ML20085B263

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
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: ML20085B254 ML20085B263 ML20085B278 ML20085B288
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

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.tepcre .No. ca.39am.se  ! r H 3 r:cT 037AIN* 3 -

..., ncc LN Accc toAt: .r urH Ic, c..1.23

. , Cocket No. 50.-289 et 796 C

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

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i o_n_ ear cat g casa <-n . se -.<vT ..an < s T eca*1 Tacility Nace: 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

, Ins;;ectors: "" - 1/d-[M ate signed

- D. R. Haverkamp, Reacto/ Inspector "

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

• O h $ k e.$ e, . 'u/*? _ _ _ , _ .

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

e. _ .s" _/ -ca:es-79

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signed

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

/ ;io,1,,F35 3r .

Inse=cdon su-rary:

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

50-32C/ 73-36) L 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 inspector and ?t hcurs ensite by t.to inspector-trainees. U Res'Mts (Unit 1): F:o items of nonccepliance were identified. L i

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

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

YRegica I Fom 12 (Rev. A;ril 77)

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CETAILS  : ,

1. Persons Ccntacted I,

Metreeofitan Edison Com:any [<

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,a: . _ . 3 ,. g .g 7. Lead Mechanics 1) Engineer-  %.'-

Mr. It. Sensel, Unit 2 Lead Electrical Engineer ..

• Fr. M. Bezilla Unit 2 PORC Secretary Fr. J. Chwastyk Shift Supervisor }f 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.

• demtes thosa present at the exit interviews en Dece-ter 14, p ISE ,

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- 2. Licease. ace 4nn on pr.wim.c in<cachnn Findines ( v I

- (Closed)' Inspector FoJ1cwup Iteer 289/73-C2.C1: LER 77-25/3L Cor- I f 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

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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 3 were cor plett:d as described it. ?!C Letter t2 ::?.C ::ogien I. Serial 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 L, '-

(Closed) Unresolved Item 320/73-24-06: !IE 73-01 Coirective Actions. l Valor type contact ar:a retainers wer2 installed in applicabla GE CK 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. l

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m. TP 272/1. Main Feed Pump.

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

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Exception E-27. - *ained 74t power with cne c;:arating main i fent Test. the plant 77 272/1. E-27. fio {

feed pup.. which met ..a intent of resolving The r z  : .. specific ficw data were required to be annotated .;,,,. in TP 272/1. . . , - I. <

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inspector'had no further questions cencerning,this iters. ,

320/73-29-00: TP 330/5. Centr si Rod Drive i (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 and 6-7.

verification of the in-limit lights fer Centrol Rods its.

GP.C Cuorun Requiremnts.

(C1: additicnal Tw2 sed) Unresolved C2C marabers Item 32C/73-29-Gt:

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

further questions concerning *.his itect.

m (Closed) 1;r. resolved item 'iri: 320/73-29-C5: Frecarttica and Review ten PCEC r:inutas hata been prepared of PO?C Festing :itr. uter.4etir.g ::o. 292 (C:tober 23-7;: vet 2r 3.1978).

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The GRC Cait 2 FORC of review  : PORC ceeting rinutas has been : -oleted thrtugh Sutsac en: written PORC The inspector FCRC l'estir.g ::o. 275 (July 11 '4.1973).

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 (Closed)

Extinguishers.

Unresolved Item 22C/73-29-07:The inspector reviev.ad Precedu a Fire Extinguisher Inspection. Re<ision 0, wMch provides require-f s:ents t: insure that portable fire extinguishars are properlyThe inspecto 8' inspected on a renthly frecency. The appears ad2:;uste for future centrol of fire extinguishers. }

inspecter : urad portions of the auxiliary building and turbine [

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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3' (Closed) Inspector Followup Ita= 320/78-29-03: Unplugged Piping -

Penetration. The fuel cil storage tant cross-cennect pipo pene. r, tration has been plugged per EC:1 5-9035. The inspector had no ,

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. (Closed) *!nresolved Item 320/73-32-01:

for runback Runback rate testing Rate was Test.re- The '

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

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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-view of documentation provided by the valve vendor. The A-E is 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 Siemans operators Osage and replacedent wil! be reviewed during Q ,

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 Control Roc s to obserte plant operaticas during off-nor .al hours. Con-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: .

plated at 8:30 a.c. Finding; were acceptatie, except as noted l't below. .

