IR 05000289/1976024

IE Insp Repts 50-320/76-16 & 50-289/76-24 on 761012-15 & 21. Noncompliance Noted:General Ofc Review Board Meeting 24 Conducted W/Alternates Not Duly Appointed & Required Signs Not Posted When Fuel Movement Activities Commenced

ML19207B216
Person / Time
Site:	Crane
Issue date:	11/05/1976
From:	Davis A, Fasano A, Finkel W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19207B214	List: IR 05000289/1976024 ML19207B213 ML19207B215
References
50-289-76-24, 50-320-76-16, NUDOCS 7908230601
Download: ML19207B216 (35)

Text

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.j _ _. - ..,r ---'~~ g, gy _ # gg N (Jan 75) (Rev) NOV 8 E76 ' - NW I HAS NOT catu : : p ::*:may 55- - . N m AcccCr. n.m ;3 cra 27so ~ ~ ' p.. p:: . . U. S. NUCLEAR REGULSTORY CCMMISSION

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OFFICE CF INSPECTICN AND ENFORCDL%T - ~-" .

REGION I

. -_. ' 50-289 - ~.. IE Inspection Report No: 50-289 /76-24 and 50-320/76-16 Docket No: 50-320 der-cu

, Licensee: - Metropolitan Edisen Cenpany - License No: CPPR-66 , i':... P. O. Sex 542 priority [[ Reading, Pa. 19603 - C' U .Categcry: 3-1 Safeguards . Group: . Loca tion: Middle:cwn, Pa. (Three Mile Island )- Uni: 1: PWR 2535 F4: (36W) Type of Licensec: Unit 2: PWR 2772 T4t (3&~4) Type;cof Inspc t.icn: Routine, Unanncunced . - ' h h a Dates of Inspe::icn: October 12-15 and Oc:cber 21, 1976 U21 iJj{lQjg i U:1: 1: Sep tencer Au, Ano - Dates of Previcus In pectica: Uni: 2: Oc:cber 12-15, 1976 . Ecporting Inspecter: _ [M o cus-O // /1/ ~ s A. N.

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///M/l - ' Reviewed By: o A.

3. Davis, Section Chief, Reacecr Projects cec :.cn Nc. 1 DATI Reac:cr Operations and Nuclear. Supper: 3 ranch . /@,34 _.

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SUM'.ARY OF FINDINGS , __,. Enforce =ent Action Ite=s of Nonco=ollance ~ ~ A.

Violations j s-Mone ...... 3.

Infractions None C.

Deficiencies 1.

Technical ?pecificatien 6.5.2.3.3 requires that alternate =e=bers of the Gene: :1 Office Re'."_ev 3 card (GORS) be appointed in writing by the cha..- =an or vice chair =an to serve en a te=porary basis and TS 6.5.2.3.6 alleus the taking of credit of two duly appointed alternates to satisfy a cuoru=. Centrary to the above the GOR 3 =eeting No. 24 was conducted

with alternates not duly appointed.

(De: ail 12.c, I:e= 76-24-13) 2.

Special Nuclear Ma:erial License No. 1671, Septe=her 23, 1976 states tha: the license authcri:es receipt, possessien, inspec-tien and s:crage of fuel assemblies in accordance with the state =ents and conditicas which are specified in the licensee's application dated July 13, 1976.

Section 6.2(1) page 4 cf : hat applicarica states ir. par: "... signs will be pos ted in the building prchibiting the use of fire hoses, fcg Er fea= fire fighting equip =ent within the building..." Contrary to the above, on Oc:cber 14, 1976, when fuel =ove=ent activities ce==enced, the recuired signs had not been posted.

(Detail 14.a(1) (f), Ite: 76-16-1) Licensee Action on Previcusl" Identified Enforcement Action Corrective actions taken in respense to NRC:I Inspec:icn Reper: 30-289/ 76-15 were cc=pleted.

(De nil 15) Des 12n Chances None reported.

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. The occurrence involved the release of Plant River Water Discharge having _ dissolved solids in excess of Enviroc= ental TS 2.2.2.a limits (700 ppe).

The event occurred on 10/12 during the release of a vaste neutrali:ing tank contents. The analysis of the Plant Waste Water Di. :harge was ' found to be 772 ppn. The total volume released was about 51,790 gallons.

The licensee transnitted a written report en this occurrence.

Other Siznificant Findines A.

Current ,, yt aftidj{l j J J11 ' 1.

Accectable Areas (These are ite=s which were reviewed on a sa:pling basis and findings did not involve any Itens of Nonce =pliance, Deviations or Unresolved Items except where noted.)

a.

Non Routine Iven: Reports (Detail 3 except subparagraphs 3.c(1), 3.c(2), 3.c(4), 3.c(8), 3.c(9), 3.c(10) and 3.c(11) b.

Precurement (De: ail 10)

c.

Records (Detail 11) d.

Review and Audits (Detail 12 excep t 12.d) e.

Crganization and Adminis tration (Detail 13) f.

Fuel Receip Storage (Detail li except IS. a(1) (f) ) 2.

Unresolved I:ers 76-24-1, Tes t perfor=ance on Relays (Detail 3.c(1)) 76-24-2, FSAR Change For RC' Monit: Delay Tine (D=:211 3.c(2)) 76-2 4-3, Addi:icnal Evaluation o f ER 76-18/lT (De:sil 3.c(2)) 76-24-4, Repair of Valve MU-723 (Detail 3.c(4)) 76-24-5, Long Tern Correct!ve Action for ER 76-2S/4T and 76-35 /1T (Detail 3.c(3)) 76-24-6, Maintenance instructisn a:.d training (Detail 3.c(9)) 76-24-7, Modification of RCS Pressure Transmitters (De: ail . 3. c (10) ). .. _.. - - e - . . ~. ~ $ D" b _ _ ... . ..... ~.. - . . .. _ . - ~ .- * .. - <. ~ _. . .' _* . - ' '

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. ..~ . - . . _ m- . . - ,. ~3- ... . -_ -p.. .. .- s .: L... _. c,.. , , ., .. .-r - -3- .. _ .. 76-24-8, TS Change for Reactor Coolan Pressure Trip Setpoints (Detail 3.c(10)) .. , . -.. ~76-24-9, cause/Evaluatien of Pressure Trans=1 :er Being ou: cf Calibration (Detail 3.c(10)) ' . t::. 76-24-10, GORB Review of Repertable occurrences (Detail 3 c(11)) s 76-24-11, Housekeeping Precedure (Detail 4) 76-24-12, Revise precedures to include criteria en due date extensions ; ec=1::ent date for cocolecien, Januarv 3, 1977.

(Detail 6.b) 76-24-13, Revise procedures to include criteria en closecut verifica:ic cc=1:=ent date for ccenle: ion, January 3, 1977.

(Detail 6.c) 76-24-14, Verify Audit Reper: 75-32 is available at site CC files ; ec==1:=ent date f or ccepletion, October 29, 1976.

(Detail 6.d) 76-24-15, Revise GP-4407 to designate duplicate OC reccrd s:crage rec uire:ent : ._ itten: da:e f or cceple:ica, January 3, 1977.

(Detail 7.b) 76-24-lo, Revise p rocedures to specify hc> codifica:icns are sent to training; cc==i::ent date for ccepletion, January 3, 1977.

(Le: ail S.b) 76-24-17, Verify ccepletion of corrective action en NCR ~>E-76-439 ; cc :1: ert date for cc pleticn, Janua-r 3, 1977. (Detril 9) 76-16-2, ?rocedure revisien to include accep:ance. cri:eria.

(Detail 14.c '3)) . 3.

Status of Previcusiv Identified Unresclved /Other Ite s The felleaing 1: ens have been resolved / closed: 1.

A0 75-15 Further Investigation /I.cng Ten Action (Detail 5.a) 2.

A0 75-16 Further Investiga:1cn (De:a12 5.b) 3.

Procuremen: Specifications Access S tatement (Detail 5.c)

Auxiliary Opera: ors LeF Shee: Infe r cu ticn (De:sil 5.d) 5.

C*SS Reviee of Facility Frecedure Changes (Detail 5.e) 6.

S? 1302-3.l., RC Flux F10e Calibra:icn (De: ail 5.f) O '4 @%.- c ,)* . . e pa . - -. + -e 6 - e =e.-p .m+ % L.

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TS 3.3.1.1.a, BWST Manual Discharge T.

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Revision of S? 1303-11..C (Detail 5.h)

Preventive Maintenzace Procedures for Control Roc = Console ~~ Meters (Detail 5.1) 10.

Seismic Qualification of Stems Genera or Level and Pressure . Indications (Detail 5.j) 11.

Check Off Lists (Detail 5.k) 12.

