personnel.

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- (Closed)' Inspector FoJ1cwup Iteer 289/73-C2.C1: LER 77-25/3L Cor-I rective Action. In, stat 1ation of perranent piping for seal water I

to the RC; evaporator was completed per C/ t ?o. 455 and Work

..$...,.. ". makeugtr.TCS29 and 10830'. The inspector had no further questions.

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Reques concerning this item.

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(Closed) Inspector Fo11cwup Item 239/73 13-C2: LIR'78-17/1T Cor-rective Action. Reduced RC3 High Pressure T.ip setpoints were app-oved by,*tRC:t:RR per Technical Specificatien kendment flo. a5.

The irspector had no further questions concerning this item.

(Closed) Inspector Foildup Item 320/73-22-C1: Pn:per Apmval of Temporary Changes Cemen tc Units 1 and.2.

Effective tan:orarf changes applicable to both Unit I and Unit 2 were revieaed. The inspector verified that a fenice Reactor C; era';or ifcented for each unit epproved the temporary chances to the asscciated facility pro-cedures. Tha inspector V4 to further questions concerning *his item.

7 (Closed) 'itencero11ance 320/72-24-01: Elect-eda 0tr.rsge Oven Temperature Less Than Required. The !icensee's correttw e measu;19 were cor plett:d as described it. ?!C Letter t2 ::?.C ::ogien I. Serial 3

CCL 102, dated September 18,197S. The overall pr:gra:s for weld red co e.rol was reviewed by CPUSC CA persorref and discussed with ap;1repriate constructic.1 contractor repriteatstiles. Curing fre-quent CC inspections of wort in preg *ess, tha storage and distri-i butica of weld md: and the temperatures of holdin; and baking ovens were found to be ac:cstable. In addition, the use of weld rod at cut-of-specification temparature conditices was evaluJied. GPUSC cemorandum PE/COS dated f:ovember 10. 1973. cor.cluded that i.he welds made with the weld rods h eld at 1900F are scurd and the suse:pti-bility to hydrogen cracking is no greater than if normal holding temperatures were employed. The inspector had ns further questions ccncerning this item.

g (Closed) Unresolved Item 320/73-24-06: !IE 73-01 Coirective Actions.

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Valor type contact ar:a retainers wer2 installed in applicabla GE CK l

12CA and CR 122 relays per C/:! 2-035. The codified relays were l.

satisfacterily tested per k!ork Request :o. 4133. The inspector had no further questions concerning this item.

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TP 272/1. Main Feed Pump.

Unr$ solved i % %0/73-29-02:During performance of IP 8C0/23.

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- *ained 74t power with cne c;:arating main Exception E-27.

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fent Test. the plant i

feed pup.. which met

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.. specific ficw data were required to be annotated in TP 272/1.

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inspector'had no further questions cencerning,this iters.

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TP 330/5. Centr si Rod Drive

,i 320/73-29-00:

(Closed) Unresolved Item Th2 acceptance of TF 330/5 E-13. was Trip Test. Exceptien E-13.

based en four previous acceptable tests performed per T7 330/5.

I:o ; robles report was required to be written for additicnal opera-b111ty verification of the in-limit lights fer Centrol Rods and 6-7.

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GP.C Cuorun Requiremnts.

(C1: sed) Unresolved Item 32C/73-29-Gt:

Tw2 additicnal C2C marabers were appointed by ;TC 1.e:ter Serial 22, 1973 to assure that GRC quorum re-G;;M 4343 dat:d SepteNr The inspector re-quire ents for.-c=bers and alternates are met. viewed rt:ent U The inspector had no agacies con =e-ning quorum requirs.ents.

further questions concerning *.his itect.

320/73-29-C5: Frecarttica and Review

'iri: ten PCEC r:inutas hata been prepared (Closed) 1;r. resolved item m

of PO?C Festing :itr. uter.4etir.g ::o. 292 (C:tober 23-7;: vet 2r 3.1978).

The GRC review of PORC ceeting rinutas has been : -oleted thrtugh thr u-?: Cait 2 FORC :

Sutsac en: written PORC FCRC l'estir.g ::o. 275 (July 11 '4.1973).

The inspector eeetin.- miw.as have teen suxsic;ed fer GP.C revi.r.no ed te;rcied and had no further gestions concerning th:s item.