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-- Several radiation control discrecancies were cbserved by the -

inspector cur:rg tne untt 2 Auxiliary Guilding tour. Used .i

- protective clotning was laying on the ficar and used rubber I 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  :

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

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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

-~ The inspector observed process instr.:::entation eenit: ring current .

cperaticas on Cece;:bar 4-6 and 13.-14.1978 and reviewed records of reactor cperations durin; February-te: estar 1973. The following :L -

logs and records were reviewed on a sampling basis. i

- Shift Fore =an Log -

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- 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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'- 21C2-1.3,'

• Unit Startuo," Revision"10 (TCis 2Df8-665,'2-78-667, 2-78-670, 2-78-700, 2 78-709); in progress en December 7, 1978

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

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- 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

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- 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' L

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- 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-

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- 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-

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- 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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-- 5' 2301 :c. "Se'an injection System Valve Lineup Verifica- '

1 tion." Revision 2; c:mpleted during July 26-Cecember 3. 1973 l

SP 2301-N4. " Remote Shutdown Instrumentation." Revision 3;

-@- . an -e .g , . , . . , ,c ,, ., .;,. comp leted. during August

,23-Cece=ber .. ,,

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-- 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; completed during 11 arch 22-tiovember 17. 1978

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- 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 t,

10. 1973 },

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- SP 2303-Q3. " Hydrogen Recer.biner Functional Test." Revision 1' 2; completed October 11. 1978 [

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

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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.9 Tank concentratten and I

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.Revisien 2; c=.=p;ated Septa =ber ,, ,. ,,. , , ,,, , ,,

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- SP 2311-2.

• 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 a and *he following Technical

- 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 3.3.3.5 (Table(72 ties 3.3-9 3.3~ 3'- and*-= s3.3 1 and 4 its3; s 1.b and 2.b).

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 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 ["'

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

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- 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 p 51 and Section 4.2 steps 2 and 4 were not initialed as 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 Valve Lineup was not fully cecpleted; - l

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 l.

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being completed, and the partially completec procedure rw i

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

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

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1. 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 -

2 as being completed;

n. OP 2105-1.3 (partially cc=pleted October 9,1978) - Sec-tion 4.2 steps were not initialed as being completed; and, u

o. 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 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 9

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nu=ters, g The above file and working copies of operating procedures were -)6 i for centrolled use. These **

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e 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

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

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-- SPJ' 01-M4 f accr;cntas Technical Specification Survelliance ,""

. Requirement 4.3.3.5 monthly channel checks of remote shut- 8

' down monitoring instrumantation. Completed SP 2301-M4, dated

• i December 5,1973, listed several remota shutdown instrument I j ...a....ejq.,. @, , . < . -

... uma. ,. values which were at or slightly. exceeded the acceptance . k.

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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 a

root sign in the equation used for the flow cceputation. This error resulted in higher than actual calculated seal return flows fecm each pump for the past three months. , The erTor

.Q 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-1eted Appendix C and required recor frg of the time, when these 4

[t 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~

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

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

, 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 * ** - A_

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

containment isciatica valves and flanges inside c:ntainment are closed, and, in addition, inc:rpor:tes sepsrata require- b' 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

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• 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," +

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

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

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

cox=en without the loss of ground being evidant; -i can leave the s-

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t that utill:e a ground as an active return pat. . fr.cluding TMI Units- i 1 and 2. BW recc:: ended that applicab!e facilities institute a I periodic test of the III/RPS to assure that gecund has not been lost.

a i:RC:sRa detar=ined that this r.atter dcas cet re;gsent a signif robles li:reever, the a;piteable licensees steu. rev ew ,-- g

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, disagrees witn the SW finding.

The possi':llity of Icsing ground 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 9 safety ha:3-d. ? cnetheitss, a loss of Surveillanca RP5 gr09nd c:ntfruity check 7.-:cedare 1303-4.1

,* has haen i=ple ented for THI Unit 1 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- und21,1977. centinuity Thechecks ins.tectorwill be frale ented for T'iI Unit 2 by January had no further questiens concerning this ..:tter at this ti:.e.

k 7. Stea !!cunted Limit Switches - Envircr: a-tal cualificiatien (Units 1 1 anc 2) . g

RC: Na2/ DIS has established that pc er c;erated centairment isota- l tien val,e pcsition indicatics to the c:ntrol rec = operator is  ;

At cther nuc1 car st . ions essentialdurin[-andfeilcwingaLCCA.certain enviren entally unqusilfied t

(SFLSs) me~ used inside containment to provide such indication. i Those factitties have been required to replace the un:;ualified

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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 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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