JAFP-85-0324, Responds to NRC Re Violations Noted in Insp Rept 50-333/84-24.Corrective Actions:Section 4.8.26 of Procedure PSP-17 Will Be Revised by 851001 to Repeat Air Injection to Ensure Removal of Water from Coolant Dilution Sample Line

Responds to NRC Re Violations Noted in Insp Rept 50-333/84-24.Corrective Actions:Section 4.8.26 of Procedure PSP-17 Will Be Revised by 851001 to Repeat Air Injection to Ensure Removal of Water from Coolant Dilution Sample Line

ML20115D968
Person / Time
Site:	FitzPatrick
Issue date:	04/03/1985
From:	Glovier H POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.D.3, TASK-2.F.1, TASK-TM JAFP-85-0324, JAFP-85-324, NUDOCS 8504190158
Download: ML20115D968 (11)

Text

-.

James A. FitzPatrick 4

Nuclear Power Plant PO. Box 41 Lycomng. New York 13093 315 342.3840 Harold A. Glovier

1. > NewYorkPower 4# Authority April 3, 1985 JAFP-85-0324 United States Nuclear Regulatory Commission Region I 631 Park Avenue King Of Prussia, PA 19406 Attention:

Thomas T. Martin, Director Division of Radiation Safety and Safeguards

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INSPECTION NO. 84-24

~

References:

1.

NUREG-0737, Clarification of TMI Action Plan Requirements 2.

Letter dated March 12, 1985 from T. T. Martin (NRC) to H. A. Glovier (NYPA)

Gentlemen:

In accordance with your request in reference 2, we are sub-mitting our response to each of the findings contained in the subject inspection report in Attachment I to this letter. Please note that for those findings which contain several parts, each portion has been provided with an individual designation to simplify response and tracking of the commitments made (if any)

.and each finding item has been referenced to the appropriate NUREG-0737 task number.

Please contact Mr. Eric A. Mulcahey of the James A. FitzPatrick Nuclear Power Plant staff if you have any questions concerning this matter.

s HAROLD A. GLOVIER HAG:EAM:jaa Attachment Copy:

L. W. Sinclair, WPO R. J. Converse, JAF J. P. Bayne, WP0 R. L. Patch, JAF R. A. Burns, WPO E. Mulcahey, JAF J. J. Kelly, WPO NRC Resident Inspector, JAF G. M. Wilverding, WPO NRCI-84-24 File J. A. Gray, Jr., WPO Document Control Center A. Klausmann, uPO B5 4190 % N 3

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IATTACHMENT'I J

l-RESPONSE TO I&E1,1NSPECTION 50-333/84 '

'NEW. YORK POWER AUTHORITY' V

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' JAMES-A. FITZPATRICK' NUCLEAR ~ POWER PLANT.

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zReviseithe procedure to assure that no dilution water is. held

-up in.thefline.-

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Reference:

.NUREG-0737,II.B.3, Post! Accident Sampling Capa-

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nResponse: ^ T PSP 417 ' section 4'.8.26 will _ be revised to, repeat

. air injecti'on ~ to E ensure'. that sthe water is 1 removed from the

coolant. dilution sample line.

This'will.be' accomplished,by

. >0ctober 1,J1985..

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_ 184-24'-02:-

Revise. the procedure so-that personnel are aware - of ~ the t

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proper; loading and installation of'io~ dine / particulate. filter

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1 assembly.

Reference:

NUREG-0737,.II.B.3,1 Post Accident Sampling-Capa-

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bility.

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Response

Instructions will be added -to PSP-17 delineating proper loading ~ and installation of the iodine / particulate filter 1 assembly..

This-will be accomplished by October 1,

1985.

'84-243-03:-

i LComplete provisions: for the ' packaging' and f shipment of ? the j

PASSisamples to the offsite laboratory.

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Reference:

,NUREG-0737, II.B.3, Post Accident SamplingfCapa-i

.bility, y

Response:-.iTheLPIM's " Post Accident Sample Cask' Operation.and 1:

Maintenance Manual" NUPACLPAS-1,; revision 1 has been received-

. and Twill; be : incorporated 11nto appropriate-plantJ procedures.