Maintenance of Reactivity Plots (Detail 5.1) "- 13. Hold Times (Detail 5.n) 14.

Preventive Maintenance - Lubrication (Detail 5.n) Exit Interview I An ext: interviev was condue:ed at the site on October 14, 1976 with the folicwing attendees: Licens ee Mr. J. J. Colit, TMI-l Unit Superintenden: Mr. W. W. C ::er, Supervisor Quality Control Mr. C. E. Hart an, TMI Lead Electrical Engineer Mr. G.

A.

Kunder, Supervisor of Operation Unit 1 Mrs. C. A. Nixdcrf, Office Supervisor Mr. J. P. O'Hanlon, Engineer Senior Nuclear I Mr.

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S. ?cyck, ocrdinator of Services USNRC M.r. A. N. Tasano, Reactor Inspector k

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jjg Mr.

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E. Tinkel, Reactor Inspector [- Mr. W.

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Ruhinan, Reacter Inspector Mr. J. T.

Snith, Reactor Inspec cr Ite=s discussed included: A.

Ncn 5rtttine Even: Reports (Detail 3.c(1) and 3.c(9:) 3.

Quald :y Assurance Audits (Detail 6) C.

Quality Assurance Progran Changes (Detail 7) D.

Modification and Design Centrol (Detail S) E.

ANSI N45. 2. 6 Certificates (Detail 9) F.

Procur enent (Detail 10) G.

Records (Detail 11) 3.

Review and Audits (Detail 12) I.

Organization and Adninis tratica (Detail 13) 'IWbW 36o .. --- - - -. - -

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. . . . . .-- , . -5- . ~ A continuation of the inspection was perf arned on October 21, 1976 at I" the CPU office in Parsipany, New Jersey.

The Licensee was represented by Mr. K. Green and Mr. J. R. Thorpe.

Mr. A. N. Fasano discussed Organization and Adninistration, Detail 13, and Review and Audits.

Detail 12, with the GFU aersennel.

E Irit !nterview II . A second exit interview was conducted on site en October 15, 1976 with the following attendees: Licensee s Mr. J. Coli::, Uni: 1 Superintenden: Mr. J. O'Hanlon, Engineer, Senior I "uclear . Mr. G. Kunder, Supervisor, Operations Mr. M. Shatto, Ingineer, Associate I Mr. W. Cotter, Supervisor, Quality Control Mr. R. Earbin, Ingineering Assis tant CSNRC Mr. R.

L. Spessard, Rea :c: Inspector Itens discussed incleded: ~ A.

N o- -:u:ine Iven: Reports including the Unresclied I: ens.

(De: ail 3) 3.

Pcc/icusiv Identified Unresolved /Other I ens.

(Detail 5) - C.

Correc:ive Action ?cr a Previousif Identified Inforcenen: !:en.

- (Detail 15) Exi: Interview III An exit interview was condue:ed en site on October 14, 1976 with :he foll wing attendees: Licensee Mr. J. Colit:, Uni: 1 Superintendent T c'e s <i. 3 c i {s Mr. L. Weir, Reactor Ingineer E Mr. J. Ficyd, Operaticas Superviser Uni: 2 - }j{ ggj [ Mr. J. E111bish, Senior Reacter Ingineer CSNRC Mr. L. C. Sjcstren, Reactor Inspec:cr I: ens discuss ed inc2 uded: A.

T-~ receipt, handling, inspection and s:crage of new fuel for *Jnit 2.

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. DETAILS' 1.

Persons Contacted Mr. R. 3ailey, Le.ad Nuclear Engineer 3.s Mr. M. Beers, Shift Superiisor Ms. S. H. Ecnneville, Ad=inis trative Assis tan: ' Mr. R. 3cstdorf, Security Guard Ms. R. 3rown, Technical Analys t-Generation :ngineering Mr. J. Carr, 3&W Resident Engineer Mr. J. J. Colitz, Unit 1 Superintendent Mr. W. E Ce:ter, Suce viser of 0.uality Centrol Mr. G. Cvij ic, Security Guard Mr. I. Daniels, QC Specialis t Mr. D. Dubiel, E? Ferenan Mr. J. Dennachie, Radiological Chenistry Technician ar. R. Doty, Secres Supervisor Mr. J. Floyd, Operations Superviser Uni: 2 Mr. E. F. Gee, Jr., Quality Con:rol Specialist Mr. K. Green, Nuclear Cc:=itree Coordinator Mr. D. Geod, Technical Analys: III Mr. D. Earper, Instr.::ent Cen:rol Super 71scr Mr. C. Earrnan, Lead Electrical Engineer Mr. J. Eillbish, Nuclear Engineer

Mr. S. Jules, Mechanical Maintenance Ferenan Mr. E. V. Kellogg, Technical Analys: 2 Mr. R. G. Ecks tein, Quali:7 Assurance Engineer Mr. G.

A. Kunder, Super 71sor of Operations Uni: 1 Mr. R. McCann, F.adiation Protectica Forenan Mr. J. C. McGray, Mechanical Super 71scr Mr. 3. M. McCu:Cheon, Section Head-Quali:-/ Assurance Engineer Mr. G. Miller, Unit 2 ?lant Superincenden: "- C "#-^a, Elec:rical Supervisor Mr. R. Neidig, C.C Specialist Ms. C. A. Nixdorf, Office Super 71scr-Suclear } } gr Mr. J. ?. O'Hanlon, Engineer Senior Nuclear 1 l .t ,h Al .$I ' v..,..v.

c 1 .n_, '5C ' ead 7 ~3.' *.. e e. ..... . Mr. W.

S. Pcyck, Cecrdinator of Services ( Mr. J. Renanski, Health ?hysics and Chenis try Suoer71scr Mr. M. Ross, Shift Supervisor Mr.-W. J. Sawyer, Engineer-3 -Nuclear Mr. M. Shatto, FORC Secretary Mr. E. S*..eets, Electrical Engineer Mr. D. Shovlin, Supervisor Main:enance Mr. J., R. Thorpe, Manager of Environnental Af f airs .._ . . _ - .~ - . - . . ,.. , ... . - _.. _ . - c.

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. - . . f . t . .. s - k... - - ... :- J - 7- . P Mr. A. M. Trout =an, Clerk Junior Mr. A. Tsaggaris, Training Supervisor - Mr. D. Weaver, I&C Fore =an g{ g) Ms. L. Weir, Nuclear Engineer E Mr. H. Wilson, I&C Fore =an 2.

Purtose and Scoce of the Insoectica ,: . ..u This was an unannounced inspecticn which prinarily addressed the - yearly review of quality assurance.

The inspection included a review of specific Non. Routine Event Reports including visual inspections of event occurrence locations.

The areas specified in the Exit r Interviews rela.e the secpe of the inspection. The receipt of fuel was also witnessed.

3.

Nenroutine Event Reecr:s _ a.

Selected Reportable Occurrences were reviewed :o verify : hat: (1) The cause was identified and that details were clearly reported to the :TRC and facility canage=ent; (2) Corrective acti:n described in the licensee's reper: was , taken to preven: recurrence; (3) Each event was reviewed and evaluated as required by :he Technical Specifica:icns; and - ( 4) Safety limits, li=iting safety systen se::ings, and li=iting conditions for operation were not exceeded.

This review included physical observations cf affec:ed equip-cent /c =conents and i=plementatic: cf corrective actions where appropriate, discussiens with = embers cf :he plant staff, and ^ inspecticn of PCRC and GOR 3 =eeting =inutes, internal si:e =e=oranda docu=enting :he recuirements of TS 6.6, Shift Fore- =an's Leg, Work Requests (WR's', plan: design changes (C/M's), surveillance test records, procedure change rec.uests (?CR's), new and revised f acility procedures, records cf Reacter Building Purges and a radicactive licuid release, a proposed TS change, and a se=orand

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-be Superviser, Operatiens to the Shif: Forecen including the.c respenses.

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The Repertable Occurrences reviewed were: (1) ER 76-16/3L, Malfunction of an ESAS Auto Actuatien 2.elay during Surveillance.

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(2) ER 76-18/lT, Inadequate Ad=inistrative Controls Resulting In a Discrepancy between Actual Reactor Coolant Punp i* Monitor Delay Tr t and the Value Assuned in the.?SAR.

,_ (3) ER 76-20/3L, Malfunction of Reactor Building Isolation E Valve WDG-V3 during Surveillance.

' (4) ER 76-21/3L, Malfunction of Reactor Building Isolation Valve MU-V23 during Surveillance.

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(5) ER 76-22/3L, Failure of the Interlock Circuit between Effluent Monitor RM-L6 and :he Effluent' Discharge Valve _ ' ' WDL-V257 to Function centrary to ETS 2.3.1.b.

