ML20092A421

Forwards Resolution of 830419 SER for Environ Qualification of safety-related Electrical Equipment

ML20092A421
Person / Time
Site:	FitzPatrick
Issue date:	06/15/1984
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
JPN-84-36, NUDOCS 8406190196
Download: ML20092A421 (36)

Text

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123 Main Street W'e te P!aens, New York 10601 s

914 681 6200

1. > NewWrkPbwer t :"mn, tv Authority June 15, 1984 JPN-84-36 Director of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No.2 Division of Licensing Sub]ect:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Resolution'of Safety Evaluation Report for Environmental Qualification of Safety-Related Electrical Equipment

References:

(a)

NRC letter, D.B. Vassallo to J.P. Bayne dated April 19, 1983.

(b)

PASNY letter, J.P Bayne to D.B. Vassallo dated May 20, 1983 (JPN-83-45).

(c)

NYPA letter, J.P. Bayne to D.B. Vassallo dated June 6, 1983 (JPN-83-52).

(d)

NRC letter, T.A.

Ippolito to G.T. Berry dated June 8, 1981.

Enclosures:

(1)

Resolution of Specific TER Qualification Deficiencies for the James A.

FitzPatrick Plant (2)

Resolution of Additional Qualification Deficiencies for the James A. FitzPatrick Plant (3)

Summary of Methodology for Identifying Electrical Equipment Within the Scope of 10 CFR 50.49

Dear Sir:

Reference (a) contained a Safety Evaluation Report (SER) regarding environmental qualification of safety-related electrical equipment

. tor the James A. FitzPatrick Nuclear Power Plant.

The SER included a Technical Evaluation Report (TER), prepared by Franklin Research Center, which noted a number of deficiencies in the qualification documentation for safety-related electrical equipment with a potential for exposure to harsh environments in the FitzPatrick

. Plant.

8406190196 840615 PDR ADOCK 05000333 l

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ThbiproposedresolutionforeachoftheidentifiedTERdeficiencies 4

Mknich are summarized in Enclosure 1) and the present status of l1y qualification were discussed with members of your staff at a meeting held in Bethesda, Maryland'on March:30, 1984.

Additional qualification deficiencies were-ident'ified by the Authority, and

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-their resolution was also discussed Yith your staff.

These items are summarized in Enclosure (2')xt'o thi's letter.

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'q 7.,1s'Furtheridiscussions during the meetingfaddressed the Authority's

?f 1 3 program'for complying with the requirements of 10 CFR 50.49,

• Environmental-Qualificatioa of Electric Equipment Important to

, Safety for Nuclear' Power Plants."

Specifically, the Authority's

'I methodology for identifying JAP equipment within the scope of

>10 CFR 50.49 and' qualification methodology were discussed.

'((

,) T Enclosure-(3) summarizes the methodology used for the identification

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fbf' equipment within the scope of 10CPR50.49.

The equipment listing 374],gresultedfromtheapplicationofthismethodology.'49(Referenceb)

) contained in the Authority's response to 10 CFR 50.

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.g y74)At the same meeting, your staff requested confirmation of the 4;

following items:

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that all design-basis events which could result in a

./f' $ l potentially harsh environment, incl'uding,fl,ooding outside

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i containment have been identified; gr'

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4 2.Lthat the harsh environment assumed for purposes of 6

qualification' includes the worst case conditions.

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LThe Authority has identified all design-basis eventsiwhich could result in a'potentially harsh environment, including flooding due to a high-energy line break 1 (HELB) outside containment.'

The Authority bas also previously-identified primary containment LOCA and Reactor Building HELB profiles for pressure and temperature.

The bases and aasumptions for these profiles were submitted to the NRC in previous environmental qualification transmittals and approved by^the NRC (Referencei(d)).

The Reactor Building HELB pressure and

protiles were recently updated by Stone & Webster Engineetemperature ring Corporation to reflect the installation of modifications. intended to

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re'ucetthefeffects of postulate'd line breaks _and to account for d

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.recent building structurel changes resulting from fire protection modifications.