!This: will-be accomplished :by -October 31, 1985.-

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84'24-04:

Evaluate _the adequacy-of the'MCA software ~to adequately 3 anal-

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j yze a; post-accidentimixture~of radionuclides.

Reference:

i lNUREG10737,L:II.B.3, Post Accident-Sampling-- Capa-y.

.bility..

.c 1 Response:

! An Levaluation willf'be performed. to. deterniine the l

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' adequacy ofi the MCA. software. to adequately: analyze a post

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-accident: mixture:of radionuclides.

This~will be accomplished-

by. _ November 30, 1985.

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. Perform a tim fand motion study for the sampling and analysis e

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. of dissolved gas.

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Reference:

NUREG-0737, II.B.3, Post Accident Sampling Capa-bility..

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Response: !A-.timerand motion study for the sampling and anal-

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4 - ysis. of diss'olvedcgas. will be performed within 90 days of reactor start-up from the 1985 refueling outage.

Start-up is i

?f scheduled ~:for May 6, 1985.

H, l84 05B:

- Document,. the previous commitment for the sampling. of dis-l solved gas, ~ including the sensitivity and accuracy of the analytical method.

Reference:

NUREG-0737,-II.B.3, Post' Accident-Sampling Capa-t bility.

Response

. Sensitivity and accuracy documentation of-the

-analytical method for : sampling dissolved gas has been-pro-vided - by ithe_ General Electric. Company to - the 1 NRC' by January 18, 1984. to Mr.n Darrell G. : Eisenhut.

This was.' found to :be t

accep. table'by Mr. William V. Johnston NRR on-July 17, 1984.

84-24-06A:

Alarm s'et points for the ' PASS background monitor;'should' be t;

revised.to reflect the'specified criteria for the' evacuation' of the-area.

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Reference:

. NUREG- 0737, 'II.;B'.3, Post ^ Accident Sampling f Capa-3

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Response:. The PASS radiatiori monitbr talarm sethpoint's-1will.

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'be set.to the level'specified in the PASS Operating Procedure e

PSP-17 byloctober 31,,1985.c-a:

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UCo' ordination '-sNould bei est'alilished betw'eenc _the groups that perform the. ~ calibration; of D the PASS, radiation monitors and

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' caudits.. : Calibration should bei conducted _in accordance: with I

imanufacturer'a recommendations.

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Reference:

NUREG-0737,. II.B.3, Post Accident : Sampling Capa-y

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Response ~:.TRid5ation_ source calibration of the PASS radiation i

monitors: willTbe! coordinated ebetween1 the RESand ID & C de-i~

1partments.

i An evaluation will be performed to - determine' a t

metho'd :for c'alibrating-to the m'anufacturer's' recommendations

>especially..with; reg'ard to radiation source; calibrations. This 4

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'will be; accomplished by-November 30, 1985.

84-24-06C:

JAlliPASSJcomponents should besincluded inithe-formal preven-

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j' tive~ maintenance program.'

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Reference:

.NUREG-0737, II.B. 3, Post Accident f Sampling n Capa- -

bility.,.

t i esponse:

A formal preventative maintienance program will in-j R

clude FASS: components-recommended.by the vendor to'be.in the program;: 5This will beJaccomplished by-December.- 31, 1985.

j, 84-24-06D::

c Procedures'should be revised to call;for the' installation of anlAg-Zeolite ^cannist'er during.use'of_theLPASS..

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NUREG-0737,' II.B.3,4 Post Accident. Sampling - Capa-

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.-The PASSf Operating : Procedure, _ PSP-17, will be 're-

Response

(vised.to require;thesuse of silver zeolite.cannisters in the 4

1 l continuous air. monitor.and/or = low -volumeiair ' sample under l

Jaccident conditions.

This will be accomplished by October.1, "1985.

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.. EvaluateT thef effeet from the tiodine/ particulate, plate-outc on ithe/NGEM! chamber under high' release emergency conditions.

Reference:

NUREG-0737, II.F.1, ATTACHMENT-1, Noble; Gas; Ef.

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An empirical calculationNwill E be ' performedi to 2

l evaluate: the Jeffect of iodine / particulate plate-out' on the iw n

.NGEMrchamber? cunder ~ hight 'rel_ ease ~ iermergencyf conditions 1 ?by -

December.31, 1985..

