IR 05000029/1975003

IE Insp Rept 50-029/75-03 on 750225-27.Noncompliance Noted: Individual Control Rod Positions Found to Be Below Actual Positions

ML20031C379
Person / Time
Site:	Yankee Rowe
Issue date:	03/13/1975
From:	Davis A, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20031C367	List: IR 05000029/1975003 ML20031C366 ML20031C373
References
50-029-75-03, 50-29-75-3, NUDOCS 8110070099
Download: ML20031C379 (21)

Text

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(Jan 75) (1:ce)

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U.S. ZiUCLEAR !;EGUL\\'10:1Y CD::::ISSIO:;

0FFICC OF I :SPECTIO:: N;D E::FO: CE::E!!T REGIO!! I L4 IE Inspection Report !!o:

50-29/75-03 Docket ::o:

50-29

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Licensect Yankee Atomic Electric Co.pany License !!o: UFR-3 h

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20 Turnpike Road Priority:

$

Ties tborough, !!assachusetts 01581 Category:

C n.

Location:

Rowe, !!assachusetts 01367

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Safeguards I'd Croup:

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Type of Licensce:

PtiR, 600 SNt (ti)

y g.p i 5 Type of Inspection:

Routine, Unannounced

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,

February 25-27, 1975 f~f

.

Dates of Inspection:

-

I Dates cf Previous Inspectica:

February 12-14, 1975

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Reporting Inspector:

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T Date i

J. F. Streeter, Reactor Inspector s

Acconpanying Inspectors:

[,0 -<, e i * W M/7/7)

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A. B. Davis, Senior Reactor Inspector D4te

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Date

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Date s

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Other Accompanying Personnel:

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A. B. Davis, Senio r i.e.x t a r Inspec to r U$5.'

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P'iR Section. Leactor Operation ; 1:raach

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8110070099 750314'

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Enforce ent.i c t i e_n_

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Deviations v 4Ne g.

W Contrary t., Section 213 of the Final !!ar. trh sc. ary.7eport, the i1 Primar Pod Fosition Indicatien cas found to nat be accuratc. zithin l{ ' ^y [

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13 inches.

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1-Licensee Actica en Previau;1 I&nti f f edjn f e re.~cnt r e c - _,

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Ite-= of !:ener--liance. II:I 7ns.setinn Pem rt 50-29/7bi6,

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2. t Details 1 3. S. ( ' '+, 13.a.(31

!3.3.f3), 1. *.,. <, ), and 16.5.(3)-

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The licen-ce's ccrrecti/o acticas eith res ect to these ite-s rere revieecd b. th e in s e c t a r an.! f m...4 c c-- I e r e.

C r ta f ic, 13, 2 '., 23 )

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crt, J-2 / ' 4 '.,.' t. s i l - 13.h.f6)

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i The licensee's corre tive acti:n; cith respect to these ita.2 ':cra revie.ted b:. the ins cetor and f:und ta be in,re;,rt_ss and not ;tet

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complete.

(?at1Lis 23 and 27)

Des 1 n Chan;ei

one IdentificJ

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Unustn1 Occurrc:ves

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!!cne Identified

Other Si nifi-r:

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A.

Currant i*

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Ac

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:ere ident fic! hrin:; u., rect i m )f ti.c full: :ing areas:

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-2-a.

Abnormal Occurrences (Detail 4)

b.

Ficodin; Ef fects of Failure of !!an-Safety Relatc<! Equip.ent.

(Detail 15)

c.

Administration 2.

ew Unresolved Ito

.4 The following iten vill require additional infor ation from the licensee in order to evaluate acceptability:

Norna11:ation of Calculated Baron Concentration uith :'casured

Values.

(Detail 2.b.)

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Infractions and Deficiencies Ileitified M Licenece

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x M-The following Deficiencies vera identified by the licensee and y

corrective action tras conpleted or initiated in a tinely nanner.

y y.-

Procedure for Controlling "akeup to Eoric Acid Tank (Detail 2.e.)

[

a.

.

b.

Safety Injection Actuation Signal Surveillance (Detail 16)

l~l 7r B.

Statua cf revi.ms Unre.mivad Itend

.,,

1. ~ The following itens have been resolved:

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,

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a.

Special Ordars. (Detail 3.b. (3))

b.

Cont:01 Rod Surveilla.;e Pro:ra.

(Detail 6)

c.

Control '.ed Bankin; (Datail 7)

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d.

Increase in Core and Loop iTs.

(Detail 8)

e.

Perfor ance Dischnr:e Testa of Station Eatteries. (Detail 10)

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f.

Availnility of Dat tcry Char;ar. (Detail 11)

g.

Control Ecd North Discrepancies. (Detail 13)

.

h.

Operatin; ' enos. (Detail 14)

[

' '

i. Use of the Tern " /A".

(Detail 17)

j.

Energency Power Under Voltac,e :: clays (Detail 21)

k.

Control of Revisions to Plant Drr.:In:;s and Procedures (Datail 26)

,

1.

Recalibration of Safety Classified Systen Insert.nantation.

(Detail 2S)

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The folloeina itens renain unresolved:

a.

llanger adj us tnents.

(Detail 3.d.(',))

b.

Revisica of In-Plant A u.li t Precedure. (i u all 5)

c.

Inspectica of CCCS Circuit Bren.ers. (Detail 20)

d.

Procurenant Centrol.

(Detail 22)

e.

Correlatien Data -. Flo.e vs.

'!C Current.