- (6) ER 76-23/lT, Reac:cr in the Startup Mcde Without Verifying P Operability of Scurce and Internediate Range Nuclear Instru=entation Prior to Startup contrary to TS 3.5.1.1.

(7) ER 76-26/3L, Inoperable Righ Radiation Actuatien Mede of the Reactor Building Purge Exhaust Monitor cen: ary to ETS 2. 3. 2.3. 3.

• (O TR 76-2S/4T, Plan: Discharge Water Tenperature was =cre

than 3 F less :han the River Wate 7 ' =- *> 7erature cen-trary : ITS 2.1. a. (1). (9) EE 76-30/3L, Failure of Cen:rol Red Drive 3:eaker to Trip during Surveillance.

(10) ER 76-31/3L, Low Reactor Ccolan: Pressure Trip Se:poin:s Cu: of Specifica:ica.

• (11) ER 76-35/1T, Plant Discharge Water Tanpera:ure was nore C

than 3 F less than :he River Water Inle: Tenperature centrary Oc ETS 2.1., '1). , (12) IR 76-33/3L, Eigh Reactor Ccolan: Pressure Trip Se: points Out of Specification, c.

The inscector's findings were acceptable excep t for these Unresolved I: ens delineated belcu. Also, inspection firdings relative to additional infernatica concerning these events are su==arized, as appropriate.

• Nc: Report.cle Occurrences, but are events reportable per ETS.

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--. / (1) With respect to ER 76-16/3L, and ER 76-5/lT, the Clark / relays referencad in ER 76-16/3L and 76-5/lT are PMAC G', " cover:1ble pole r-laya,10 a= peres, 600 volt, max 1=u= ..._.. AC 25 to 60 Hert:. The SU15-13 relay, referenced in

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ER 76-16/3L is in the Engineered Safeguards Actuation y:i-hr System (ESAS). This relay performs the follcwing function: Auto Actuation logic relay to go to its

' Engineered Safeguards (ES) position when an ES signal is received. During the surveillance testf ng per cro-cedure 1303-4.13, the relay failed to go to its safeguard position when its ceil was de-energi=ed by an ESAS tes: trip signal.

. The Clark relay referenced in ER 76-5/1T, SU12-11 is the Auto Ac cation Logic Relay in Reactor C0olant Channel 33.

While performing procedure SP 1303-4.13, the relay fa led _ to go to its IS posi:icn upon receipt of an IS trip signal.

This relay is par: cf the two out of three auto-logic for actuation 3, 31cck 4 cc=penents.

It failed again when channel RC33 was reset and tri ed once more.

By tapping the armature of this relay i: then vent to its ES pcsition.

The licensee rencved both the 5U14-13 and the 5U12-11 relays and replaced the vi:h spara relays.

The 5U12-11 relay was par:4. ally' disassembled by the licensee's electrical engineering group. During the disasse=bly of the 5U12-ll relay, Octal chips and filings fell out.

The licensee stated that a odification was done to the relay cabinets while at the plant and the retal dirt found in the relay prcbably is the resul: of the =cdifica icn work perfor:ed by :he licensee.

The SU14-13 relay was not dis as s aub led by the licensee.

3c h relavs were returned te the supplier for tes: and evaluation.

A repart frc= GTE Sylvania dated July 12, 1976 defines the tests tha: the relays we sub-jected to.

The tests are described belcw: (a) Cc=parisen of relay centrac: to catalcg data.

(b) Electrical cperatien of relay a: ra:ed vol:cge '? 23 C.

(c) Energi:ed relay ceil at rated voltage and frecuency 40 C a=bient rec: condition.

Checked C for one dav at drag and d' ep-cut.

r (d) Repeated No. 3 lbeve leaving coil energi:ed continuously fer 3 days.

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(e) Room at 40 C, operated each relay electrically + a dozen times.

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(f) Visually exa=ined each relay ce=ponent for. unusual - conditicus.

' It was stated in the GTI Sylvania letter that both relays ' passed the test described in steps (a) through (f) above with no failures.

During the visual exa=ina:1cn of the relay described in , step (f) above, the following condi:icus were noted: Relay SU14-13 Top lef t hand nor: ally closed pole centact spring tail was out of the slot in the cole operating rod.

The magne: pole faces were slightly rus ty and the lef: hand side nounted poles had a double headed silver bette: =issing on the rear stationary blade.

GTI stated "These faul:s, in our opinion, do not centribute in any way to - a possible failure to drop out."

The contact spring tail for Relay SU12-ll was incorrectly seated on a acnber of poles in this relay.

The extrere right hand pele in the deck i=nediately above :he contact ar: (nor: ally closed' as well as the third, fourth, fifth and sixth pole frc= :he righ; hand side on the sa:e deck had spring : ails incorrectly seated.

The SU12-11 and SU14-13 relays had the abeve conditiens corrected and were returned c the licensee on 6/1/76.

The licensee stated tha: the =enthly performance cf sur-veillance tes: 1303-4.13 is sufficient to detect any future relay proble=s.

The licensee plans to do a drep ou: time tes: en selected Cicrk type PMAC Convertible Pole Relays during the nex: cutage scheduled for March 1977.

This ites, 76-24-1, is unresolved pending the perfor:ance of the test progra: by the licensee and a subsequent review of the results by the NRC inspector.

(2) With respect to IR 76-18/lT, the licensee performed a QA audit of 3&W's C.C Progra=/ Organization. The audit findings were considered to be acceptable and the licensee plans no further action on this mat:er.

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__ - , . . :==. -11- .. -... / +y ..... . The licensee plans to revise the FSAR to include the nev . analysis perfor=ed by 3&W; however, the licensee could not ._ provide the date by witich this action would be ec=pleted

because of uncertainties involved in ob:21=ing infomation frc: 35W.

Revision of the FSAR re=ains to be ccepleted, E.. and this item (76-24-2) is unresolved.

, The supple = ental analysis was perfomed using the 3&W -2 ' , correlation, with fuel densification penalties and para-ceters conservative with respect to cycle 1 and 2.

Sub-sequent to this occurrence, the licensee reported (ER 76-24/lT) that 35W had info =ed the= that fuel densifica:1cn penalties were not properly incorporated into TS prepared for cycle 2, but that the elimination of the ven: valve by-pass flev penalty would more than cocpensate fer the error. The inspector asked the licensee if the supple = ental analysis as docu=ented in ER 76-13/lT was still valid based en this now info =atien (ER 76-24/lT). The licensee was unable to provide an answer to the inspector's question, but indicated this =a::e: would be reviewed and the inscec-ter wculd be advised of the results of this review. This iten (76-24-3) is unresolved.

(3) With respect to IR 76-20/3L, testing of valve WDG-V3 (ence/ week for four weeks) was cc pleted under SCP d413 cn July 9, 1976.

2 additional problems were encountered.

_.

(4) With respect Oc IR 76-21/3I, tes ting of valve E-V23 (once/ week for four weeks) was ccepleted under SOP 1413 en July 9, 1976. Valve ::avel ti=e and excessive running curren are still a prob 12=, and WR15772 war prepared to trouble shco: and repair the valve during the next scheduled outage.

The valve is closed (ESAS pcsitien). This WR is en the outage schedule, and an cu: age is clanned for late Oc cber 1976.

Rep tir of valve E-V23 remains to be cc=- pleted, and this itec (76-24-4) is unresolved.

(5) With respeen to ER 76-22/3L, the centrol rec = coerator was _ slew in responding to the ala= condition (Ala= Restense . Precedure C-2-1, page 30) in tha: the ala= exis:ed fc: . - about one hour before required ac:icns were ec=pleted.

' _ - Although the operator erred in respending :c this ccndition, ~ the situation was cecplicated by the plant startup in progress - c _ and the-temporary nature of the alar: during the ene hcur .. " - pericd (repeated ac:uatien/:learing of the alar =). The ~ . _ . - -. - - , _ _ . .- . - .

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% - e-t.: / operator ves i==ediately counseled by his Shif: Supervisor, ... _. mad all licensed shif t personnel were =2de aware of this

event during the third cycle requalification program.

._.. A discrepancy in the contents of the "3" Was ta Ivaporator iq Condensate Storage Tank (as reported by the licensee) was identified during the inspector's review; i.e., the tank E ' contained 91.6 uCi and not 91. 6 C1 (typc error). The .. licensee stated this item would be corrected by a revd sed .. _.. report.

(6) With respect to ER 76-23/1T, in addition to the Shif t Supervisor and CR0 involved being counseled by the Super-visor, Operatiens all licensed shif t personnel vere rade aware of this evert during the third cycle requalificatico progras. Additionally, 0? 1102-2 was revised by ?CR 76-412 (Rev. 17 issued on August 2, 1976) to req _ ire ec=pletion of S? 1303-7.1 and S? 1303-7.2 on both channels prior to startup if act done within the previcus seven days.