The assumptions used in<this updated analysis are 9,

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-t conservative and consistent'With Standard Review Plan, Section 3.6.1

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( NUREG-7S/087).

As discussed at the March-30 meeting, the NRC will prepare and issue U

c a' supplemental Safety Evaluation Report to indicate that the Authority'sLelectrical equipment qualification program, as described in this and' previous submittals, meets the requirements of 10 CFR e

i 250.49 and that the deficiencies identified in the SER (Reference (a)') are resolved'as documented in this letter.

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4 If you have any questions, please do not hesitate to call Mr. J.

A. Gray, Jr. of my staff.

Very truly yours, S

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ay'h secutive Vi President Nuclear Generation cc:.M.L.

Doerflein,.

' JAP Resideist Inspector U. S. Nuclear Regulatory ~ Commission P. 0. Box 136 Lycoming, New York 13093 e

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t ENCLOSURE 1 REVIEW OF SPECIFIC ~TER QUALIFICATION DEFICIENCIES

.FOR THE JAMES A'. FITZPATRICK PLANT t-l l

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-RESOLUTION OF SPECIFIC IEP QUAL IFICAll0N DEFICIENCIES Component Iype: CABLING, IERMINAL BLOCKS, SPL ICES QUALIFICAIION TER NO.

JAF COMPONENI ID IER DEFICIENC;ES RESOLUTION SIA]US 111 Terminal Block Document ed evidence of qualification.

Additional test documentation has IN PROGRESS (C.E. EB-5)'

been obtained and supplemented by analysis.

The existing installation of these terminal blocks in junction boxes in the JAFNPP Reactor Building is presently being modified to reflect the tested configuration. This work will be cumpleted by March, 1985 Io increase the level of qualification of electrical junctions locat ed inside primary containment, the Aut horit y is replacing all terminal blocks with splices qualified to NUREG 0588, Cat. I requirements. Ihis work will be completed by March, 1905.

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Cables I

142 Rockbestos RSS-6-104 Adequate similarity between installed Additional test documentation obtained and supplemented by alhas been QUALIFIED 143,144 Eaton Dekoran equipment and test specimens.

nalysis.

145 Anaconda FR-EP Also, cable traceability and similarity 147 BIW No. 14538-H-006 documentation has been established.

Plant specific qualification reports LRYVfgg0588, Cat. I requirements are

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Page 2 of-2 RESOLUIION Of SPEClfl0 IE R QU AL !flCAIlON DEflCIE Nf.lES

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. Component Types (AeLING, IERMINAL. BLOCKS, SPLlEES (Cont.)

QUAllflCATION

' IEH NO.

JAf COMPONENT 10.

IE N DEflCIENCIES

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' _RE S0L ul f 0N STATUS 161-

' Insulated Wire' funct ional test. criteria Ihe Authorit y t akes no credit for the QUAtiflED connector (dielectric strength) insulating capabilities provided by the (i&B Iefzel) insulated sections of these connectors.

The required dielectric strength is pro-vided by properly installed and configureo terminal boards and insulated splices.

Loss of dielectric strength of the Terzel insulation on the wire connector will therefore, not prevent the safety-related function of the electrical circuitry.

Therefore, no functional testing for dielectric strength is required by the test program.

148 Vulkene Cable Adequate similarity between in-Additional test dccumentation has been QUAliflED (CE Co.)

stalled equipment and test obtained and supplemented by analysis.

specimen.

Also, component traceability and similarity documentation has been established. A plant specific qualifica-tion report to DDR Cuideline require-ments is on file.

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- d Page 1 of 2 RES0tHIION'0F SPECiflC IER QUAL IFIC ATION DEFICIENCIES Component Type: ELECIRICAL DISIRIBul10N EQUIPMENI QUALIf!CAIION IEN NO.

JAF COMPONENI ID TER DErlCIENCIES HE50tHil0N SIAIUS 38 71ACA)

Documented. evidence of qualification.