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Evaluatelthe energyfdep'endence'of the factor which'is'.used to

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convert 9 exposure',ratei to,^ activity : release _ rate, sinces the

..F sresponse cof;the : ion = chambers. may shift sdue to the?. variable

-.energyJsp,ectrum'following4an accident.-

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Reference:

xNUREG 0737,7II.F.1,- ATTACHMENT 1, Noble ' Gas.. Ef-

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to c convert ; exposure z rate tom activity release ~ rate l isnbeing pursued! through the?: vendor.

It,is. anticipated that this

information will be ~ received by October. 31',.1985.

Attthat 1

. point,aan; evaluation will'be? performed:on the appropriateness;

'of the calibration.-

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- Provide 1the: capability for. the : doselassessment-computer model l

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to ' receive. the results directly from - the ~NobleJ Gas Effluent.

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- NUREG 0737, ~ II.F.1, - ATTACHMENT 1, Noble Gas Ef-

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Response: )The Authority (disagrees with the requirement gfor F

inputting n then NGEM Jresults - directlyn to.the n dose assessment -

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computer model for the following reasons:

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-a.. 'Present procedures provide a' simple,: reliable and' rapid-4 Emethodjfor< inputting monitor data..

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benefit-to be realized.

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No;regulatoryrrequirement/for directly inputting r;nitor E

data has been' identified.

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L84-24 08A:1 4

2 Perform an fempirical f determination of possible Lline' loss of

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11odinejin.the sampling line.-

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Reference:

1NUREG-0737,c II.F. I',. ATTACHMENT. 2, - Sampling and Analysis,ofsPlant: Effluents.

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An

empirical-f ealculation ~ will; !be'. performed 'to y f p

determine; possible 111neDloss Mof siodine in the sampling'line-1 bytDecemberJ31,71985b

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ReOiseiproceddresito: identify sample-collection, handling and

, transportnsteps under~ emergency conditions..

Identify antici"-

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. pated hazards-and time constraints under these-circumstances.

No, lIn particular,ve'valuates the source, term and determine expo.-

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sure: ' hazards. land _ co~nstraints : to personnel from-the NGEM fchamber :(see; sectionc5.2.1' of: this' report for details).

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-Analysis.of. Plant-Effluents'.

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i esponse: N stsdy will;be;performeduto, establish'the source R

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term from:the;NGEM andidetermin~eDexposure~ hazards to person-

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-nel occupying the: PASS stack, sample room.

This study _will?be-

.. accomplished 1by December 131,; s1985.z. Within 90 days l ofire-M ceiving the study, the PASS'_ Operating Procedure, PSP-17,_will

.beiirevised to: reflect. study:;results,. sample collection,

- handling n transport steps,, anticipated : hazards and time con-=

straints.

i 84-24'-08C:

Incorporate.the' iodine results'into the source term.which may

- be;used-for'offsite: dose. assessment.

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Reference:

^- LNUREG- 0737, II.F.1, ATTACHMENT 2,

Sampling and

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Analysis of'PlantlEffluents.

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! Response:

Procedures will be irevised to input ~ planti and/or

. field. sample data for~ : dose. ' assessment during an f emergency.

4 This wil1~be accomplished by.0ctober 31, 1985.

84-24-08D:

ii Provide >' shielding for. cartridge storage'. ' n..the _ sample i

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. building l to? limit exposure. in ithe-event that - a higher than fanticipated' activity _ isi collected on ' a. cartridge..

These

[

items will;be reviewed.Lduring a subsequent' inspection.

Reference:

'NUREG-0737 ~ tII F 1 j

Analysis of'PlantiEffluents.

~,-ATTACHMENT 2,

Sampling and r

1 supplier will be r.equested.

- to-evaluate' the. consequences:pmenti

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-Response: _ ;The fsampling ? equi of a1 flow element. failure.

Cor-rective uand/orisafety' measure (s) shallbe - undertaken based

_upon:the evaluation-of~the4 supplier'scresponse.-

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< Define.th'e. primary and alternative -- methods ' for estimating core damage based-on reliability of data and methodology.

Reference:

NUREG-0737,

-II.F.1, ATTACHMENT 3,

Containment High-range Radiation'. Monitor.