(Detail 19)

f.

Polar Crane Control Circuit Pallure. (Detail 12)

?fanace at Interviee s

A managenent intervicts tas held at the site on February 27, 1975:

'

-

Persons Present Wy 4,

ifr. H. A. Autio, Plant Superintendent dd tir. L. X. Bozek, Qualit:. Control and Audit Technici n W

M r. 11.

b'.

Eb e r t, Plant ?.eactor En;ineer W

!!r. L. H. Heida r,

2nat;c r of Ope rations b#

?!r. W. G. Jones Assistant. Plant Sup2rintendent

'

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!!r. N. N. S t. Laurent, Technical Assictant to tha :'lant Superintendent

.

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Iten; ?! <. u;% *

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Purpose of th: !n m etion s

The inspector stated that the purpose of the insp2ction 'eas to revie c; i

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(1) previous o-en and unresolved itens, (2) previous identified Itans i

of ::onconp11ance, (3) plant creratiens, ( '. ) aMernal occurrences, (5) safety i hits. limi t in.: safet" systen settin.u, and limiting conditions fo. 7?eration.

.

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Revie' of Ite-; of ?:ancon,liance g

,

.

,

The itens discussed are as identified unter th2 "Enforcenent Action" and

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"Other significant Findinp " sections of this report.

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Revio-of Previo*:s Unrosolve 1 Ite ;

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The itens discussed are ite,1: ed in the "Statu; of Previous Cnresolved

.

Itens" section of this report.

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D.

Eevie' # %. ' :; :: ~< " ': v rc- c.c:-. -

The iten; di m.u d are i ten: rd in t% "I.ic en;_

.\\ction on Previousit Identified T.nferce ent Ite s" section of t'ai, re p.ir t.

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Revie*' c f 0:'to r.. _! !it--

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The iters discussed are itemir.cd in the "Other S.,nificant Finding;"

section cf this rc~ ort.

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Statu< of Pr -- n o.' F,n-e 112 /':t:11 39)

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!!ethod of l'andlin

• .1 cnsee findit Findin y (::etail 3!)_

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DETAIIJ

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Perco1; Crn*ncted-

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!r. D.

Ar.y, En;incerin ; Assistant hM

fr. H. A. Autio, Pleant Superintenknt

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Mr. E. D. Barry, Control Rcom Operator Mr. R. L. Scrry, Technic.tl Assistant I)

!!r. N. D. B11 tings, Chemistry and I:calth Physics SQpervicor Mr. R. L. Ecut.:all, Engineerin;; J.ssistant p)Q

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Mr. L. X. Ec:c>.s Cualit; Control and Audit '.'echnician Js'

Mr. T. P. Dum':, Operatiens Superviser

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Mr. R. E, Durfey, Engin2ering Assistant

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Mr. ?!.11 Ebert, Plant Reactor Engineer hf)

!!r. J. A. Flani,;an, Plant licalth Physicist g'"1

!!r. J.

Gedutis, Technical Assistrant - Chemistr.v l,

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Mr. C. ". Coud.In, Cen:rol ' 'on Ope r;.to r

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Mr. L.11. R.ider, ":na;er of Oparn: lens j _.

Mr.

• ?. '". senes, -

-lant Sup rintender.t

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E. Juren:.'.ssistant

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.:u.., daitt Su;erva.ar

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Mr. 3. L.

• irk, Shift Supe rviso r

fr. L. J. Lcifend, Control Roon Operatcr

,

Mr. P. E. Laird, Maintenance Supar"isor l

Mr. A.

Lepage, Central Roan Operator

!r. R. L. Paradis, Control Roen Op2rator

.

Mr. L. L. Reed, Gullity Ccatrei an1.iudit Coordinatar

+

Mr.

1.

Seybold, Tc h:Ical Assistent Mr. J. H. Shippce, Instruncnt and Centrol Supervisor

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Mr. d. L. Staub, Technical Assistant

Mr. R. H. Streeter, Ster: keeper

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Mr..;. N. St. Laurcat, Technical Assistant to the Plant Superin:endent

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'tr. E. A. *.alsh, Shift Supervisor y

6s 2.

Safetv Li-it;< (SLs). Li-itin-Snfet:.

~;teg %-*!_nm (L39: 0, ini Lini t i- - t'e nJ i t ion s f o r ow ra t io-'s

4)

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The inspector revie ad selected SLs, LSSSs. and LCOs for the systens l-listed bele.. to derernine compliance eith Ierhnical Specification /

requirc-nts.

The revie r consisted of direct observations of pracess

,

instru enza:' m,

nitari:: of c'

iti nc, dir,-

ob wrc ::f r of consoles, revis-o f i:u t ru. ent.1:icn en trts, revice of ec-, uter print-

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outs, and revie./ of d:ita.heets.

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-6-a.

Reactor Coolant Systen The inspector revie red the recorder chart fer fuel assenbly exit thern0 couples for the period of *.u;ust 8 - 14, 1974 Thre e instances store observed cherein heaten.nd cooldren rates of the reactor coolant exceeded 5007/hr for short periods as follous:

(1) Approxinately 2045, Aucust 6, 197'

600F/hr heatup over S hour period (2) Apprcxinately 0330, August 11, 1974 660F/hr ecoldoun over y hour period

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s (3) Approxinately 2340, August 11, 1974 WE.i

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80 F/hr cocidewn over S hour period

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Technical Specifications section D.2.d(S) linits the heatup and

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cooldown rate of the nain coolant systen to 500 /hr.