(7) With respect to IR 76-26/3L, the work being cerforced by WR 15763 was accceplished over a 24 hcur period tinvolved

3 operating shifts) and the pr>cedure used did not recuire ir specify the re=ovel of the relays.

The ins tru=en: cain-tenance personnel were counseled regarding the res:cra:icn - cf equipment and the use of adequate procedures.

The generic =aintenance procedure (1430-RMS-4, Rev. O, Troubleshco: The Alar: Circuit, Repair and Retest) requires a functional test of the alarm circuit before and af ter :he perf ernance of work and this precedure is to be used for future work in-i volving the alar: circuit.

The inspec:or noted that a purge of the Reac:cr Building was in progress at the time of discovery (raquired by S? 1303-4.15) and was prc=ptly terzinated by clesure cf the purge axhaust valves. Release records shewed, as was the case for the three purges repcr:ed, that no TS release li=its were violated.

-, ,a/*,i and :n ,c.-3c..,., :we inspec:cr ( v, ) ..,:.n respect to,cn / fm . ee-a.

a_ has no fur:her questions relative to the ecunseling of cperations personnel.

The licensee is evaluating changes :c current requ're:ents which will previde sufficient opera:icnal flexibility while ccepl"ing with requirements, and :his ite: (76-24-5) is unr es olved.

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-- .,. s - -13- -- / _ (9) With respect to ER 76-30/3L, which describes the GE 600 volt breaker which failed to trip on a reactor protection --- syste= test signal. This breaker is located in the D.C.

- Trip 3reaker Cabinet position C32, of the Control Puilding ~ ~ ~ Uni #1, elevation 338. While rerfor=ing routine sur- . veillance testing on Reactor Protection Sys te= (R?S) Channel C, Control Rod Drive (CRD) 3reaker failed to trip.

This surveillance testitg was in accordance with procedure , ' 1303-4.1.

The cause of failure of the breaker was due to dirt or hardened grease binding the operating link 2ge of :he breaker. Maintenance was perfor=ed on the breaker and satisfactory operation was achieved af ter cleaning and lubricating the linkage as recon = ended in the GE =aintenance instructions for this breaker.

The inspector reviewed the GIl-50299A Maintenance Instructions and the licensee Preventive Maintenance Procedure E-36, dated May 5,19 75 titled CRD Trip 3reaker Check.

The require =ents of paragraph 6.6 which require lubrication references the rype cf lubricatipn as specificd in the GE =aintenance instructien. The licensee stated tha: this precedure E-36 will be changed :o specify the type of lubrica:ica recuired and the a=ount.

I: vas also s tated by the licensee : hat a training progr1= will be established on :he GE breaker for the =aintenance personnel.

This ite=, 76-24-6, is considered to be unresolved pending the review by an NRC inspector of the procedure change and

he planned training progra=.

(10) With respect to IR 76-31/3L and ER 76-33/3L, a plan: design change (C/M #632) has been approved to install a c=perature - cc=pensation circuit f or :he trans=1::ers ** ' '-4 e drif t frc= te=perature changes. This =odification is to be done by the equip =en: vendor, and it is a design f ea ure currently available frc= the vendor.

l=ple=entation of this design change re=ains to be cenpleted, and this ite= (7 6-24-7) is unresolved.

The prcposed TS Change (#55) was in the review /appreval chain, and it had received PORC review and GCR3's review was pending. The inspector infor=ed the licensee that this proposed change did not appear to adequately address the inclusion of the 30 psi instru=ent error assu=ed in the YYOU , .. ~....... ~.., ' _ '....._ .. ,,....,,.... ..... ,,,, _,b ^ ~ '. '. . . .. ..... _ _._.

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The inspector stated : hat the STS being developed for TMI-2 provided an acceptable =ethod in Table 2.2-1 to account for instru=ent drif t, i.e., - ' values are specified for the Trip Se point and the Allowable - values. The licensee ack=owledged the inspector's com-g- =ents and stated that these would be evaluated. The ' inspector noted that this change, which includes an increase in the current High Reactor Coolant ?ressure Trip Setpoint, - --- s is also part of the licensee's long ter= corrective action - f or A0 75-15.

Sub=1ttal of the proposed TS Change to NRR and NRR approval re=ain to be cc=pleted, and this ite: . (7 6-24-8) is unresolved.

. The cause of the pressure trans=1::er (RPS Cha:" 3) bting . out of calibration could not be de ter=ined by . - personnel and the trans=1::er was returned to the vendor ior :esting.

The cause of the occurrence re=ains to be deter =ined and ' . evaluated by the licensee and this ite= (76-24-9) is unresolved.

(11) GOR 3 review of the Reportable Occurrences delineated in paragraph b above had been acco=plished with the exception o f ER 76-16 / 3 L, ER 76-26 / 3 L, ER 7 6-30 / 3L a nd ER 76-31/ 3L, and this iten (76-24-10) is unresolved.

Housekee in: During the visual inspection of the relays described in ER 76-5/1!, ER 76-16/3L and 76-30/3L the inspector found the tops of the cabinets housing these relays to be dirty.

The dir found on top of the cabine:s and also inside the Control Rod Drive 3reaker Cabine: appear to have possibly contributed ;c :he failures as described in :he referenced ERs.

The conditions found above the elec:rical cabinet tops and inside of :he Control Rod Drive 3:eaker Cabinet is in nonce =pliance with Regulatory Guide 1.39, March 16, 1973 and ANSI 45.2.3, 1973.

This it e: was identified with a lack of housekeeping procedures and is noted in the licensee's QA Nonco=pliance Report No. 7 6-19 2, Augu s t 12, 1976.

This ite=, 76-24-11, is considered to be unresolved pending a review by the NRC inspector of the housekeeping procedure and its i=ple=entation.

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Previous 1v Identified Unresolved /Other Ite=s f k a.

A0 'i5-15 - Further Investication/Long Ters Action Reference: NRC:I Inspection Repor: 50-289/75-14, Detail 10.d(l) - The Shif t Foreman's log shcwed that surveillance under WR 8628 ' was initiated od June 3, 1975 and that the out of tolerance set-point was identified on June 5,1975; therefore, the June 3, - 1975 date on page 36 of WR 8628 was in error.

This explained the previously identified discrepancy, and this item'is resolved.

The TS change (proposed change J55) had received PCRC review - and was avai:ing GOR 3 review.

This ite: is resolved.

The - sub=1ttal of :he proposed TS change to NRR will receive additional inspection follevup (refer te Detail 3.c(10) of this repert). b.

A0 75-16 - Turther Investication Reference: NRC:I Inspecticn Reper: 30-289/75-14, Detail 10.d(2) The PCRC (Meeting 4320 conducted on February 2-6, 1976) evaluated the cause of the voltreter being cut of calibratien, and it was de:ertined :ha: cc:penents withir :he instru=ent had failed cue to corral use sc e tire falicwing its last calibra: ice by their vendor. This evaluation, which included a reper: frc: the licensee's vendor, discicsed tha: the instru=ent railure was not attributed to any practices i=ple=ented a t the site.

This ita= is resolved.

c.

Procurement Scecificatiens Access Stata-a - Reference: NRC:I Inspecticn Rercr: 30-239/75-14, Detail 9.b The ins ector's review of procurement dccuments during this inspecticn (refer to Detail 10.c of thd-repcri) revealed : hat a statement regarding the licensee's right of access to surplier's facilities and records for visits and audits had been p? iced cr.

all procure:ent docu=ents involving cuality assured i:ees.

The inspector has no further cuestions en this ites.

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Aux 111arv Querators Loe Sheet Infor=ation - Reference: NRC:I Inspection Repor: 50-289/75-14, Detail 3.f, [ 3.g and 3.h ct . The licensee has been revising :he Auxiliary Operators Log .. Sheets to provide =ax1=u=, =ini=u= or expected values and % , , identifica:ica of e9ui =ent in co. eration based on co. eratienal .J . exterience. The current version of the Auxiliary Coerators Log Sk.eets - Out - Building Tour, Pri=ary Auxiliary Operators Leg - Tour Readings, Primary Auxiliary Op arators Log - LWDS Panels, - and Secondary Auxiliary Operators Log Sheets were reviewed during this inspectica to access the licensee's progress on upgrading . these leg sheets.

.

The inspector has no further questions en this ite=. . e.