Control of Portable Fire Unresolved Item 22C/73-29-07:The inspector reviev.ad Precedu (Closed)

Fire Extinguisher Inspection. Re<ision 0, wMch provides require-Extinguishers.

a insure that portable fire extinguishars are properlyThe inspecto f

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8' inspected on a renthly frecency.

The appears ad2:;uste for future centrol of fire extinguishers.

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inspecter : urad portions of the auxiliary building and turbine

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buildirg at various times during this inspection and found no ex-The inspecto aspies of cissing portable fire extinguishers.

no further questions concerning this itect.

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(Closed) Inspector Followup Ita= 320/78-29-03: Unplugged Piping Penetration. The fuel cil storage tant cross-cennect pipo pene.

tration has been plugged per EC:1 5-9035. The inspector had no r,

further questions concerning this item.

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(Closed) *!nresolved Item 320/73-32-01: Runback Rate Test. The I

for runback rate testing was re-e

. ;,.s acceph cHterit of JP 200/31,.dalled for'a runback ' rate of

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vised such'that unit Tcad descand 30f_2 per minute. The revised acceptance criteria *was met during a

a rotast ccepleted on October 25. 1973. The inspector had no further questions cencerning this item.

(0 pen)' Inspector Followup Item 320/78-32-07: LER 73-54/31. Cor-rective Action. The qualification of Siemans-type operators used with CA-V3. CA-V4t. and CA-V43 has not yet been determined by the licensee. NEC Letter Serial CCi 5305, dated Novenber 15, 1973

  • stated that the Sic:ans operators are considered adequately qual-ified for teeparary use inside contain:r. ant, based on licensee re-The A-E is view of documentation provided by the valve vendor.

attempting to deter: sine the extent of " temporary". Sectuse these operators use Class 3 insulatten, the long'-term temperature effects are not sufficiently known to allow the operators to be left inside centainment permanently. : Replacement of these operators is planned for the earliest convenient outage. Final ifcensee evaluation of Q

Siemans operators Osage and replacedent wil! be reviewed during a subsequent inspection.

3.

Plant Tour (Units i and 2)

U;on arrival at the sita at 6:15 a.m. on Dece~ber 4.1973 the inspector proceeded directly to the Unit 1 and Unit 2 ControlCon-Roc s to obserte plant operaticas during off-nor.al hours.

trol Rc::m canning and control board c:enitoring instracentation and equf;: ent controis were cbserved for confor ar.ce with app 11-cable Technical Specificatica require:-ents. The inspector than conducted a tour of the Unit 2 /-uxiliary hilctng to check for f,

general cleanliness and housekeeping conditicns, potential fire r",

hazards and adequacy of radiatien controls. The tour was co:.

l' plated at 8:30 a.c.

Finding; were acceptatie, except as noted t

below.

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m Several radiation control discrecancies were cbserved by the inspector cur:rg tne untt 2 Auxiliary Guilding tour. Used

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protective clotning was laying on the ficar and used rubber boots and gloves were laying en the step-off pad at the cen-(

trol point entry to the S Cecay Heat Yault. Ho barricade was

,2. ::.,in., place at the entry,to tha A Decay Heat Yault, which was.,

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' posted' as 's radiation area. '!o radiatica ares signs were-posted at the entries to the :Sp-1C and M!J-T-1A cubicles.

which were identified by radiation work pemits as radiation areas. The radiation work pemit for the seal return cooler cubicle was laying en the floor at the entry to the cubicle.

Thh Unit 2 radia'tfen pro: action forecan also identified the above discrepancies during a facility tcur conducted at the same time as, but not in cc-.any with, the inspector. Although these items were prompt 1.y corrected, the inspector expressed. concern over the appa-rent degradation in proper radit.tica protection control during the preceding weekend. The discrepant conditions resulted frc= a ecm-binatics of inadequate training and insufficient designation of responsthilities regarding cperations and radiation protection per-sonnel. Licensee representatives stated that appa:priate correc-tive action would be taken to ensure adequate radiation protection controls are maintained in the future.

O The inspect:r condacted t.co' subsequent t:urs of the L' nit 2 Auxiliary Building during this ins;ac: ton and notac that radiatica protection controls were acce; table. The effectiveness of licensee acticns to maintain proper c:ntrols for prctective clothing disposal and radiaticn ar=a postisg/harricading will continue to be reviewed during r:atine NEC inssections. The intsect:r had no further questions c:ncarning this itera at this time.