For those cases delineated above the avera;c rate over an hour did not qqd y A;"

exceed 50 F/hr.

The. licensec's inter ret; tion of this specift-cation was that the averacc rate fer an hour could not exceed l 4;;

v.

50 F/hr. The inspector had no further questions concerning this

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natter.

,

b.

Reactivit" and Pover Centrol

The inspector reviered Rowe Power Station Log

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1 for the periods January 1-7, 1973 and Februarv IS-23, 1975 and daternined

,

,

'

that in all cases chile at 100E pcue r and * ith tha exis ting reacter coolant pressure, the core inlet te nerature tas belou 520"F chich 3'

is more conservative than the linits fer 'araced stainless steel clad and zircalcy clad fuel assemblics in Figures 16.3.2-1 and

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i 16.3.2-3 of Chapter 16 of the proposed Technical Specifications.

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By review of Procedure 0?-4601, P.ev. 1, "'uclear Instrunentation I

Surveillance Checks," the inspector determined that the porer trip i l was less than 105: chen tested on Dece-bar 3,1974, Decenber 18, 1971,

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I and January 21, 1975, and February 23, 1975.

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-7-By discussions with a licensee representative, revleu of the incore inst ru.entation ninic p mel, and okrvat kus of a tenpcrature recorder the inspector determined the folloui92:

(1) Two fission cha.bers vere available to traverse 20 avail-able incore paths, one of which cas the at channel.

(2) More than 16 therr. occupies were available to nonitor radial core fuel exit ter.p e ra t ures.

The inspector observed a plot of boron concentration versus f

burnup for the present core.

Extrapolatien of th;s core appeared a

to intersect the abscisst at the expected core burnup at end of N4 life.

The licensee had not nornalized the calculated boren H

.

concentration with this neasured value to determine hou well l ~r l

F this core is teeting predictions, but agreed to do sa.

This

'

matter is unresolved pending fullfillnent of this contienent.

gw LO4 4 c.

Core and Internals

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The inspector daternined by rc. vim of the Charistry Log Beck fbr f:;~ [

the periods of Januarv 2-20, 1973, Januarv 22, 1973, Februar-6,

[i; 1975, and February 20, 1973 that the 0.3, Cl~, and F concentraticns c

in primary coolant bleed scnples ' e re 70.01, c0.1, <.01 respectively.

'4 These values are within these 3pecified in Section 105 of the Final

[f

.

o Hazards Sunnary P.eport and in proposed Technical Specificatiens r ' I',

16.4.18.

d.

Power Conversion Srstc =

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,

The inspector revieved procedure OP-6103 Attachnent K, " Functional

,

Test of Scran Circuits." This procedure denenstrated that a turbine

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trip caused a reactor trip.

It is perferned each time tha reactor c3 has been subcritical for core than eight hours.

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The inspector revieued parts of a re, ort prenared byestin;h:use h.

I entitled "Stean Turbine Inspection "erort."

In the period 't2y 13,

,

l 1974 - August 17, 1975, during the refuelina outage, turbine main

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tenance was perferred and trip pointa vere adjusted.

The as left l

trip set points vere:

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(1) Lov vacuun - 16.3 in. H;.

(2) Thru3t bearin; - 70 to 73 psi:; oil pr2csure

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-8-(3) Low lube oil pressure - 2 psig (4) Overspeed trip - 23 to 25 psi;; oil pre :sure to nave wei.;ht In addition, the manual trip vas deranstratcJ to be operable.

The inspector also detcenined that prc a dure 0?-2102, " Turbine Startup", requires the follmiin.; to be accc plished af ter a maintenance outa;;e or incident?1 outace that has been preceded by 2 or nore nanths of continuous c;'eration:

(1) Control valve exercise (2) Thrust bearin; trip test (3) Oversaced trip oil test (4) Overspeed trip test at I

.

a (5) Lov bearin; oil pressure trip test.

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The inspector revie red procedure OP-4605, "Stean Generator ': arrow

%.n Range Level Trip Calibration," to deternine proper trip settings.

/ g'l; This procedure is perforned on a 15 nenth frequency.

Trip settin;s

'

were satisf.tcrar" (i.e. no - are than 13" beloe nornal levul) for bH SG-1(6/6/ 7,), S 3-2 (5 /30/ 7 '.), S';-3 (5/29 / 7 '.), and SG-4 (5/2 9 / 7 ' '

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Auxiliare S=c3

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By review of en.;ineering fic : d ia;; r.,ms the inspector deternined char

two operable paths exist for boron inje:tien to the reactor coolent (.,

systen.

One path ras the ener;;ency baratian path; the other as

-

fron the boric acid tank to the Ic. pressure storage tank.

By direct observatica of the baric acil :::nk, tha inspector deter-cined that 330 gal. (versas a Technical Specificatica requirenant

,

of 1500 gal nininum) of liquid existe; in the tan';.

E;. re. ie. o f chenistry analvsis shaets, the in ectsr detarmined the tan <. cen*.cnt y

l varied batveen 11.9; and 137 W 3 fo r fi~e anal:.a s nade be t. cen l

l 1/2/75 and 2/20/75.

By direct ob.screations of a temperature gauge i

.

l the inspector deter-ined the tank te Nrature to be 152 '.

These t y results were acceptable.