An analysis has shown that a poten-.

NOI APPLICABLE 39 71PI-71ACA) tial f ailure of this equipment (trans-197 71PI-71ACB3 formers and 120VAC distribution 198 71ACB) penals) during or subsequent to post --lat ed accidents will.not prevent the funct ioning of any safety-related equipment.

This equipment is, there-fore, nct within the scope of 10CfH56749.

104 BMCC-2 Documen'ed evidence of qualification.

Ihe New York Power Authority, as a IN PROGRESS 105,106 HCC-165,-153

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member of a joint utility group of 15%,-163 BWR owners, has contracted with 107 NCC-164 General Electric Co. to qualify the -

190 DMCC-1,3 CE Series IC7700 motor control centers (MCC).

Phase I of this program demonstrated successful qualification to an enveloping utility environment for 15 major HCC components. Phase

!! of the program addresses plant-specific qualification. A final qualification' report for the James A. FitzPatrick equipment la scheduled to be completed by August, 1984.

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1 Page 2 of 2 RESOLit. ION Of' SPECIFIC TER QUALIFICAIION DEFICIENCIES Consonent'iypea [LECIRICAL DISTRIBUT ION EQUIPMEN T ( Cont. )'

QUAllflCAll0N IER NO.

JAF COMPONENI ID IER DEflCIENCIES HE$uttill0N STATUS 108 1.-16 Documented evidence of' qualification, The New York Power Authority is IN PROGRESS 109 L-15 presently' engineering enclosures around the entire switchgear units.

Ventilation equipment powered from the emergency buses will maintain the enclosure t emperat ure, pressure and relative humidity at normal levels during all pestulated accident conditions. An analysis will be made of aging due to normal environment and to radiation during postulated accident conditions.

Enclosures and associated qualifica-tion reports are scheduled to be complete by March, 1985 150 Circuit breaker Documented evidence of qualification.

This equipment item has been relocated NOT APPLICABLE (G.E IHQB1120)

Temperature / pressure profile envelope. to a mild environment and is, therefore, not within the. cope of 10CFR50.49.~~-

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'RESOLU1104 Of SPECIFIC IER -QUAT tr t CAT ION DEFICIENCIES Component Types (fjtCIRICAL PfMEIRATIONS.

QUALiflCAll0N IEH NO.

'JAF COMPONENT 10

.ILR DErlCIENCIES RESOL UI l0N SIAIUS 47 X-1010 Similarity between. equipment and test Additional test documentation has QUAliflED X-103A,9 item.

been obtained, which has been supple-X-104D

' Aging degradation.

mented by analysis. Also component X-109 Qualified life.

traceability and winitarity document.

X-1100 Spray criteria.'

ation has been established. A plant Radiation criteria.

specific qualification report to' DOR Guideline requirments.is on file.

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.Page 1 of 7 RESOLUTION Of SPECIFIC IER QUALIFICAIION DEFICIENCIES Component Type: MOIORS QUAtlflCATION IFR NO.

JAf COMPONENT ID IFR DEFICIENC5ES HESutui10N-SIAIUS 42 27P-11A,8

' Documented evidence of qualification.

Ihese are sample pumps associated with IN PROGRESS 199 the original gas analyzer equipment for containment. hydrogen and oxygen.

Refer to IER items 44, 45, 155, 166, and 167 in the Gas Analyzers Section for the resolution of qualification defaciencies for these items.

A fully qualified replacement hydrogen analyzer meeting NUREG 0588, Cat. I rey sirements was installed in August, 1983 A fully qualified replacement oxygen analyzer meeting NUREG 0588, Cat. I requirements is scheduled to be installed by. larch, 1985.

40 10P-3(A-D)

Documented evidence of qualification.

Additional test documentation has QUAL! fled 49 14P-1A,8 been obtained which has been supple-mented by analysis. Also component similarity documentation has been established. A plant specific qualification report to DDR guideline requirements is on file.