4.

Review of Safet/ Li its. Limitins Safety Syster Settinas and Lim tino c:r.oitions r r 0: erati.m

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The inspector observed process instr.:::entation eenit: ring current cperaticas on Cece;:bar 4-6 and 13.-14.1978 and reviewed records of

L reactor cperations durin; February-te: estar 1973. The following logs and records were reviewed on a sampling basis.

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7 Operatino Procedure (CP) 2102-1.1, " Unit Heatup," R2visicn H

16; completed December 1,1978 C? 2102-1.2, " Approach to Criticality," Revision 5 (TCt 2-78-669);

completed Cecember 3,1978

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  • Unit Startuo," Revision"10 (TCis 2Df8-665,'2-78-667, a

2-78-670, 2-78-700, 2 78-709); in progress en December 7, 1978 I

OP 2102-2.1, "Pcwer Operations," Revision 9 (TCt 2-78-701);

control room file copy CP 2102-3.1, " Unit Shutdown," Revisien 6 (TCis 2-78-612, 2-78-654,2-78-683); ccepleted October 29, 1978 OP 2102 3.2, " Unit Ccoldewn," Revision 10 (TCis 2-78-615, 2-78-671); cc=pleted Septeeter 23, 1978 CP 2102-4.1, " Reactor Butiding Purge and Purification." Re-vision 3; partially cocpleted February 17, 1978 CP 2103-1.1, " Filling and Venting the Reactor Coolant System,"

Revision 8 (TCt 2-78-694); partially ccepleted September 24 1978

-Q CP' 2103-1.2, " Soluble Poisen Concentration," Revision 4; con-trol'rcem file cooy CP 2103-1.3, " Pressurizer C;:eration," Revision 3; partially cc=pleted Septe=ber 16, 1978 OP 2104-1.1, " Core F1 ceding Sys:em," Revision 8; partially co=pleted August 22, 1978 CP 21C4-1.2, " Makeup and Purif t:stion System," Revision 11 4

(TCi 2-78-623); ccepteted ;;ovember 19, 1978 A

>l CP 2103-1.4, " Reactor Euilding Spray," Revisico 3; Appendix g'

A Valve 1.ineup ct=pleted July 14, 1978 CP 2104-3.3, "Cecay Heat Closed Cooling Water System," Revis-ton 5; completed August 22, 1978 t'

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s OP 2104-6.2. "E: ergency Ofesels and Auxiliaries.* Revision 8; cocpleted r.ay 30 and Oecc ser S. 1973 i-CP 2T04-6.3. "Ecergency Feet ater." Revision 4; Ap;endix A l

Valve Lineup ccepleted itovember 17. 1978

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OP 2104-6.4. " Hydrogen Recs::biner Operation." Revision 2; con-trol rocs file copy j

07 2104-6.5. " Hydrogen Control Systes." Revision 1; c ntrol reora file copy CP 2105-1.1. *::uclear Instru.entation." Revision 2; c==oleted October 9. 1973 07 2105-1.2. " Reactor Protection Systen.' Revision 4; partially cs::placed August 25. 1978 CP 21C5-1.3. *$4fety features Ac':.ation System." Revision 2t partially cc:pleted Oct:bar 9,1978 0? 2105-1.9, "Centrol Rod Crives." Revision 5; cor plated (un-dated) 8 0? 2107-1.2. " Class 1E Electrical Systas." Revision 5; c==-

. pleted Noverter 13. 1973 hu.S tillance Precedure (57) 2301-51 " Shift and 04 fly Checks."