Response ~:~ The " Containment Radiation Monitoring - Post Acci-

, ; dent" procedure 1RTP-34 will be revised to clarify the-primary and alternative methods for estimating core damage. This will

,jbe~ accomplished by' October 31, 1985.'

+ 84 24-09B:

' Assure the calibration would be. valid for-the modified po'si--

' tioning of the A" detector.

Reference:

NUREG-0737,- II.F.1, ATTACHMENT 3,

Containment.

2High-range Radiation Monitor.

Re'sponse:

An engineering " evaluation will be performed prior

-to repositioning the

' A detector which-is.- tentatively

' planned for;the 1986 refueling outage.-

84'-24'-09C:

. Provide documentation-toD justify thei present detector -loca-

tion's are free.. from shielding effects or ? direct dose' rate effects. from adjacent structures 1or equipment.

Reference:

.. NUREG-0737,.II.F.1, ATTACHMENT 3,, Containment.

High-range Radiation Monitor.-

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Response:. An-engineering evdluation is - being ' performed to

determine if the present' detector--locations--are appropriate.

The evaluation'will.be1 completed by July 31, 1985.-

84-24-10A:

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Address samp1'e1purgingJand in-plant < field" analysis.in appli'-

cable procedures.

1

Reference:

NUREG-0737,_ II.D.3.3, Improved Inplant. Iodine

~

Instrumentation Under: Accident-Conditions.

Response

Procedures-which would ' be"used' for in-plants field ~

+

air; sampling / analysis: ;in cemergency -situations. will4be- ' re-Eviewed ; and revised! as. necessary --to-require iodin'e cartridge ;

L. purging'.;;Thisnwillo.be accomplished.by. November;30, 1985.

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2 iProvid'e readily accessible' air. samplers for emergency situa-tions.

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Reference:

j NUREG-0737,._II.D.3.3, Improved: Inplant -Iodine

) Instrumentation Under Accident Conditions..

. Response:

Emergency; air: samplers are maintained inLcabinets, designated ifor/ emergency use. '

In1 addition,;.the RES / depart-ment has. : plans for abuilding Jan s instrument -issue room' to controirinstrumenti location.; : This_ will ensure a : larger, t

,readily ?available inventory (of L day-to-day instruments.':

The

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instrument. issue-roomyis:.expec et dito -bec completed c prior. to

'the 19861 refueling. outage..

" 24-11:

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The inspector checked the preceding' calibration records'which

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t indicated: that -these ' instruments wereEcalibrated within ~ th~ei

- due - date. - However theD above".two' calibration records showed

that -' there were ~ e' tremely high. drift problems, with these -

x

instruments.

-The clicenseel. explained.that the radiation

instruments -weren calibrated independent 1y' and. at different

- ' intervals'by'the'I&C' department andLthe~ radiation-department.

The I&C calibration Gused ~ two - point electronic pulse - input-from Ea : pulse Egenerator -whileuthe radiation departmenticali-

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bration.-used one point;: radiation Jdose - rate - input,.for. a. four

-decade Jinstrument.

In o'rder <to' avoid similar problems from recurrencei the: licensee agreed yto ^have one department in:

charge for 1the calibratio'n - and that morez than one pointi dose rate source be used in the calibration.

Reference:

' None.

Response

This" item was responded to'in item 84-24'-06B.

s 84-24-12:-

LThefinstrument.. calibration -stickers iattached' to.ihe'instru-<

s ments f were?: not.properlysfilled in. _ The' instrument J numbers were ? incorrectly placed.. where the " Calibration Due Date"

.should be..

'RAference:

None..

iResponse:. Instrument calibration stickers'have been replaced-

'by properly completed stickers.

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~According'to the ' licensee's' PdSS personnel, the normal cooling water to the. sample, cooler- 'would not be available after ' loss' Jof offsite : power.

They: stated that ' emergency power was :available 'and ~ that and " emergency water. supply con-i nection" was provided at the sample cooler.

However there is

.no' defined; water' pump (powered'by emergency bus) nor defined water source physically hooked up to this connection.

Reference:

None.

~

Response':

. Preliminary evaluations ~ indicate'd -that sample

cooling may not be ' required to maintain sample temperatures within the. vendor's recommended temperature for the equip-

. ment. - Several' tests will be run to determine if cooling is required.

These tests will be completed by December 31, 1985.

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