F In reviewing the data to deternine tb bnric acid concentrati:n in

'

the boric acid tank, it was de termined that a procedure.eas not

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issued to cover the interactiens cr-n the cFe-!strv and o,erations departrenta in controlli,; the

,,s-u -- to t h.: tank aad to assure an analysis aitt

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perforred ay inforral, arai co-.anicition.

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-9-made by an intern.il licencee audit.

Th!- is contrary to Technical Specification D. l. "hich s:. ite ; in, art th t: "... p l..n t operations ubich have a significant direct or atential effect on the re eter and its auxiliary systes.Lc.11 be co'v uct d in accordance tith written procedure s."

To correct this aituatien, a procedure !s beic~ orepared.

The inspector revic ed a hand.;ritten draf t of the pr~ceO;re and eb-tained a cennit.ent that an approved pro.edure vould be issued by P. arch 31, 1975. This Itc, of :;oncon,11ance identified by the licensee is considered to be a Daficicner, f.

Electrical S_veten By revie: of ::enorandum to File H-30 dated ':ove 5 er 6,1973,

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entitled " Plant Lead "edt etion to P.epair % a:;c aused by N

Electrical Tault," the intpector deternined tan the required i'

reactor parar reduction fron 600 'r t to <450 :"t as cade when pc er f ron ' as Z-126 ras lost due to a fault at !!arrinan

,,.

Station. Thic, uas the last loss of a 115%v line.hich has

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occurred.

Lic=nsce action was censistent tith Tcchnical Spect-st fication requue. ants.

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. -3 The inspector revie :cd procedure OP-4209 Rev. 1, which vu par-r forr.ed in June 1974 for all three diesel generators.

The pro-

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cedure tested the auto.atic startin:: of each diesel after inia-

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ting loss of volta p on the three associated energenc;. buses.

e The results uere satisfactory for each diesel generator.

,

The inspector revicu precedure OP-426 and Abnornil occurrence A0-73-8

,

,

to determine if each operable diesel c,enerator was started tithin

-

2 hour:; to denanstrate e p e rna ili t:. af ter cne diesel generator.:cs ej found inoperable.

The follcuing satisfactory infor ation was h

obtained:

> ?{

.

(1) D3#1 was incperable on :ay 30, 1974 at 1000 (2) D0u2 uas started on ::ay 30, 1974 at 1135

'

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(3) D053 uns started on '!ay 30, 1974 at 1145

-

By direct observation t :c inspector deter.ined the quantity of fuel b

oil stored in the three day tMs an.! tha decel fuel oil stora ;e tanh. All tc.':4 excec ed nini en re piirc ents hich tre 213 ;al in each day tank and 503'l gal. in the avera;;e tank.

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-10-The inspector daternined by conve. sat ten ith a licensee repre-sentative that di.>el oil acceptance testin; coa.sists of a naisture test.

The inspector inforned the lirer.see t:ut the standard spt:ci -

ficaticas being prepared for ne.er plants required nare acceptance tcuting.

h.

E er;cnt-Core Coolin, &csten

.

By direct observation in the plant and by revicu of procedure 0?-120-Rev. 2 for veckly periods frv-1/3/75 to 2/20/75 the inspector verified that the Safet - Injectica S:cstte c 4 in a conditica of readi-ness to inject borated vatar into the reactor.

This deterninatica was nade by observing valves to be in tSe properly opened or 10ckad open positiens in the LPSI, HPSI and accunulator piping and by revicving ucekly cperating data which docunented recirculatien qg operation of the H?SI and LPSI pur.ps.

1.

Other Eneineered Safer' Feature 5e n-By review of procedura CP-2100 (and its contained stepuisa chcckoff i;'t initials), the inspcetor determined that vapor containnant integrity was established at the appropriate tina during ph.nt startup fran T.,

cold shutd :n en August 25, 1974 EP '

.

3.

Revies of Flant Onerations

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The inspector revievad the follouing logs and operating records:

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Shift Supervisor Log 2/1/75-2/10/,3

.

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Rcre Statica Lc; U. 1 2/1/75-2/10/75

,

j Rove Station Lea No. 2 2/1/75-2/10/75

-,"

Prinary ?lant Log Sheets 2/1/75-2/10/75

!

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Secondar. Plant Lc; Sheat, 2/1/75-2/10/73 Special Order Ecek 1/1/75-2/25/75 Th

!binte.7 2nce Reques t Lag 12/19/71-2/26/75

'

Bypass of Safety Function and Nos. 74-18 and 75-1

,

'i Junper Control Requests Plant Iafornation Reports Nos. 25, 26, and 27 t,

The above records were revieved to deternine if:

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y (1) Contr 1 roon log sheets were filled out and signed.

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(2) Auxiliarc (prir :ry ple.nt) lag sheets tere f Liled out and h

signed.

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-111 (3) Chift Supervisor I.oq 'cas being niintained in accordance tith

..e applicable p' ant precedure.

(4) Log book revie:3 ' tere being conducte1 by the nfant staff.

(5) Jumpers or byalsses did not centain by,1< sing discrepancies with Technical Specification require ents.

(6) Plant Infor:1 tion P.eports confirn that reported problens do not involve noncompliances t:ith Technical Specitications requirements.

b.

The inspector had the folloving con =ents on the above listed logs and records.

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,

(1) Logs secte being m.tintained in accarcance tith established

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procedures.

aa-(2) Jumpers and bypasses and Plant Information :'.eports did not

%' M ejs involve noncon'liancet' tith Technical Specification requirenants.

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(3) I erevements had h'en ride bv the licen: e in the unkeep of the i~

IE I'spection f

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Special Order 2:ch.