Revi;1cn 12 (TC:s 2-73+651, 2-72.687, 2-73-69C), c= ;1eted August 27-Sa;te"ter 3. Sestacar 13-25. Oct tar 3-15. ::cveder 3-10. and Oeced er 1-6, 1973 SP 2307-201. "R"5 Inventory." Revision 2; cor.,,1sted during October 1 "tcr.ber 11. 1978 SP 2301-W1. *%ee'<1y Surveillance Checks." Revision a (TCts 2-78-657. 2-73-711); cc pleted during Octcher 5-Decerter 7

,L 1978-

-I 57 2301-W2. " Station St: rage Batteries and Chargers %eekly Ii Check." Revisica 2; cceplated during Octcher 4-Dec.ter 6 l

1978

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3 5' 2301 :c. "Se'an injection System Valve Lineup Verifica-tion." Revision 2; c:mpleted during July 26-Cecember 3. 1973 1

l SP 2301-N4. " Remote Shutdown Instrumentation." Revision 3; l ted. during August,23-Cece=ber 5.1978

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-e SP 2301-MS. "P.CP Seal Return Measurement." Revision' T; cm-pleted during August 2S-Cecem:er 6.1978 SP 2301-MS. " Core Flood Tank - Isolation Valve Breaker Post-tion Verification." Revision 2; c:mpleted during August 23-December 4. 1978 SP 2301-MS. " Containment Integrity Verification." Revision 6 (TCt 2-78-673); c:mpleted during August 23-Cec:mber 7.1973 SP 2301-M11. "CHCCJ Yalve Lineup Verification." Revision 3; co::spleted during August 10-November 10. 1973 SP 2301-Q1. "Statica Storage Batteries." Revision 2; completed e

August 16 and ::cvember 22. 1978 SP 2303-M13. " Hydrogen Purge Cleanup System.* Revisien 1;

. Q completed during 11 arch 22-tiovember 17. 1978 SP 23C3-M142/S/C/C/E " Emergency Feed System Valve t.ineup Verification and 0;erability Test; and Turbine Driven E.F.

Pump Operability Test." Revision S; corrplated during July 20-Decer::ber 2.1978 SP 2303-;t1EJ/0/C/D. "Exergancy Diesel Gacerator ard Cooling Water Valve C;artoitity Test." Revision 8; cmpleted during October 2-Cececher 11. 1973 h

SP 2303-M37. "Hydregen Mixing System - Remote Start and C;er-d ability Check." Original; ccepleted during August 10-Cecacher 6

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10. 1973

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>l SP 2303-Q3. " Hydrogen Recer.biner Functional Test." Revision 1'

2; completed October 11. 1978

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SP 2304-W1. " Borated Water Source Concentration Test." criginal; ccepleted during August 7-Oecember 12. 1978 i;-

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SP 2304-MI. *Cera Fic-d Ta% E:ren Concentration." Revision 1; co=pletec curing Ja!y 31.tecectar 3.1973 I

I SP 2304-SA1. *3siidin; S: ray *:ac. Tank concentratten and I

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26. 1978 Volu=4.".Revisien 2; c=.=p;ated Septa =ber j ;.,,..

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  • ifn'ir:n Te::e-a.Jee for Criticality." Original; control rocn file ccpy SP 2311-5. "Cer.t f=a-t Integrity." Revision 5 (TCN 2-78-713);

ca pletad during Aur.s: 25-W.e= der 6.1978 SP 2501-MI. "?.eclained I:ri: A:f d Tank Te: perature." Original; cos:pleted durieg Aur st 2-Ca:e.ber 2,1978 The observations and rec:rds --view were c:nducted to verify that startup, pcwer and/:r s.ttd: : react:r operations were in confom-ance with Tech-ical !:ecift:2 f=n safety ifaits. Ifmiting safety system settings and it=iticg ::rdit'icns for operation.

Acceptance.critaria f:e the aS:ve itecs included delected require-ments of facility o;eratics prs ad res and *he following Technical a

- Specifications (listed ac :rding to their respective systes).

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R'eactivity C:strol and.;.ve Distrittati:n Technical Specifica-tions 3.1.1.2. 3.1.1.1. 3.1.2.2. 3.1.2.8. 3.1.2./. 3.1.2.9 3.1.3.1. 3.1.3.3,- 3.2.1. 4.d 3.2.4

'nstru: entatien Techr'::I 5;ecificaticas 2.2.1 (Table 2.2-1 f tes 2,3,5.5 and -)

2.3.1.1 Ts5:e 3.3-1 items 2, 3. 5. 5 and 9). 3.3.2.i (72 ties 3.3 3 and 3.3 4 its s 1.b and 2.b).

3.3.3.5 (Table 3.3-9 ~ '- *-= s 1 and 3; indicator item 1 and patch point ite=s 1 ard 4)