CTSS Review of Facility Procedure Chances Reference: NRC:I Inspection Recerts 50-289/76-01, Detail 13.b(8); 50-289/76-09, Detail 17; 50-289/76-10, Detail 13.a; 50-289/76-12, Detail ll.g; 50-239/7e-1.5, Detail 27.g; and 50-289/76-17, De tail 10.a Based on review of re:::anda frc= the Manager, Generatica Ingineering Oc the Uni: 1 Superintendent concerning procedure changes (PCR's) =ade during the period of Nove=ber 1 :hrough Dece=ber 31, 1975 and January 1 through Februar7 29, 1976, the inspector deter =ined that CTSS (Cer: orate Technical Sucport Staff) review had been ec=ple:ed en FCR's 75-409, 75-410, 75-433, 75-435, 75-457, 75-468, 75-472, 75-480, 75-492, 75-493, 75-496, 75-524, 75-538, 75-543, 76-065, 76-098, 76-104, 76-105 and 76-129 Additionally, ?CR 76-Olb was cancelled, and 1:s cen:ent.. had been included in PCR 76-098.

Tais cc pleted all er"i; u CTSS action en procedure changes =ade during the afore=entioned periods.

This ite: is resolved, f.

S? 1302-5.4 RC Flux Flcw Calibration Reference: NRC :I Inspectic: Reper: 50-289/76-09, De: ail 23 The inspector's review cf the current version of S? 1302-5.4 (Rev. 2 dated Septe=ber 2,1976) revealed tha: the procedure W0001 -- ...... ................ ...... L.

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. This item is.esolved.

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TS 3.3.1.1.a, SWST Manual Discharce valve

' ... . t-Reference: MRC :I Inspection Report 50-289/76-09, Detail 25 The licensee sub=1tted a proposed TS Change to NRR 00 delete the recuirement for locking open the 3WST =anual discharge valve (no valve installed), and this change was accreved bv NRR (Licensee A=endnen: No. 21 dated Sertember 15, 1976).

This ite: is resolved h.

Revision of S? 1303-11.10 . Reference: NRC:I Inspec:icn Recer: 50-2S9/76-10, Detail 3.b(3) (a) The inspect:r's review of the current versica of S? 1303-11.10 (Rev. 4) revealed tha: the procedure had been revised by ?CR 76-352 :c include those precedure changes previcusif proculgated by TCN's 7 6-49 and 76-50.

Addi:icnally, the inspector deter-tined tha: FCR 76-352 had been reviewed by the CTSS pursuan to TS 6. 5. 2. A. 2.a (Memorandct fre Manager, Generatier Engi-neering to :he Uni: 1 Superintendent). This ite: is resolved.

i.

preventive Maintenance Precedures for Centrol Eccc Ccnsele Meters Reference: NRC :I Inspection Report 5 0-259/7 6-10, De: ail 3.b(4) (b) The inspec:cr deter =ined that preventive saintenance precedures to cover calibration of the Diesel Genera:or Synchronizing Volt- =eters and KW =eters (E-39, Rev. O, dated Augus: 6, 1976 and E-40, Rev. O, dated August 13, 1976, respectivelv) had been approved. Additionally, the preventive maintenance schedule recuires the perfor:ance of these procedures at a k'a-dal frec.uency er scener.

This ite= is resolved.

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Seismic Oualification'of Steam Generater Level and Pressure Indications ..... Reference: NRC:I Inspection Report 50-289/76-10, Detail 6 and Licensae Event Recorts (76-11) dated February 27, . March 27, April 9 and May 7, 1976 . Th2 inspec c: cbserved that the licensee's actions had been cr:pleted as stated in the May 7,1976 letter. Tie down of the a>plicable cable trays was ce=pleted by WR 15115 en May 12,1976.

/nchoring of the NIS/ICS cabine: was ceepleted by WR 15216 (i=ple=ented C/.M 711) en May 17, 1976. ?recedural coverage for use of a digital volrneter Oc obtain stea generatcr level and/or pressure indi'caticns should these re ers f ail was provided by Rev. 3 to I? 1202-30 (Appendix 1), Ear:hquake procedure dated - June 3, 1976.

As a long ter= =easure, the licensee intends Oc =ake a design change to ensure stea= generator level indication is i= ediately available following a seis=ic event without need cf :he coerator action specified in I? 1202-30 as previcusly described abcve.

This ite: is being tracked by Generatica Engineering.

This iten is resolved.

. <. Check Off iists Ref er ence : NRC:I Inspecticn Repet. 50-289/75-11, Detail 17.a The licensee's methed for documenting cc ple:icn cf recedural requirements has been changed to recuire signcf f cf the individual . steps within the precedure instead of the use cf serarate encies-ures. ?CR's to all cperating precedures have beec wri::en c accceplish this change, and abou: 60~ of these precedures had been revised to include these new signoff require =ents by the individual s eps.

This 1:en is resolved.

1.

Maintenance of Reactivity ? lots Ref er ence : NRC:I Inspection Repor 50-239/76-15, Detail 17.a The inspector's review of the current versien of C? 1102-2 (Rev. 13 dated September 17, 1976) revealed tha: the procedure 790003 - -.. . .. - - - .-. ' * ' " se-.se.. -

. . , , ( , ' n.. . -. - -19-now includes a require =ent to attach the reactivity plots ' cbtained in Step 33 (Ite: 10) to the ccepleted procedure.

-- This item is resolved.

[.. m.

Ecid Ti=es -. . r, : .' Reference: NRC:I Inspec:1cn Repor: 50-289/76-15, Detail 17.b F The inspector's review of the current version of 0? 1102-2 (Rev. 18 da:ed Septenber 17, 1976) revealed :ha: the procedure no longer references Figure 9 and holding cites (applicable enly for the previcus fuel cycle). This i:e is resolved.

n.

preven-Maintenance - Lubrica:icn Refere_ce: NRC:I Inspectica Reper: 50-289/76-15, Detail 23.b AP 1015 is currently being revised, and it will cover lubrication via the preventive maintenance prograr.

Additionally, a "leco closing" f eature is being added to the pr gra by inputing the lubrication schedule into the cc puter as lubrica:icn is scheduled via the existing card syste. A: cresent, about 70~ of the lubrica:icn progra: has been inputed to the ec puter, and this included all weekly and conthly iters, two-thirds of the quarterly it ers, and those s e 1-annual and annual i:e=s scheduled during the previous tuc cenths.

Based en the licensee's curren: scheduling techni:ue, :he re=ainder of the lubricatica program will be inputed to the ec puter over the nex: ten centh period. The status of the lubrication pr gram as well as other parts cf the preventive main enance progra: is readily available f ce the cceputer en a Departmen: basis (?M Results Record). This 1:e is resolved.

6.

Ouality Assurance Audits The inspector reviewed records relating to Quality Assurance audits conducted frc: June 1975 through June 1976. These audits were reviewed with respect :o 10 CFR 50, Appendix 3, Criteria II, V, XVI, T7 I and and :he.,.,causee,s procedure v,.-40,o,. _.&nese auc :s ere not c . .. r,.... tat . reviewed with respect to the recuirenents of A.NS N45.2.12 since the li cens ee 's c r-d tnent to this Standard specifies i=plementatien con-current with starting the Cperational Quality Assurance Pregra: en V ua w .n. ns.

<.ge.

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Audits Reviewed The audits listed below were reviewed to verify tha; they were conducted as follows: in accordance with written / approved pro-cedures and checklists; by trained / certified personnel not having.

- - direct responsibilities in the area (a) audited; with audit results p docu=ented and reviewed by =anage=ent responsible for the area (s)

audited and by Corporate =anage=ent as/if appropriate; with [. appropriate, cinely corrective actions taken, beirg :aken, or @ ' sche.duled; and, in conformance with established schedules.

[- Avdit Area Audited Conducted 75213 Docu=ent Control 06/23/75 07/25/75 r 75-14 10 CTR 19 06/19/75 [

75-15 Cc=pliance vi:h Environ = ental /14/75 - 11/2:/75 Recuirenents 75-16 Inspection of Cranes 06/18/75 - 06/24/75 75-17 Significant Operating Experiences 07/03/75 75-18 Tes: Equip =ent - TMI Uni: 1 06/24/75 - 06/3J/75 75-19 TMI-l Securi:7 06/06/75 75-20 Use of Perscenel Moni:cring Devices 06/29/75 - 07/21/75 75-21 GP-1024 07/18/75 - 07/22/75 75-22 GP-3002 07/22/75 775-22 Opera:c: Deterninstion cf Sore 07/15/75 Ccncentraticn 75-24 GP-0013 08/14/75 75-25 IR 75-01 08/2S/75 - 09/05/75 75-26 Titus Ash Dispcsal Facility 08/26/75 75-27 General Office Review Board 09/2S/75 75-2S Safe:y Reviews 09/30/75 75-29 Special Processes 09/15/75 - 09/26/75 75-30 GP-0002 11/14/75 75-31 G?-0C07 12/02/75 75-32 Radia:ica Meni:oring 10/29/75 75-33 Modifica:ica Centrol 12/10/75 - 01/09/76 75-34 Technical Specification Surveillance 12/29/75 - 01/21/76 Progra: 75-35 GP-1015 01/11/76 - 01/15/76 75-36 vendor Audi: 01/07/76 76-01 Enviren=en:a1 Monitoring 02/09/76 76-02 Special Nuclear Material 06/02/76 - 06/03/76 76-03 Technical Specification Surveillance 05/13/76 Progran 76-04 GP-3303 05/16/76 - 05/25/76 76-05 Con:rol of Engineering Records 05/25/76 - 05/2S/76 76-06 Abnor=al ?recedures 05/29/76 76-07 Docu=en: Centrol 05/06/76 - 06/13/76 76-08 Refueling Physics Testing 06/16/76 76-09 Station Preventive Maintenance 06/14/76 - 06/21/76 ^ Y$300(55 __.