The concern dccu ;nted in n

Report 50-29/74 16, Datail 4.b. (2), is rcsalved.

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c.

The inspectors toared the nenatal plant accessible areas on February 25 and toured the '.'apor containrent on February 27.

Obser-f

,

vations were nade of the follerint,.

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(1).'!cnitoring ir.;trumenta tion; (2) Annunciator alarna;

(3) Duty control roon personnel;

'

(4) Radiation exposure control;

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(5) Housekeeping; (6) Fluid leaks and pipine vibraticas;

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l (7) Pipe hanger adjust..ats;

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l (8) 'lalve positions; (9) Eq:I nt ta; etir.;; and T

i (10) Disc i n; rith centr,1 rem-ne r u :n

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The inspector had the followin; ec ne:ts on Itens observed durin; p'.

the teurs:

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(1) The.ulti-channel recorder paoer en the 'adi it ion "on!:orin t Systen Console as not p ro:'e rl:. ti ad.

The 11cen<ce ad j uned

?'lk the rapcr anl the inspe ter ha.: na furti.2r questions con;ernir th's matter.

M, (2? ihe calibration sticker on a safety injection loo, pressure

1" transnitter indicated the instru ent ras cast due far calibra-tion and another trans.itter lid n,t have a stieker affine;.

If The licensee's calibra:Ian recordi indicated that the instru-N.

ments were not overdue for calibr.tlon an ! the licensee affined d.1 stickers on the t co instru.ents that anree:1 with tha ualibrni:r Cb records.

The insnector hau no further questions concernin; this

natter.

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(3) The Prieary Rod Position Indicttien (indivilual rod indicat

,.a*

-

i - -- T display en the main control bonrti in:!icat:.4 ti.at secer.'l rods V'

m were lo ter then the wtu al poaf ti n est Oli.2n:d thrcu;h ;rr s s checks bet teen visicarder calibriti n d :t2.nd the Secor".:.r Rod rosit.en indic:. tion u,roup ir.u ca !cn f.

Tr' f allc i dn I

tas gn'. red f r:m ::.e main ;antrei ; _.r in !.ic a t irs en. :.;ruir". :.

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a Individual Group (.t.c t ua l)

Indication Indication Errrr e

Con t ro l

~'.od (Inches '.'ithdrT:-d

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75 80 211 5 2/5

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84 88 1/8 4 1/3

75 88 1/3 13 1.'s

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72 88 1/8 16 1.'s

84 88 1/8 41.'3

81 88 1/8 7 1/5

,

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This lack of accur. ey in the individual rod position ind!:ni:n

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systen is contr.,:y to the state ent in Section 213 of the Fin:.'

Hazards Suamary 7.eport i hich s t ates that "...th2 accuracy is sufficient for po ter plant operation, an 1 is eithin =3 in."

Tha I

inspector noted that this sanc stat <. ent had been incorporatel g{

into the licen we 's p reposed Fn~'. This i t n i=: considered ::

be a Deviation and a reononse fro-the liceniec addressinc this

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r.atter is relai red.

(1.: f e r to O n :l l e j (4) "The inspector obc-rv ! t%t th-arin han rc <n the nr.e<:r'

e-f surge line and the ri:id h.n er:

.

the a fet. 1:lectinn ria:

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header had not be.n 1.i>:c.1,.nc

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I st,i t : visit S.

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inspecter.

The licen;ee stated t.ut h t ! recent i:. is4c.s a

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-13-procedure concerning this itter in1 the rork raa to be done s:.-.

The inspector revie ced a carv of ;'racedure 0?-5107, "Invectirn and.\\djust ant of Pipe '!an::e r s, " is-ned en 2/4/75 and hvl no further questicna on this iten at thi4 t i-e.

The concern d2:u-e.cnted in IE In:metion :te: ort 50-29/74-16, De tail 4.c. (3), run;ing unresolved pend'nc cor.pletion of her;er adjustncats.

.

4.

Abnor-21 Occurrences-The inspector noted that no abnorral occurrences had been reported to !!::

since the date of IE:

f ns.scetion 50-29/74-1o.

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The inspector ex nined the follouing records to deter :Ine if the related h

events 'ecre re?ortabic as abnernal occurr nces or unusual events in

' ;

accordance tith Technical Spccification C.2:

N's k

Syste-Records Exanined D;scription of '!ai. itentn:e

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Charging and

!!R 74-596 Repaired crack in al char:in; i' ll

Volu'e Control JO 74-205 pump cuction strainur.a'd.

L

Weld Data Sheet LP Inspec.lan report

!

Q.\\ Inspectica ::ecard

.

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S t'.an t'en 2 ra te r

?rt 74-515 Repaired le level Level Control J0 74-135 alarn on "3 steam gencrat:r.

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,

OP-4604

'

OP-62%

The inspector a-reed that the events were not reportable as ibn:.al l

occurrenccs or unusual events and had no furthcr questions concernin;

,

this raatter.

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5.

In-Plant *udit Pr.mtra-i

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h o The inspector revieved the status of the In-Plant.iudit Progra-. and

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noted that the yearly cycle of tne audit nregran that was due for

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conpletion on 5/75 was canaleted in 12/74.

This.tas acconplished by

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the licensee in order to convart from a cycle beginning a-d ending k

in !!ay to a calenda f:ai cycle.

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The inspector revie:ed a draft of aracedure Mi-119, "In-Plan t liul! t

,

P rogra. " T:.c p rx.nlure 2: revi.