Reactor Coolant Systes Tech.ical Specifications 2.1.1, 2.1.3 3.4.1, 3.4.4. 3.4.5.2. and 3.4.9.1 i'

Es:ergency c:re ce=Tir; systa: s Technical specificaticas 3.5.1 and 3.5.4 1

Containment systes Tec--ica Speciffe: fons 3.5.1.4. 3.6.1.5, i

3.6.1.7. 3.6.2.2. 3.6.3.1. 3.5.4.2 and 3.5.4.4 I

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Plant and Electrical ?cwer Syste:-: Technical Specifications 3.7.1.2, 3.7.1.3, 3.7.3.2, 3.8.1.1. and 3.8.2.3

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The items observed and reviewed by the inspector were acceptable, e M. ;*>. :

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. j The inspector noted the fil'owing exa:ples of Isrproperly or inadequately coepleted operating procedures:

4.

OP 2102-1.3 (in progress on Dece.ber 7,1978) - Step 4.1.40 and subseque.* stecs were perfomed, but were not initialed as being cc=pleted; b.

OP 2102-3.2 (ca.npleted Septeber 23,1973) - Steps 3.6, 3.7, 4.2.2 and 4.6.a were not initialed as being ec..pleted; c.

OP 2102-4.1 (partially cer:pleted February 17. 1973). All prerequisite steps were not initialed as being ccmpleted and Appendix A Valve Lineup was not fully completed; d-OP 2103-1.1 (partially comoleted September 24, 1978) -

Section 3.1 step 3. Section 3.2 steps 10-35, 41-49 and 51 and Section 4.2 steps 2 and 4 were not initialed as p

being ec=pleted; e.

OP 2103-1.2 - Varfoils procedural evoluttens had been perfor-ed, but no cc:pletad peccedures were in the cen-trol room files; f.

OP 2103-1.3 (partially cc ple'ed September 16, 1973) -

S'eps 4.1.5.7 and 4.1.5.8 were perfomed, but were not initialed as being completed; g.

CP 2104-1.1 (partially ec.pleted August 22,1973) - Steps 3.1 and 3.2 were not initialad as being cocpleted;

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h. - CP 2104-1.2 (ccepleted :oveber 19,1973) - A;endix A l

Valve Lineup was not fully cecpleted; f.

0? 2104-1.4 (Appendix A Valve Lineup cc=pleted July 14 j

1973) - ::o prerequisite er startup procedure steps were r

initialed as being completed; I

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OP 2104-6.2 (Undated) - Many steps were not initialed as being completed, and the partially completec procedure rw i

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OP 2104-6.2 (portions ec: pleted on Pay 30 and December 8.

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Procedure excerpts.for. diesel generator manual.

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start e lutions were in the control roc:a files vice the entire p cedure; e

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OP 2104-6.3 (Appendix A Valve Lineup ccmpleted november 17, 1978) - no prerequisite or startup precedure steps were initialed as being c =pleted; m.

OP 2105-1.2 (;artially completed August 25,1973) - Steps 4.4, 4.5.8(1)-(14) and 4.5.3(18)-(25) were not initiated as being completed; 2

OP 2105-1.3 (partially cc=pleted October 9,1978) - Sec-n.

tion 4.2 steps were not initialed as being completed;

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OP 2105-1.9 (Undated) - Steps 4.2.1.17, 4.2.1.18, 4.2.8.1.

4.2.8.2.1 and 4.2.8.2.2 were not initiated as being ccm-

,Q pleted and the partially co oleted precedure was not annotated with the date of perfomance.

The inspector stated that, based on the n'.. ber of discrepancies noted above, corrective action was necess:ry to assure c:nfor-ance with licarsae administrative c:ntrols for operating procedure teplecentation and review. Licensee representatives stated that operators would be rcminded of their esspensibilities for pr per procedure c,:pletion. This item is uneasolved pending review of Ifcensee ccrrective actions and selectad, cc=pleted ocerating precedures during a subsequent inspecticn. (320/78-35-01)

The inspector noted the folicwing exacales of improperly hl annotating unused control reos centrolled file and/or wrking g

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l copies of operating procedures:

t a '. OP 2102-3.2 - File an1 working copy steps 4.27.1 and 4.23 were initialed as being c:tpleted; b.

