IR 05000295/1990026

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Insp Repts 50-295/90-26 & 50-304/90-28 on 901022-26.No Violations or Deviations Noted.Major Areas Inspected: Training Concerns & Quality Verification Effectiveness
ML20062F675
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 11/16/1990
From: Nejfelt G, Phillips M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20062F665 List:
References
50-295-90-26, 50-304-90-28, NUDOCS 9011280111
Download: ML20062F675 (7)
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Text

{{#Wiki_filter:. . . . . U.S. NUCLEAR REGULATORY C0lmISS10N REGION 111 ' ! Reports No. 50-295/90026(ORS);50-304/90028(DRS) < Docket Hos.

50-295; 50-304 Licenses flo. DPR-39; DPR-48 ! Licensee: Commonwealth Edison Company Opus We-t III , 1400 Opbs Place . Downers Grove, IL 60515 ' a Facility Name: Zion Nuclear Power Station --Units-1 and 2 Inspection At: 2 ion, IL 60099.

Inspection Conducted: October 22 - October 26, 1990 Inspector: pp ofa [) (6 f 9D W.f7.JOjfelt fg Ifate ! i Approved by: M W)(1)lf) llf/lofk6 IForite /N Phillips,ThieT-op-Data

Operational Programs Sect'on < ! Inspection Summary ) Inspection on October 22 - Octokr 26, 1990 (Reports flo. 50-295/90026(DRS); r No. 50-304/90028(DRS)) Areas Inspected: Rou'dne, announced ins ection to follow-up on findings from the emergency verating Reports flo. 50-295/90004(DRS) procedures E0Ps)TeamInspection(flRC~ inspection

50-304/90004(DRS)) covering E0Ps - technical deficiencies, training concerns, and quality verification effectiveness.

Results: ilo violations or deviations were identified. All open items from the T07 Team Inspection were closed.

In particular, the. licensee's self initiated quality assurance (QA) audits in the area of procedural control were .foundtobeeffective(discussedinParagraph2.b.(4)). ! , 9011280111 901116 PDR ADOCK 05000'295

O PDC l .b

, .- -- . ,.

3 < .' . < . REPORTDETAILSI 1.

Persons Contacted ' < a.

Commonwealth Edison Company (CECO) Personnel +* Adams,LA.R., Senior E0P Writer,_ Contractor- - *Beale,: Gal.,L Regulatory Assurance Staff. . >

. >

  • Bump, D.A., fluclear Quality Program:-(NQP) Department,.

Superintendent- .

  • Denenburg,-G.A., NQP, Group Leader

+ Joyce, T., Station Manager q + Kurth, W., Production Superintendent: -,

  • lladden, J.J., Assistant Technic.al-Staff. Supervisor -

! ' + Saksefski, T., NRC Coordinator,. Regulatory Licensing -}1 .

  • Rieck, T. A.. Technica l' Superintendent

+*Valos,':N.', Operating-Engineer . In addition-to the abose othermemberslofthePlantStaff(e.g.~, training licensing, etcd.were contacted;during the inspection period.

L b.

clear Regulatory Commissjon (HRC)

l -

+*Leemon, R.J., Resident Inspec_ tor.

. +*llonninger, J.D..: NRR ' l -

+ Denotes those present at~ Entrance'llecting on October 22,-1990.

  • DenotesthosepresentatExitMeetindofl0ctober 26, 1990.

2.

E0PTeamFo110wvojtems(92701) < (CLOSED) Open Item (295/90004L01; 304/90004-01):; LThe corrective i! a.

actions takep by the licensee -to-resolve the E0P ' technical-deficiencies. were reviewed by the inspector.. Procedural changes were completed by-the licensee to resolve the following items: . s

(1) subcriticality guidance ;

(2) contingancy for tripping reactor coolant pumps ;< (3) restgrationofpowerto-_servicebusesfollowingcreactor.

tr.ip.; and ' (4) verification of injectionihead for emergency.boration, 5-The following two evaluations were not-yet -completed by the licensee. - (1) Determination if-the-containment spra when' the reactor gater -storage tank (y-pumps can be stopped-j RWST) level. reaches its- "LO-LO" set-point was-scheduled for completion six months: after receiving theontracted Westinghouse study? Atithe Exit c 2 -: ' , I.. - -, . . .- lleeting, the Technical Superintendent comittEd to obtain a.

firm date for the completion of the vendor's work.