. aul! re.'.. the con: erns s

i docunented in IE.I Ins,'ction 'eport 50.0/74-16, ?etail 5.5.(31 This iter re ains unctI,olved rendin; licen e issuance of final

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procedur:.

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Cont rol ':o.

Eurveillance Prorry Reference:

(1) ';P.'; letter to licen:.ce dated Februari 19, 1975 (2) Licens.'e letter to '.1R dat,cd reb:.are 14, 1975 (3) ';Pa letter to licensee dat..!.lanaar e 22, 1975 (4) IE:I Inspection epert 30-29/7?.-10, Detail 6 (5) Licensee letter to Directoraw of Licencia;; dated

.

Septenber 4, 1974.

(6) Licensee letter to Division of hactor Licensin.;

..

'

dated August 27, 1954.

,

The Office of "uclear ".eactor regulatien autharice.! in reference (1)

f@f a tenperar-4 treck extension of the current 12 e'. survcillance interval for control red drap testing.

The ncxt control rod drop test :ust be u-

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perforned not later than " arc'.i 22, 1973. The concern docunanted in reference (4) is resolved.

s:

7.

Control ?.od Banki';

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Reference:

IE:I Inspection P.eport 50-29/74-16, Detail 7

'E..

'

.

t The inspect!on revierad data fron control roi positica checks nade on K

12/26/74,1/9/75,1/2 3/ 75, and 2/6/ 75.

These checks are nor,11v na.'e

'

'

every sin. ceks to provide a periadf c prc'ren to insure pro;2r control

'

rod banking.

The chachs were conducted bi.::ekly for a pariod to

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deternine tchy reds 9, 10, 16, 22, and 24 : ere being found out of bank

(lo:eer) by about tro inches.

'

-

The results of the latest surveillance tests ncnticned above have re-inforced the licensee's opinien that the rods are not slippin;; in.

The l-problen is believed by the licensee to be that the subject rods cannot

[

_

be noved. ith the renainder of the rods in the banks beyond 87 3/8."

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It has not been deternined /rz certain rods cannot b2 noved bevond

'

.

87 3/8" and this rill be the subject of a licensac investigation f., c.

during the next refueling shutdoin.

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As stated in the IE:I Insocction P.cpert 50-29/74-16, Detail 7, the licensee has evaluated the safety aspects of this probic and believes that safety of plant o,erations has not been reduced.

The Plant

{

Operations ::evie: Cc :lttee ( PR'.C) revieced the banking pro 51er in

!eeting 75-8 on F2bruary 4.

The insp.etor had no furth2r questions

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concernin;; this natter at this ti c.

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Increa c_._in core and I.oxi iT's f4 Reference:

(1) IE:I Inspection ':e:*o rt 50-29/7*.-if., Detail 9 E

rJ1 I s

(2) IE:1 Ins ection neper: 31-19 / 7.- )2, ce t t : 1 18 r. i

.

(3) Licensee 's Se 1-inn : il J' wrm.

c-1erort.or the 3.N, I

.

period July 1, 1973, to :we+ r 31, 1973

f M gy The P0';C has reviered the incre e in cor.

and Ico, LT's that hu Y<

been attributed by the li:ensee to scatter of te wrature data.

.

h The inspector had no further questions 'concernir..; this natter at

..

this ti-e.

oy 9.

Main coalin! r :, a n i % " il f a j:e a i rg

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0. ; pl Re ference :

(1) IE:I Inspectica Report 50-29/7'.-16, Detail 8 m3 (2) IE:I Inspection !:eport 30-29/7'.-14, Details 2.c.(2)

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and 2.c. (3)

W+ 4',

(3) Licensee letter to IE:I dated December 9, 1974.

- 1 f,, M M

The inspector verified th it the licenuce has drcfted receisicas to

..

procedures ;?-5293. ":'ain Coolant Check 'laiv2.: a i r, " a n ' OP-5 20 5

"!ain Ceolant Pun: Ira ection cnd ::et. irs": F cccer. since this actica is incen71ete these itens re,ain unresc h ; '.

,'

10.

Pe r fa r-n ce is ch try Texts of Srstin1 P tt: * e;

'

.

. -

The inspector revie ed nrecer!ure /sP-30'D, 'ev.

1.,

' Maintenance Departnant Surveillcnce Schedule," and deter.-fr.cd that tha licensee

.

plans tc ccaduct s tatian b at te r" c : Tei ty te ns. cery 3 years.

Th2

>

concern identified in I?:I In r e c t ion t'.en c r t s 3 3-2 0 / 7 '. -h,

'e t a i l 5, and 30-29/74-14, Detail 19, dealing zith the sub k:t tests is resolved.

11.

Ava i '. n', i l i t 'z o f En te r" Ch ir er

.

The ins::cetor revie.:ed a draf t of Plant Nii nn Chan :e '.eq :as t 74-14

'

which provid. s for a nodit icatian o f ':o. 1 and 2 battery charcer circuits that include s addin; an alarn circuit ta ;ive an alarn in the Control Teo-aanever the citr;;er f: ses ope..

Th previsions of PDCR 74-14 resolves the cencera docu.ented in IC:I Inspection Zeport 50-29/73-2', Detail 11.d.

f-12.

Polar rra, r --t r,1 Ci rm.i_ t_

" 21 ! n re The 1:t >;

e

s 1-c. t i t?

!! f the v 1, r c r,

c: : tral circ u t by providir-t redund.nt m: dizerce upmer. l f it ir t riod.