OP 2102-4.1 - Several working copy prerequisite and purge I

4 peccedure steps were initialed as being completed; and, h

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0? 2!03-t.I-Her6.ing copy Page 35.0 was annotated with nu=ters, g

The above file and working copies of operating procedures were

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e.>.." stcred in cont-ol roca file cab netsprecedures, shesid have'no ~annotatiens, e

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4 tive TQs or cancelled TCs. Licensee repr sentatives stated that

'l a full page audit of file and working copies of central reon pro-cedures was schaduled to be ;er#cr ed.

In addition to page check-

'7 ing for procedure c:epleteness, the pages will be reviewed for frpr:per annetations. This item is unresolved pending c: pletion of the schaduled ;rocedure audit. (320/73-35-02)

SP 2301-51 incorporates various Technical Soecification sur-veillance require ents to be perforced at onca per shift.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or daily frequencies. The inspect:r noted the following examples of 1. properly implementing SP ??01-51:

a.

Baron reductions were raade on 5 oc:asions without ccm-pleting Appendix H, as required by SP 2301-51s b.

Perforcer and/or approver signatures were missing on several occasions; g

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Various paracetars,sare not rec -ded cr were incorrectly rec:rdad en several ec:ssions, including c:ntairc: ant at=c:pn2re and gasecus c:nitoring systa: cha.anel checks.

F.PI/ API /;reup c:ntrol red po:itions, c:nden:ste stor:ge tank level, operational code, R.E. pur;a valve accurulated ti.e. P.?S chennal c. heck, scurce range flux. EMS"" te per-ature 2.3. ;rassure daviations act pu: p/ flux ::ntact conitors;" and, d.

L!napproved minor changes.were made to required data, i.e.

  • !.P." to "*.;R*. of SP 2301-51 on six occasions.

Tha ins;2ctor stated that except as described ab:ve, all p:rtions I

of the SPs 2201-51 had been fully and properly c:-cleted. Licensee i

representatives stated that appropriate action would be taken to l'

assure that SP 2301-51 is properly implemented in the future. ' This itz-is unresolved pending review of licensee corrective actions

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ar.d selected c::pleted SPs 2301 51 during a subsequent inspection.

(32':/72-35-03)

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9 SP ' 01-M4 f accr;cntas Technical Specification Survelliance J

Requirement 4.3.3.5 monthly channel checks of remote shut-8 i

down monitoring instrumantation. Completed SP 2301-M4, dated December 5,1973, listed several remota shutdown instrument I

4.,.u a.,. values which were at or slightly. exceeded the acceptance k.

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m criteria of tvithin 2Fof'correspondin7 control' room instru-s:ent values. Prior to tha end of the inspection, SP 2301-M4 was perforced again wit: the results being acceptable. The 2

inspector noted that t.%e prescribed acceptance criteria was not appropriate for all instrur.ent ecmparisons. In some cases, the acceptanca critaria acceared more stringent than necessary; in other casas, th? 25 tolerance did not provide a meaningful ecmparison of para.? stars. Licensee representatives stated that SP 2301-M4 would be revised to provida appropriate acceptance criteria. This item is unresolv,ed pending revision of SP Z301-H4. (323/78-36-04)

SP 2301-NS, Revision 1, was issued on Septem:er 29,1978 to provide an feproved method of calculating RCP seal return flew.

The inspector noted that the

  • revised procedure cmitted a square root sign in the equation used for the flow cceputation. This a

error resulted in higher than actual calculated seal return

.Q flows fecm each pump for the past three months., The erTor was conservative with respec* to Technical Specification RCS leakage limits. Prior to the end of the inspection, a TCt was pre;ared to provide the correct edJation. The inspactor had no further questions concerning this item.

The inspector noted two inadecuacies with !? 2303-M13. Revis-fon 1 dated August 9, 1977. The precedure recuires racerd-ing of the tima on ;;pendix C of CP 2102-4.1, when R.S. purge exhaust isolati n valve AM-V3A is opened in Podas 1 and 2.