. (2) liethods to refill RWST to maximize length of time-as source for ! ECCS pumps were being-analyzed by the facility. The licensee has identified events that could involve,the RHST as the only source of water for injection (e.g., E0Ps E-0, ECA-1.2, and .ECA-2,1); and has comitted to include criteria for assessing the need for refill'of the RWST m procedure revisions no later than December 31, 1990, The actions 'taken by the licensee for this open item were found acceptable and long term comitments were established in the licensee's tracking system. This open item.is' considered closed.

., b.

(CLOSED) Open item'-(295/90004-02; 304/90004-02):, The.following-E0P Team Inspection concerns identified during in'-plantiwalkdowns were resolved: (1) Weaknesseyinproceduralvalvelocation'identificationwere' > wrrected. Also, therlicensee took the initiative to correct otheritemsthatweresimilarinnature-(e.g.(MOV)gl-operation'- loe of auxiliary feedwater motor operated valves

and
valve line-u r gravity feed between reactor water storage tanks (RWSTs )

> (2) As-a compensatory action to. provide gergency lighting-inLareas with no permanent emergency lighting., the licensee planned to utilize flashlights and miner-helmets which were maintained for, fire protection usage in locked cabinets. 'Alltin-plant equipment locations that would require access to perform E0P action have been identified. However, long term corrective action to install additional permanent emergency-lighting in the plant is . date of June 1,1991{2)he licensee's. evaluation:(commitment pending completion o t ., to determine number and location of emergency lighting.

(3) In-plant radio conaunications wereLtested g several locations in Unit 2 satisfactory on -October -25, =1990. Also, the ~ inoperable in-plant telephones identified in the E0P Team Inspection were repaired and'no additional-phones were found inoperable.

Inability to maintain continuous radio ~ communications ' in the-feed regulating valve areas was to be. corrected by enhancing radio communication hardware (to be com ed by 1993,: based upon equipment availability.from the vendor (4) The concern with the control and use of E0Ps by the Auxiliary.

Operator-(AO) was rasolved on-0ctober 25, 1990,.with a demon - stration by the licensee. - Several in-plant tasks that would . be directed gy the E0Ps,;such as isolating reactor cogant pump

(RCD) seals and prevention of accumulator discharge ,were determined to be performed satisfactory. The information for < performing the local E0P-actions was concisely given to the A0 by a Unit Supervisor..Also, ~ thgunit Supervisor required repeat backs.for the information given i

J '

., a .- . . P To address the E0P Team concern for providing equipment operators with E0Ps to be' used in-plant,. the licensee placed , controlled copies of E0Ps in the contro11 room.for immediate-y distribution. The-inspector noted that1these E0Ps were not-included in a weekly audit with other controlled information in-the control room. To correct this, the EOP copies for use(in: the plant were= placed on a wee,kly, audit schedule.. Upon:further review, it was. determined that aLfacility self-initiated quality-

assurance (QA). audit of controlled procedures.ha'd identified. theneedtoestablishformalprocedu.ralverifgationofcontrol- ! room documentation'used forfplant operations.

=furthermore,- t the licensa was' evaluating a method of using.a computer check - i of the. procedural. data base before a procedure was used to g supplement.thel routine audits.. The actions taken by the ' licensee to resolve.this= open item were >i a found acceptable and -long term commitments'were' established in the-licensee's tracking system.' This'open : item is considered close l.

i c.

(CLOSED)OpenItem(295/90004-03;1304/90004-03): The E0PTTeam.