The liv eee is in the pace af or r:r :

art-ter :

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-16-13.

Cont ral ".ed '.?rth Di ic ry inc ie_s Reference: (1) Licene letter to ' m dated Janu.rv 31, 1975 ce (2) Liecnsee letter to IC: I da ted Sep t e nbe r 18,19 7!..

The inspector revie ed ref.:rence (1) in Fiiel the licer we conclud2d

.

that operation at full po..:r to end-of-life of Cere :t'rith the measured rod wrths is covered bv the safety a: W.. i s ceaducted usin; calculated rod.corths.

The insyctor had na furta.:r questions con-cerning this catter.

14.

0'eratin

"e es Reference: (1) Licensee letter to IE:I datv! February 12, 1975 (2) IE:I Insrection nepart 50 -29/ 73-91, Seta11 2 it

,

(3) IE:I Inspection Report 50-29/74-?6, Detail 10

The inspector revic*:cd the licensec's effort in clininating all

{h; safety-related Ope ratin: "anos by cancelling the n:~as or incerpor-

s ating then into ncs. or eni, ting plant preceJ

res.

The licensee r-1-had co 7 cted this a:tica bc fere the '! arch 15, 1975. date establined i.

in reference (1).

T..is atter is r sclved.

.

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,

15.

Floedin-rff, cts o f Fa!! ures o f ':on-21fet" elated "m:!' ont p.

.. n -

The inspector reviered the tenporary protective neasures ehich rere h c.i r

initiated by the licca.=ee to protect vital areas f ren ficoding in the r

j

'

event of a failure of non-sa fety related e pi.. ut.

The licens.:e 's

action as as stated in his letter to the

"'C date ! January 20, 1975

-

(1.7R 75-9).

The inspector had no furthe r questicns concernin;; this catter at this tina.

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16.

Safet. Iniection.ictention Si n11 9urv'illc"ce

'

.

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4 The inspector revic*.cd surveillance data for the tre contain ent n'ir L

A pressure s. itches that initiate a Fafety Injecti:n.ictuation SI:nal.

The inspector noted that the.snthly operational c'.ucks of the s ritches c

were not nade durin. Januarv as required by FIM' Section 503 and f

Technical Specificati:n D.2.1.

The lican we provi?cd the inspector i

with infornation that indicated t!.e licens e had previously discovered

[

this nissed surveillance test and h,d tak<n appro,riate corrective

~

_,

action to prevent recurrerce.

This Itan of

.r. cmliance id ntifi d

by the licensce is considered to be a De f ic i m

.

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-17-17.

I'se of the Tern "':/1,"

The licensee rrovided infor: stien that indicat2! th3 lietnse.- is presently cc.nsid2 ring, all "::/.\\" 'nt ri s in prxc lures as chan.es to approved procedures.

The "' /.." ent ric a tre b.in a,, roved ';>

two Senior licensed indi'.iduals an1 tha FC.

Th cencern docu-cented in IE:1 Inspection "eport 50-29/7'.-16, Detail 13.b.(4), is resolved.

' crt an Gnor 11 ne e.:r ret' c '

18.

Fail tre tn Reference:

(1) I.icensee letter to IC:I date ! Tebruary 7,1975 (2) IE:I Inspection deport 50-29/7'.-16, Detail 13.b. (2)

.,

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The Itcensee's corrective action as stated in reference (1) is

.W 7th acceptable. This ite: 3 is resolved.

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46MI 19.

Correintion 'sta

• Flc 7 vs. ':en current

. "a

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Reference:

(1) Licensee letter to ':3C da t ed l'eb ruc r.- 19, 1975

.

(2)

'r'.

2 2 t:nr to 11cr~m d it, '

Y"a~

39, 1)75

, )

(3) Licenace lettcr to "RC d;ted Enuare 31, 1973

..

-

(4) IE:I Ins,ection scrort 50-2 9 / 7 '.-M, Detail 13.b. (2)

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The inspector stated that he had revIc'.ed the reference.1 naterial and could not de te r:-ine from the d-ita if the.Tia conlut pu p

loe curre.t set pcInts cre equivtlent to a fir-of no less than

80% of ncrr.al.ain ceclant (1c.7.

The lice 1.ee stated that this

.

probic, had been referred to '.:estborouch fer rno'utica and that

,,

b'estborcu;pi * ould resolve the issue il th '3C.

This iten identified i

I in reference (4) re.ain; unresolved.

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,

20.

Inc rectica of ECCF Circuit Bre,' e r r ->

-

I

-

The licensee had draf ted a revisien of procedure 0?-4506, " Inspection p

1'

of ECCS Circuit Breakers," to resolve the concerns identifici in (,

'

IE:I Inspection Report 50-29/74-16, Det ail 13.b. (S). This iten

[

renains unreceived pendin;; issuance of the final proccdure.

t (

21.

E.ercene-Pr 3r l'nde r 'lal t,q a Pel a";

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.

5-The liccns2e stited taat ve ri l ca ti vi te s t i-' of un.!er e,lt l'e rela

'

I serraints aad 2_ n incor oritei into th.* nre it!

-' ntenance

.

I'

l progran and ::euld to pe rie:.2 ! durin : th. n :t re :elina outa

.

l The cancern Jx umented in ti:I Inspectica..e p a r t 50 -2's / 7 4-16, Le t:.11

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13.h.(9), is resolved.