Technical Specification 3.5.1.7 which became effective on February 8,1978, requires the accumulated time with any cen-tainment purge supply and/or exhaust valve cpen, when in Modes 1, 2, 3 and 4, to be < c0 hours for the preceding 365 days, In addition, CP 2102 T.1 Revision 3, dated April 18,1978, de-

[t 1eted Appendix C and required recor frg of the time, when these 4

valves are open, in a log book kept at centrol roca panel 1'

25 where the valves are operated. SP 2303-M13 requires revis-I fon to be consistent with T.S. 3.6.1.7 and OP 2102-4.1 require-6 ments. The log book requires review to ensure that the accuru-lated time is correct with respect to completing SP 2303-P.13, ii

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as well as Reactor Buf1 ding purge and depressuritation opera-M

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tions. This item is unresolved sending ccmpletion of the above corrective actions. (320/78-36-05) l 1

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L Technical Specift:2ti:n Surveillance Retuire=ent 4.6.1.1.a.1

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states that, for certain valves, blind flanges and deactivated F

auto:natic valves which are locattd inside containment, these penetrations shall be verified closed during each cold shut-do.n (Mode 5) except that verification of these penetrations

.{ ' <:..';.' - w. 4%' '.W ' :.O.. s: "* '~'.< beingk closet need r.ot be perfomed more often than once' per 92

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days. SP 2311-5 inco p: rates this requirer ent to verify that

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containment isciatica valves and flanges inside c:ntainment b'

are closed, and, in addition, inc:rpor:tes sepsrata require-mants to verify that airlock dcor seal leakage is within limits. The valves inside cen airn:ent ware verified closed during perfor-anca of SP 2311-5 on August 26, 1973, while in Hod.e 5.

The plant entered Fede 4 on August 28, 1978 and was subsequently in :*:de 5 during fievember 10-20 and 23-30,1978.

The plant has been in E de 4 or above since Cace=ber 1,1978.'

The air lack door sest leakage portion of SP 2311-5 has been properly perforced throughout this period, but the valve verification porti:n of SP 2311-5 has not been c =pleted 2 face August 25, 1972.- Failure to perform surveillance of valves inside contair=:ent is c:nsidered an Itam of Monccz oliance at the Ceficien:y level of severity. (320/73-36-06) 5.

CTeanliness (Cnit 2' a.

Progrm Review The inspect:r reviewed the felicwing precedures.

Station f-c=fnisthtive Procedure (SAP) 1003, "Ccod House-keeping," Revision 4 SAP 1020, "Clesnliness Raquirements," Revision 6 SAP 1030. " Cent-ci of Access to Pri.m.a y Syste= Cpenings,"

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Revision 2 SAP 1034 (Unit 2 Caly), "C:ntrol of Cor.bustible Materials "

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The'rrocedures were reviewed to verify that written admints-trative controls have been established to assure adequate j

housekeeping and cleanliness and that the procedures used included require ents for the following items.

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Material accountat.fif ty in critical clean areas such as openings in the prinary system, work on pricary system l

components, and the refueling area l

Cleaning prt=ary systes cceponents that have been re-i

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Returning excess ew!prent or material to applicable g

storage areas of the facility u.

Prompt removal frtrs the facility of cer:bustible material and debris Acceptance criteria for this review included applicable re-quireccents of Technical Specifications, ANSI ttla.7-1972 and Regulatory Guide 1.39.

Findings were acceptable.

b.

Teole-entatien Review The inspector interviewed selected ifcensee personnel to ve-ify that they are ccgninnt of and use the abcve precedures for f) the control of housakaesing and cTeanif r'.ss.

Additionally.

.at varicus times durir.g the ins:ecti:n, the inspector cor. ducted tours of the P.eacter Evilding Auxiliary Building. Turbine Building arid Control Zuildir.; to verify that the program fer housekeeping and clean!! ness control is effective.

  • The inspector's findirgs regarding these Ites were acceptable.

Areas which needed h:.usekeeping fr;.eveents we-e discussed with licensee resteser.tacives. T e cer.diticns observed did-not cause an icediate fire or safety problem.

6.

Reactor Protection Syste greunding Snta-Tastfra (t' nits 1 and 2)

Cn l' arch 8,1978, B&'.! nettff ed the t:RC about a potential RPS ground-h.

ing. safety concern, pursuant to 10 CFR Part 21. The Er4 letter to the t:o.C.-dated March 9,19T3 d:cumented the evaluation of this cen-cern, wherein it was postulated that a lesseof ground could cause the f*I/RPS to fail to perfor:: its inter.ced function.