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--., * . - . _21_ 7.. --.. _ - ~~~ - - r:: : .... .: - . The inspector was shown a prin: cut from a tracking system used to =onitor the status of outstanding audit report items.

- .-.2_ .. The inspector's review indicated that one finding, 76-09-5, had been deleted frem the listing due to a secretarial error. The - licenseu stated that the closecut of the finding would not have k.; been impaired since a separate, redundant system fer ite= tracking '. '. (utilizing the audit report and the lead auditor) veuld have - - - ' detected the lack of preper closecut.

. . . Three unresolved ite=s were iden:1fied as docu=ented in Details 6.b, 6.c, and 6.d below.

b.

Extensicns 6f Corrective Action Cecoletion Dates Audi: 74-7 was conducted on March 19, 1974. Finding 74-7-2 identified a lack of a procedure distribution chart wnich was required by Paragraph 3.3.1 of procedure 1001, a corrective action ce=pletion date of May 31, 1974 was es tablished. This due date was changed by 3 extensions and was finallf c1csed en October 9, 1975 with the state =ent tha: the ite= vas " identical with ite: 75-13-3."

I:e= 75-1:-3 was given corrective action ec=pletion date of August 22, 1975. This date was subsecuen:ly extende2 5 "es and the itec was closed en June , 1976 (see also Detail 6.c below). The actual p ccedure revision :aking the required change was issued on September 9, 1976, 2b re=-e af:er the finding was ini:ially identif;ed.

All of these extensions were gran:ed in accordance wi:5 the licensee's precedure G?-4015.

The inspec:or s tated tha: :his gra. ting of repeated extensicas did not satisfy the timeliness ' aspect of 10 CyR 50, Appendix 3, Criterion :G'. Ecwever, the inspec:cr's review indicated that the noted exa ple appeared : be an isolated case.?ving mirical safety significance.

In addition, the licensee na d that such extensions were not routinely granted and that precedure changes veuld be initiated and ce=pleted by January 3,1977 to procedurally preclude such extensions in the future.

Pending ccepletion of the litensee's procedure...anges, this item (76-24-12) is unresolved.

- c.

Corrective Action Closece: Verification As referenced in De: ail 6.b above, ite: 75-13-3 was closed out on June 4, 1974 and the procedure taking the change was not issued v. w\\ J 0. ['., f} p v..- $ s ') - Nw6& . N -eam ww .m.

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. -._ . until September 9,1976. The inspector noted tha: tha licensee' r auditor had closed the finding when the PORC had placed the procedure revision on their agenda for review.

The licensee had subseque'tly, in answer to another audit finding, .. stated to the audited group that closecut of procedure revision -- items could only be acce=plished af ter the procedure had been issued. Again, the closecut.of the ite= noted above was the s only exa=ple found during the inspector's review and appeared ._, to be an isolated case. The inspector interviewed 6 auditors and all stated that closecut of audit findings recuiring pro-cedure revisions could only be done af ter :he procedure had been approved and issued. The licensee's current crocedures de not include any guilance to auditors on when such ite=s =ay be closed-out.

The licensee stated that procedure revisiens would be =ade by January 3, 1977 to give acceptance criteria for correc:ive action closecut verification.

. Pending co=pletion of the licencee's procedure changes, this ita= (76-24-13) is unresolved.

d.

Audit Raccr: Distribution . Procedure G?-4407, Paragraph I.4, recuires that a ccpy of cc=- pleted audit reports be forwarded to Three Mile Island Quality Centrol af ter. :he original has been signed by the Manager of Operational Quality Assurance. The inspector reviewed 33 audit reports, one (73-32) was not available at the Three Mile Island Quality Control file. This repor: was reviewed at the licensee's corporate of fices in R?ading, Pennsylvania and a ecpy was = ailed to the site prior to cc pletien of the inspec: ion.

' Pending verifica:icn that a copy of audi: reper: 7 5-3 2 is avail-able a: the site Quality Control files, this ite= (76-20-14) is unresolved.

7.

Quality Assurance Pro 2rs: Chances Changes =ade to the licensee's Quality Assurance Progra i=plenenting procedures since the previous Quality Assurance inspectica (July 1973) were reviewed on a sanpling basis to verify confor:ance with: the accepted Quality Assurance Plan (FSAR Appendix 1. A); 10 CIN 30, Appendix 3 criteria; and, ANSI Standards and Regulatory Guides endorsed by the licensee's co==itments.

The results of :he review are se=:ariced below.

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Procedures Reviewed - ' Nu=ber - Title Revision / Dated J . , . . GP-4003 Ouality Assurance Personnel Training

05/12/76

=

F-GP-4005 Review of Procure =ent Docu=ents

08/13/75

GP-4008 Re< :1p: Inspection of Material and . Equipmen:

12/08/75 ' GP-4010 Approved vendors List

02/17/76 GP-4012 Surveillance Progra=, Nenconfor=ance ~ Reports, and Stop 57 ark Orders

10/30/75 GP-4015 Audit Finding Closecut Progra:

05/10/76 . G?-4016 00A Audit ?r gram .

04/27/76 . GP-4403 Three Mile Island Ouality Centrol ' Sucule= ental Ins tructions

02/19/76 G?-4404 Receir: Insrection of Repairs and Returned i; sed and Unused Ecuincen

05/06/76 GP-4406 Instructicas for Processing an NDE cr In-Service Inspectien Recues:

05/08/75 GP-4407 Regulatory Retentien and S:crage of CC Department Records

10/17/75 GP-4409 Acceotance of Nuclear Saf.e:v-Related - Ecuip=ent for Installation Only

10/22/75 The inspector identified one unresolvec ite with rasrect c the stated review cri:eria.

Tais ite is documented in De: ail 7.b belev.

b.

GP-4407 Frecedure GP-4407 ccvers the s:Orage cf CC raccrds.

This pro-cedure does not describe the f acilities used for d"9 '" e record storage, where such records are to be s:cred, ner the recuire=en: to forward duplicate ccpies to the additica s:crage facili:1es.

The recuirements were, in all cases reviewed by the inspector, being met and the records cus cdian had been or lly inic red of each ef the above recuirenents. Ecuever, Paragraph 5.3 cf A'ISI N45.2.9 requires these ele =ents to be detailed in a precedure.

'.hese ele =en s wculd be included in the H e licensee stated that a procedure by.!anua 3, 1977.

Pending ccepleticn cf the rocedure revisiens, this ite (76-24-15) is unresolved.

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Modifications and Desien Control The inspec:or selected and reviewed completed denign changes /=odifi-cations listed be* ew to verify: accceplish=ent in accordance with 10 Ca 50.39 and he licensee's p ccedures ; inclusica of code recuire-p =ents ; inclusion of acceptance tests and related acceptance values ; records of equipment perfor:ance were included, reviewed and accepted; revisiens were made, where necessarv, to procedures, drawings and/or ' prints ; and, cc=pleted changes are reviewed by plant personnel during subsequent training sessiens.

a.

Modifica:icas Reviewed Modification Title /0escriotien 'a~ork Recues : 4 624 Install Fan en Fuel Handling Bridge Hois: 13365, 13570 637 Installation of Spare Nuclear Instru=entatien De:ec:cr 13527 646 Control Rod Drive Feuer ?atch Panel Mcdifica:ica 13679 525 Replacing RC-V-a Mot : 11078 700

_=ergency Diesel General Relay Panel 1;662 673 Install Lini:er Plate :c Lini:

Tercue 14200 ..- ' 'Ji:h respect to the sta:ed :: view criteria, one unresolved iter ~ was iden:ified as docu :a:ed in Detail 3.b belcw.

b.