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Proc _ure a t The lice n:,c e.,tated that Guideline ':n. 1 is still uni r revision and an apprcved vendars list is being co iled.

The revisica effort shot.1;.ah e :' uide li na :o. I conii m nt rith precedure AP-1211 in the area of vendars lists.

This in-t.hmti tci in !C:I Inspection neport 50 29/74-16, Dotail 14.b., re.ains unresolved.

23.

Fire Proof Files The licensee has received

,c.e additional firepre.,f files to be used for the stcra e of pi,nt <1uality assurance record <.

This n

Iten of ::ence-- liance identificd in IE:I insrectien "eport 30-29/

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74-16, Detail 15.b.(2), renains unrcsnived readine, tiliar, of QA

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records in these files.

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Unapprcred CS:mes to Precedures M..;

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Reference:

(1) Licensee letter to IE:I dsted February 7, 1975 j; >

(2) IE:I In3;c: tion peport 50-29/74-16, Details 13.b. (3),

i 15.b. (3), and 16.b. ( 3)

The licen ;.e's cor:2cti.c action descri

.>d in reference (1) is acceptable.

This iten is resolved.

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25.

Plant Dr.r:in e s Re ference s : (1) IE:1 letter to licenee dat.d February 25, 1975 dated r bruar: 7,1975 (2) Licensee letter to II.::

e (3) IE:I Inspection p.eport 50-2'!/74-16, Detail 16.b.(7)

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The licensee's corrective action described in reference (1) is acceptable.

Procedurc AP -0225 " Plant Dre rin;s", tras issued for

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use en Februsry 20, 1975.

This item is resolved.

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26.

Control of "evisions to Plant Drn.Incs an ! Precedures i. -

The licensee has revised procedure AP 9222, " Job orders",

to assure effective contral over the idc.ntificatien and re.Iston of drauings and procedures af fected b; danien changes.

The concerns identified in IE:I Inspectica 7epart 50-29/74-16, Details 16.b. (6), 16.b.(7),

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and 16.c., are resolved.

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Test r^ t@,nyn t lemi! rl_n Ou t s,i,.!r C:ll ib ra t bg i

Reference:

(1) I:::I letter to licen<c:, dated rehreirv 25, 1975 (-) hicensee letter to li;:I d it.s

"et a ire ;

1973

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(3) IE:I Inspection Perort 50-29/71.-16, Petail 13.o.(6)

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The licenece's carrective action dercrib d :n refe ence (1) is j

acceptable.

Tnis iten remains tinresolv2d pon 'I" ' revia ton of N'

procedure /2-0215.

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28.

Recal!5 rat ! :. c f Sa e t, ci,csif te ; gg,tg, r g-:a.,-t.1eron

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t uj i The licensec stated that uhen neasuring and test equi 7 ment used to perfern calibrctiens ca a safetj classiff;d 3,..ste.[ is foung j

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out of tolerance and the out of tolerarce condition resulted in

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a less conservative safet" sW te: calib -t.4o.., t'ne.m,n t Suner-

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intendent vill review and apprete actica on the natter. The N

concern docu ented in IC:I Inspection Report 50-29/74-16, Detail UN 13.b. (6), renains unresolved pendin:; res isien of prc:edure AP-6002

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to incorporate the Plant Superintendent involvement.

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29.

Adniaistr,r,:

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The inspector reviered the licensee's.eth?d for handlin~ the review Iten at :3nco7 11ance identified b:

'..'C ins ectors and the nethod :cr Processin; propcsed to,ts and e:.,eri-ents.

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Plant Personnel 3re co.;izant of re luirnents and th[ir respon.;ibilities

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in these arc H.

ne inspector had na furthcr ques: ions concernin',

this natter.

30.

Status of tre

.,u d chan e 112

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t The licensee en-essed cencera citer the v'C f alay in revieuin and J

approvin;; Proposed Change 112 to tha Technical Spacification which

'i was su nit ca v the licensee on January 3, 197'..

This chan e inclu ed piant Technical specificat w,c in a fornat outlined in

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Regulatorv t,ume 1. 70.

To aid in tha. C revie* and aopreval of

this caan;e the licensee also provided the Final I!a:ards Su c:ary

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Peport rewritten in FSA?, fornat.

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The basis for th!s request that approval of the chanr,e tra s would substantially :'ssist both the staff and the "".C in providing the necessary uidezlines to prevent difficultie, currentl;. encountered with the prevent rechnical Specificatiens and Pir;.

The inspector acknoeled od the licensee's re arks and stated that Fl.

had established a schedule for review and approval of the change. The expected co: eletien date is Septe :ber 1973.

31. ?!ethod of Handline f.icensee 3.udit Fin :in w M

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3rg The inspector infor. e3 the licensec that all liccnsce findings identi-M.Sd ficd by the licen <ee as Itens of ::eneo :eliance would be documented in N)E IE Inspection reports as Itens of : onconpliance.

The inspector stated N

that a 1:otice of Violation would not be issued for such itens unless

.N the itens were Violations or the licensee failed to take tinalv d'

corrective actions.

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The licensee cr-rese?l concein nver the f-t th e 5.e would be. en:11:ed l

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for an effective pro;rar (i.e., the nere Iter.4 of !!onconcliance he L

discovers and prefer 1: resolves the worse his prcerar appears).

The

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licens2e also indicated that there was no :e ;ulatorv requirenent for i'

him to docunent his findings as Ite.s of :enco.pli,-ice.

The inspecto.

acknowleged the licensec 's con-ents.

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