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.9 The preliminary safaty cenc9rn preposed the fc11cwing hy;othesis:

a fil/RPS ch:r.nsi eay em:erience a loss of grouad to its instru=ent j'

...,.,..,dition,asinglepostulatedfailureinenechanne$ven cox=en without the loss of ground being evidant; -i can leave the g.4,. i unanaly:ed cer.dt tiens. The cencern. exists for. those plants.....

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that utill:e a ground as an active return pat.. fr.cluding TMI Units-ar t

i BW recc:: ended that applicab!e facilities institute a I

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periodic test of the III/RPS to assure that gecund has not been lost.

i:RC:sRa detar=ined that this r.atter dcas cet re;gsent a signif a

li:reever, the a;piteable licensees steu. rev ew,-- g robles fng systari for their plants in ac:ordance with the rccoc=endations to verify, en a of SW and should have an engsing test prograf:

periodic basis, the gr und centinuity of tne fil/RPS-RR, Serial GQL G752, da'ted April As stated in HEC Letter to !:R":::the-Ifcensee r.as reviewed the c:rcern raised by 25,1973, The possi':llity of Icsing ground disagrees witn the SW finding.

within tha ti*/2?S was evaluated by Unit 1 and Unit 2 PORCs and by P.EC's Generating Engineering Section, which agreed that a :'ouble There-failure sculd be required, to cause the syster to ha degrad2d.

fore, tne BW concern was net c:nsidarM to represant a substantial

? cnetheitss, a loss of RP5 gr09nd c:ntfruity check has haen i=ple ented for THI Unit 1 Surveillanca 7.-:cedare 1303-4.1 safety ha:3-d.

9 16, 1978, "Reect:r Protection Systra," Revisicn 29, datad Octcher includes checks for a loss cf greu-d c:ntinuity duct g performance These cf weekly protective char.nel coincidarce 1:;fc surveillance.

checks 411 identify the loss of c:nnection of the ;iant ground Licensee syste:t to Ore or s: Ore fC/RFS channel instru-t st ::c--ns.

rapresentatives stattd that si=ilar g-und centinuity checks will 21,1977. The ins.tector be frale ented for T'iI Unit 2 by January had no further questiens concerning this..:tter at this ti:.e.

Stea !!cunted Limit Switches - Envircr: a-tal cualificiatien (Units k

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1 1 anc 2) g Na2/ DIS has established that pc er c;erated centairment isota-l

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tien val,e pcsition indicatics to the c:ntrol rec = operator is At cther nuc1 car st. ions essentialdurin[-andfeilcwingaLCCA.certain enviren entally unqusilfied (SFLSs) me~ used inside containment to provide such indication.

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Those factitties have been required to replace the un:;ualified

APCO-type S:'J.Ss.

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The inspac*ne reyfe::cd 2; c;,-Ilcability of this pr:ble.: at both TMI units. With respect to Unit 1, no faCO.rpa 5:15s are used inside contain::: ant for containrent isolation.alve position Indi-cation. Relative to Unit 2. eight !MMCO-type Model EA 740 2 000 5:1Ss,are used.inside containcent for position. Indicat. ton of. K3 1

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purge supoTy and exhaust valves. ' The inspector verified that these

? MMC 3 5:153 were a different codal than those identified as environ-mentally un ualified, t.fcensee representatives stated that the limit swit:hes were qualified but no documentation was available for the ins;ector's review onsite. The ifcensae is conducting a generic review of the envircreental qualificati:n of safety-related electrical equipcent at both units in res=onse to IE Circular 72-03

(?.eference: Inscector Followup Itect 320/73-29-C5). This itsa is unresolved pending verification that the above Unit 2 MC-type 5:15s are qualified. This will be acc mplished during a' subsequent inspection at the corporate office. (323/73-26-C3) 8.

Unr= solved Itz s Unresolved ite:s are matters abcut which more infor-Stion is re-l quired in order to ascertain whether they are acceptable ite s, itacs of nonce =pif ance, or deviations. Unresolved ita 2 disclosed during the inspection are discussed in Parsgraphs 4 and 7.

9.

Exit Interview The ins:ector r et with ifcensee re:resantatives (denoted in Para-graph 1) at the c nclusten of the inspectica on Occa-1,er 14.1973.

The inspector su:=2rized the purpose and scope of the inspection and the findings.

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