Notification of Trainin; Decar: rent

Cc= le:ed cdifica:icas were rou:ed, when requirec, :c the Training Depar: rent.

ine c. :rk responsible f or :he routing was notified of the requirenent by means of c s tare which was placed en the front page of the ccerle:ed =cdification cackage.

Neither the criteria used :: de:ernine when ccepleted packages were required te be rcuted to the Training Depart =ent, the respc - - sibility for making the deter =ination, ner the use of the "sta= " - were described in docunen:cd instructions, procedures or policies.

- The licensee ' stated that the current practices wculd be accrc- . - ; _ _- priately decu=ented prior c January 3,- 1977.

. - . -Un:12 the current ~ practices -have been docu=ented, this ite - ._ ,_ (76-24-16) is un. resolved.

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ANSI N45.2.6 Certificates ~ The licensee's forms used to docu=ent certifica:1cn of QC personnel performing inspectf n, exa=ination and testing functions do no: . identify the c=pir er, the level of capability ner the effective - period of certification; these three ite=s are specifically recuired to be on each certificate by Paragraph 2.2.4 of ANSI N45.2.6.

s - , v: L.: - In a memorandu= dated Septenber 2,1976, the licensee had documented - this proble=. During discussicus between the inspector and the Supervisor cf Quality Con:rcl, the Superviser s tated tha 1: was his epinion that -he conditien warranted the fornal docu=entatica and control of a nonconfor:ance rescr: (NCR).

Subsecuently NCR TMI-76-439 was issued and a date cf January 3,1977 was established for ce= leticu of the corrective action.

Until the corrective acticas for NCR TMI-76-439 have been ec ple:ed~ and verified, this ite: (7 6-2 t-17) is unresolved.

_ Since the licensee's accepted Quality Assurance Plan (?SAR Appendi:: 1.A), Section 7, states in part: "Me:-Id vn11 cceply with...Regula: cry Guides.. 1. 58 (August 19 7 3)...." ; this failure to cecoly with a re-quirenent of Regula: cry Guide 1.52 (which endorses ANSI N45.2.6) is a licensee iden:ified 4 a- ^# noncc=pliance.

Since onif the docunen-tation and no the :: ining er other recuire=ents for car:ification were lacking, a Deficiency level severity is assigned.

10.

-?--- -= ent The inspecter reviewed :he precurement centrol phase of the licensee's pregra: with respect Oc the recuire ents of 10 CyR 50, Ap:endix 3, Cri:eria IV and VII, the TM: Cperaticnal Quality Assurance Plan, Rev. 6 and associa:ed impleten:ing precedures.

a.

Personnel Rey personnel responsible for the initiation, review, and approval of procure =ent documents were interviewed and indicated that they were knowledgeable of the cen:en:s of the applicable crecedures and understand their individual responsibilities.

b.

Procure =ent Decurents Selected The follcwing purchase crders were randenly selected as sc ples for the review described below: i > - h - . ... .... - t

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~ V. : ,p (1) P.O. 23585 - Fittings (2) P.O. 23125 - Hex Nuts ... _. (3) P.O.

24616 - Loop Seal Parts (4) P.O. 22499 - Parts for Control Rod Drive Mechanism (5) P.O.

24250 - Welding Red g (6) P.O. 24746 - Parts for 12" Gate Valve c.

Soecifications The procurenent specifications used in the purchase of the items in Detail b above were reviewed to verify that the fellowing requirements were included: proper approval; cuality control " inspection recuirenents ; cuality record require =ents ; and a s tate-ment establishing the licensee's right of access :c surplier's facilities crd records of visits and audits.

The inspector identified no discrepancies.

d.

Noncot forcinz Itens Feur no ecnforcing spara parts were selected fer review as described below: (1) P.O.

43939 (NCR 76-221) CED Srares (2) P.O.

43662 (NCR 76-324) Relief Valre Spares (3) P.O. IS991 (NCR 76-343) Way Scienoid valve a (4) P.O. 22005 (NCR 76-349) Gasket v.a:erial The inspec:cr reviewed these itens and deternined that: parts were inspected upon delltery, parts were properly handled n accordance with neasures established for con:rol anc separa::cn or noncon-forcing parts; and, parts were supelied by an a:preved render.

The inspec:or identified no discrepancies.

e.

Receirine Instecticn A rev1,7 of receiving inspection records verified the follewing: (1) supplier records, as required by the purchase docunents, are a railable and cceplete; (2) receipt inspecticns are conpl,ted and signed-off in accord- . ance with procedures; i 3 0 0.1..t . . o gM6e e hue he e e MMW.

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-2 - - C-' . ('. . - - t (3) items can be traced to procurement docu=ents and inspection records; and, (4) items released to storage or use are identified as to 'their ~~ a:ceptance status.

l= The inspector identified no discrepancies.

f ~~ ~ 11.

Records On a sa=pling basis the inspector reviewed the liceusee's pregra= - for the control, storage, retention and retricval of records and docu=ents with respect Oc the recuirements of 10 CFR 50, Appendix 5, Criteria V and XVII, the TMI Opera:1cnal Quality Assurance Pli.n, Rev. 6, and associated imple=enting crecedures.

_ d.

Retrievability Specific. records, selected by the inspec:0r, were recuested to - deter =ine the licensee's capability te centrol, s cre and retrieve records.

The records selected, all in :he for of eperating procedures and associated changes, are lis ted belcw.

(1) Reacecr Coolan: Svster . Procedure 1103-6 " Reactor C0 clan: Pu=p Opera:icn" (2) Reactivity and ?cuer Centrol Precedure 1103-4 "Scluble ?cisen Concen::stien Centrol" (3) Core and Internals Procedure 1104-1 " Core Flced.ing Sys tem" (4) ?cwer Conversien Svstc= Procedure 1106-9 "Turb ne Lube Oil ?ung Sys tem" (5) Auxiliarv Svsteu Procedure 1106-4 "Auniliarv 3c ilers" WOO.1.2 . - * = - - . h ! ... _ _ _ _ m.

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-. t t.. - (6) Electrical Svstem . Procedere 1107-1 "Nor=al thutrical Sys ten" ,:; (7) E=erzenev Paver Procedure 1107-2 " Emergency Electrical System" (8) Emerzenev Core Coeline Svstem ? ocedu e 1.'12-11 "?lan: C oolacwn" _ (9) Saferv Svste= ? ccedure 1303-11.21 " Core Flceding" In each case, the record requested by the inspec:or was cade available by the licensee.

S.e inspecter identified no discrepancies.

b.

Entineerinz Drawing Centrol Twenty safety-related drawings and their lates t revision nu=ber, randc=ly selected frc= the NI Drawing Inde2, ('.is t of GAI Drawings Issued frc= 1/1/50 :o 7/1/76 - run 7/2/76) were checked against correspending centrolled prin:s =aintained in the 21I Administrative Office and against cor esponding =icrofil= cperative cards =aintained a: Corpora:e Engineering.

The resul:s of the review are st==.ariced below.

7.I Index Ad=in Office Coro. Eng.

Dravin: No.

Rev Nc.

Rev Mo.

Rev. Nc.

(1) 302-011

18 IS (2) 302-051

21

(3) 302-101

16

(4) 302-131

16

(5) 302-690

16

(6) 201-341

13

(7) 208-204

4 !. (8) 'OV-'"m.

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2

(10) 220-054

13

(11) 304-012

13

(12) 304-131

6

(13) 304-72S

3

r (14) 305-020

5

(15) 308-368

0

(16) 308-575

Missing

' (17) 308-866

Missing

(18) 319-103

2

(19) 319-011

2

(20) 313-001

1

- Prior to the ccepletien of the inspection, copies of the two missing drawings were =ade f ree the Aininis trative Of fice aperature card file and placed in the print file.

Also, an additional ten drawings were selectec frc= the TMI Drawing Index and ce= pared agains the corresponding drawings in the idei _.s tra tive Of fice. This additicnal review :::duced full agree =ent between the TMI Drawing Index and the Ad=inis trative Office drawings.

The inspector had no further cuestions in the Engineering ' Drawing area.

c.

50.59 Saferv Evaluatien Records The inspector verified that receria of changes in cpera:ing procedures are maintained to reflect changes in the f acility and include a written saf ety evalaation which provides the basis for the deter =inatien that the change does not invcive an unreviewed safety cuestice as described in 10 CFR 50.59(b). This finding is based on a review of the procedures lis ted Nelow.

Procedure Title CP 1103-8 Approach to Criticalicy OP 1104-1 Core Flood Sys tem CP L103-15 Reactivity 3alance OP :.104-2 Makeup and Purifica:1cn OP 11G4-4 Decay Eeat Re=cval Syste= OP 1104-21 Penetration ?ressurizatien Sys te= The inspec:c identified no discrepancies . W0014 . - _.