' , . Inspection identified the need-to providecEOP basisitraining tod non-licensed operators. To resolve this concern, a: training plan

was established by the'1.icensee. llowever, full implementation for , go all non-licensed operators will: not be completed until Aanuary 1,'19M '. Another concern identified by theLEOP Team was that the. policy) for - t control room protocol was not formalized.: The E0P Review Committee . was currently considering a new ZAP 5-51-4' series procedure to resolve this concern.-

The actions taken by the. licensee Ifor this. open item were found. acceptable and long term commitments were established in'the licensee's tracking system.. This open item:is considered closed.

d.

(CLOSED) Open Item (295/90004-04; 304/090004-04): The EOP Inspection x Team determined that the lgensee failed to actually walk-down.al'i-

l specific local E0P actions. To! correct this~ concern, the licensee , revisedthevalidationproceduretE0;nsurethatE0Ptaskswill e + actually be verified in=the plant-and walked =down all.the local.

E0P-actions. Additional guidance was also provided in fluclear) Quality Program Instruction (tlQPI) flo. 22, "i'se of Field lionitoring; . ^ Program," Revision 0, for conducting QA field walk. downs and ' categorizing the+ findings.

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. . . .. . , , 110 violations, deviations, or unresolved -items were. identified.

Four previously identified epen items were closed.

3.

Entrance and Exit fleetings Theinspectormetwithlicenseerepresentatives(denotedinParagraph1) to discuss: inspection scope on October 22, 1990, and. inspection findings on October 26, 1990. The' licensee did not identify any documents or processes for this' report as proprietary, c

l y l

. -5 _ _ _ _ _ _ - - _ - - -..

.-

. , . . . ENDNOTES USED FOR , ZION E0P FOLLOW-UP REPORT tl05.

50-295/90026(DRS) AND-50-304/90028(DRS) . t 1.

Zion E0P Team Inspection Report !!os. 50-295/90004(DRS)and 50-304/90004(DRS), Paragraph 2.c.(1).

2.

Procedure change 0-90-0484 deleted ambiguous caution from Zion Critical

Safety Function (CSF) status Tree F-0.1.

,

3.

Added as immediate action in ELO, " REACTOR-TRIP'0R SAFETY' INJECTION," l -Step 6.c, Rev.'10, with Procedure, Change 0-90-0097.

4.

E0P' ES-0;1, " REACTOR TRIP' RESP 0tiSE,"' Rev. :10, Steps 7 and 8 were revised;. i - and Appendix C was added to restore offsite power to the service buses by: Procedure Change 0-90-0557.

'~ 5.

FR-S.1, " RESPONSE TO NUCLEAR-POWER GEllERATION/ATWS,"'Rev.:7, Step 6 was ~ _ revised as an immediate action by Procedure Change 0-90-0228.. 6.

Westinghouse evaluation is tracked as 295-100-90-00401.03.

7.

Procedure Change 0-90-0488 corrected location levels for. valve accessibility.

8.

Procedure Change 0-90-0115 for' E-2, " FAULTED SG ISOLATION.'? a-9.

Procedure Change 0-90-0488 for ECA-3.2, "SGTR WITH LOCA --SA1URATED REC 0VERY."

, 10. No emergency lighting fixtures were found in the pump rooms for core spray (CS), residual heat removal (RHR), safety injection-(SI), and charging that could require entry using ECA-0.0, ECA-0.1, and ECA-0.2.. 11. Equipment is audited by PT-231, " FIRE OPERAT"tG' PROCEDURE EQUIPitENT INVENT 0RY CHECK."

12. Licensee's response for the E0P Inspection Teain Report dated - flay 4,1990, Attachment 1.

13. Unit-2 Diesel Generator Roons and auxiliary feedwater pump area.

14.

See licensee's response-for the E0P Inspection Team Report dated' May 4,1990, Attachment 1.

~ = 15. ECA-0.0, " LOSS OF. ALL. AC POWER,!' Rev. _10, Steps 7a and 7b.

. 16.

ES-0.4,"NATURALCIRCULATIONC00LDOWNWITHSTEAMVOIDINVESSEL(WITHOUT RVLIS)," Rev.=6, Step 12.a.

17. ZAP 10-52-7, "0PERATIONAL C0!iMUNICAT10tlS," Rev. 3.

18.

Facility QA Report, NQP.22-90-01, Finding No. 2.

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