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Review and Audits a.

On Site Review Cc==f ttee Meetings Technical Specification 6.5.1.4 requires that the PORC =eet E at the frequency of once/=onth. Meeting rinutes Nos. 341' to 352 fre: June 28 to Septe ber 17 were reviewed. The licensee =et the =eeting require =ent for this period.

- b.

On Site Review Cc==itt ee (? ORC) Ouorum Technical Specifica:ica 6. 5.1.4 and 6. 5.1. 5 specify the cuorum required for a PORC =eeting.

The above referenced meetings and Met-Ed' Superintendents Operating Me=o No. 6, Rev. 9, Augus., 1976, were reviewed. Member and alternates are designated.

The quoru: require =ent appears to have been met.

c.

Review cf Test and Ex eri=ents Af f ectinz Nuclear Safetv The PORC =inutes 341 through 352 were reviewed. There were no tests of experiments perferced aff ecting nuclear saf ety.

d.

Off Site Review Ccc=it:ee (GCR33 Ouoru: The General Of fice Review 3 card (GOR 3), Draf t Minutes of Meeting No. 24, Septe=ber 24, 1976 were reviewed. The =e ber-ship docu=entatica for the appcintment of alternates in acccrd-ance with TS 6. 5. 2.3. 3 was not availcble.

Technical Specifica:icn 6. 5. 2.3. 6 requires a =ajori:y of prencipals or duly acpcinted alter =ates.

The meeti.:g =inutes of Meeting No. 24 did not apoear to meet the TS requiraments.

This ite: (76-24-13) is censidered to be an Item of Noneccpliance of Deficiency level.

e.

Cn Site Review Cc==i: ee Restonsibilities The FORC =inutes for Meeting No. 241 through 352 were reviewed with respect to =ee:ing TS 6.5.1.6.c.1), 2) which address the review cf Technical Specification changes, repertable cccurrences and violations.

The inspector f ound no discrepancies.

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i.- . !- ... 13. Orzaniration and Ad=inisriation -- a.

Organiration Structure . .... if The organization structure is as described in the Technical I~.; _ Specifica:ica 6.2.1 and in the TMI FSAR Figure 12-1, A=end=ent - 2.

50, Rei. 1, February 18, 1976.

... b.

Mini =u Shift Crews, Schedule for Augus: through October 1976 for TMI Uni: I was reviewed. Also, discussions with the licensee on the =ethods used to assure TS covera'ge assuring =ini=u: shift crews was conducted.

It appears that the licensee raintains a crew require =ent nee:ing TS 6. 2. 2.a.

c.

On Site Review Cc==i::ee (?OkC) 'te:Sershi The inspector reviewed Superintendent's Opera ting Me=o No. 6, Rev. 8, PORC Uni: 1, August 3,1976 along with PORC =inutes (Ref erence De. tail 12 of this report). The FORC =e=bership was found to be as required by TS 6.5.1.2.

d.

Persornel cualift:2:icn Levels Tha q"n! * 'd-atice level f or :he personnel holding the f ollowing responsible pesi:icns were reviewed and f cund to ree: the sugges ted =ini=un education and. experience levels as sugges:ed in A"SI . i a. 3 _1 c, s,. .t

• Unit Sucerintenden Sucerviser of Opera:crs Nuclear Engineer Radiation ?rotec:icn Supervisor FORC Chair =an (Ingineer in charge)

S taf f Che=is : Shift Supervisers Lead Mechanical Engineer Lead Electrica.1 Ingineer Instru=entatice and Control Lead Engineer Electrical Maintenance Supervisor Instru=enta:ica and Control Supervisor Acceptability of cualification was based on resune e.v.trav s, Senior Reac:or Operator License docu=entatien, attach =en Oc the application for By-?reduct License Ite: 4 of For: AIC 313 and interviews vith the licensee persennel.

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. e.

Of f Site Review Cc==ittee Me=bershio .... Attach =ent A of GOR 3 Meeting No. 23, June 7, 1976 was reviewed.

Also, the inspector was provided with extracts of the me=bers resunes. The areas of expertise per AriI N13.7 are listed and . cross ref erenced to the per=anent =e=bers of the GOR 3.

The concerns of the inspector on alternate =e=bers is addressed in , Detail 12.d of this report.

' 14.

?uel Receio and Storaze. TMI Unit 2 a.

License Recuire=ents The inspector reviewed Specisi Nuclear Mater:al (SNM) License 1671, which authorizes receip t, possession, inspection and s:crage of nuclear fuel; Refaeling Procedure 2501-6.1, Rev. 1, 10/7/7 6, Receipt, Inspection, Fit-Up and Sterage of New Fuel and Centrol Cc=ponents; and the Final Safety Analysis Recort.

A subsequent inspection wat conducted with the f ollowing obse:vations.

(1) 5: craze Area . The inspecter : ured the Fuel Handling 3uiliing (?H3) and ccted the follcwing: (a) New fuel dry storage racks were covered with a poly covering to =aintain cleanliness.

(b} The presence of cc=bustible naterial was at a-d-4-"- and the cond-tion of cleanliness appeared adecua:e.

(c) Radiation nonitoring was in accordance with license r ec uir e=ents. (d) The licensee's energency p ccedure for building evacuation and re-entry was pes ted in the FE3.

(e) All personnel entering the FE3 were required to carry personnel =enitoring devices.

(f) Centrary to the licensee's SNM license, signs were not posted in the FE3 prohibiting the use cf fire hoses, fog, or foca fire fighting ecuipment within 'he building. This ite= (76-16-1) is a Deficiency level I:e= cf Nence=pliance. Af ter being inferned of :nis '!000$.) -. .... _ _ _ _. __ . +He-ie.,. ...

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R03DRIGM , . ' ~ .... '- situation, the licensee i==ediately po sted the required signs. No additional corrective or folicw-

z up action is. required by the licensee.

(2) Securitr Cont cis h c: The inspector reviewed Security Procedure 1005.17, Rev. O, 9/17/76, Unit Il Fuel Receipt, Handling and Storage, which ' defined the controlled areas and access control for Uni: II fuel receipt cperations.

The security controls and guard requirements specified rithin this procedure appeared to =ce: license require =ents.

On a sampling basis, security controls in the FE3 were verified to be in accordance with the procedure. The inspec:cr hac no further cues:1:ns in this area.

(3) Inscection and Handlin: ~he insuector witnessed the arrival, receipt and unleading of the first shipment of new fuel asse=blies.

In srection for damage, cleaning an?. radiation surveys of the shipping containers appeared to be in accordance with precedures.

Appropriate shipping docu ents and the necissary Nuclear Material Transfer Reperts (NRC-7al) accc:panied the ship =ent and were reviewed by the licensee.

The inspec :: verified tha: the firs: two asse=blies were procedurally re=cved frc: their shipping centainer. The licensee's inspection for any da= age or manufacturing deficiency was condue:ed visually and by radiation surveys using_the manufacturer's inspec:icn findings, which accc=- panied the shipping container, as a guide.

The licensee's SN'-! license requires that all inspecting ac:1vi:1es ccccerning the new fuel will be perfor:ed in accordance with written procedures which have been approved by the Unit Superintendent.

~he inspector noted that the procedure covering each new fuel evoluation did not include .~ . -. detailed inspection guidance; however, a de: ailed inspection

- ' - was actually being conlue:ed on each asse=bly prior :: being . -. - - inserted into the dry new fuel s torage racks. This.1:e= & (76-16-2) is unresolved pending the inclusien cf assembly . inspection criteria into the procedure.

Th'e~ licensee intends to conduct addi:icnal insoections on each new = - - . assembly prior to core loading. _ - . . - .% , ....

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s , 15.

Conective Action for a ?reviousiv Identified Enforce =en Ite: . Reference: NRC:I Inspection Reper: 50-287/76-15, NRC:I letters da:ed Augua: 9 and September 8,1976, and Met Ed letter dated Augus 30, 1976 The inspector reviewcd NCR 76-346, FORC nee:ing minutes No. 339 and No. 340, and =e=oranda fro = the Superrisor, Operations to the Shif t Supervisors, Shif t Fore =en, CRO's and A0's and held discussions with the Supervisor, Operat.uno and a Shift Supervisor.

Based on this review, the inspector determined :ha: the corrective action had been tc. ken as delineated 1 the ref arenced licensee letter.

Additionally, da:a sheets for S? 1301-1, Shif t and Daily Checks perforced foe the peried July 1-21, 1976, were reviewed during a previous inspection (NRC:I Inspec: ion Repor: 3 C-2 S9/7 6-19, Je: ail 4.a.

(1)) and no inadequacies were identified.

The inspector has no further cuestions en this ite=. .... ,, . . . _.

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