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.4 Page. 2 of 2 RES0 Lull 0N OF SPECIFIC IER QUALIFICAff0N DEFICIE'NCifS Component Types M0f0RS (Cont.)

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QUAttr1 CATION-SIAIOS RE SOL U T I ON IER NO.

JAf CONPONENT ID IER DEflCIENCIES l

53 66UC-22(A-X)

Docum.ented evidence of qualification.

Fully q.sall fied replacement motors' IN PROGRESS have been ordered and will be in-1 stalled.by March, 1985.

Other cor. trol panel coeponents.for these motors were removed from plant areas, which could experience harsh environ-ments due to postulated accidents.

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.Page 1 - of 2 HESOLull0N' Of SPECIFIC IER QUALIFICAIION-DEf'CIENCfES I

Component lype POSli10N SWITCHES /POSIllHN INDICAIORS QUAllflCATION' IfR NO.

JAF CONPONENI ID TER DEflCIENCIES' KESGLUll0N -

STATUS 25 27PNS-101A,8 Documented evidence of qualification.

These position switchea.have been QUAllflED replaced.with position switches fully.

27 27PNS-132A,0 qualified to NUREG 0588, Cat. I r e.'

28 29PNS-86A-D 29 66PNS-100A1,A2, quirements. Plant specific qualifi-cation reports are on;flie.

01,82-66FNS-101A1,A2, 81,82-33,168 27PNS-147,146 37 27PNS-103A,8 169,170 27PNS-145 171,172.

27PNS-144 173,174 27PNS-143 175,176 27PNS-142 177,178 27PNS-141 180 27PNS-131,112,

-115,116 181 27PNS-117,118 182 27PNS-113,114 30 23PNS-18 Documented evidence of qualification.

Based on an evaluation of system and NOT component functions during postulated APPLICAELE 32 23PNS-LS) accidents, it has been determined that 35 02-2PNS-40 these components are not within the 36 02-2PNS-J9 scope of 10CfR50.49. ~~~

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RESOLUTION Of SPECIFIC'IEN QUALIFICAftHN'OEFICIENCIES Component Type POSITION SWIICHES/ POSITION INDICATORS (Cont.[

T E R NO.' ' jar COMPONENT ID TER DEflCIENCICS gf;S7.UTION

. QUALIFICATION STATUO 31 23PNS-LS4

' Documented ew idence of quali ficat ion.

' 1his posit ion swit ch.is scheduled to IN PROORESS be. replaced with a fully qualified.

posit ion swit ch by March,',1985 157 02VME-11(A-L)-

' 164 02VHY-71(A-L)

Document ed ew idence of quot ificat ion.

A joint Ornop of utility owners has IN PROGHESS'.

200 Hardline contractes ith Babcock & Wilcox to Signal Cable t est a complet e system to i;3 REG 0588,

'(SRV Acoustical Cat. 1 requirements. The test pro-Monitors System gram has been completed and the Components)

Authority has reviewed the preliminary test data. A final report is presently being prepared.

The Authority will modify.the syst em to time t est ed configuration by March,'1985 h

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s 1 Page 1 / of 3 RESOLull0N OF SPE CI'f l 0 IEN QUALIFIC4fl0N DEFICIENCIES.

Component'lypt - PRESSURF, DiffERENilAL PRE SSURE, A Lftil INSTRUMENIATION IER NO.

JAf COMPONENT ID IER DEFICl[NCIFS QisALIFICATION RES0tuTION STAIUS 54,55 10-PS-120(A-H)

Documented es idence ~ of qualificat ion.

Additional test documentation has QUALIFIED 60,61 02PS-128A,8 Adequate similarity.

62,63 02-3PS-52(A-D)

Aging degradation.

been obtained, which has been supple-64,183 Qualified Ilfe.

mented by analysis. Also component traceability and siellarily document-83 10PS-100(A-D)-

Peak temperature / pressure & duration.

a4 10PS-101(A-D)

Radiat ion crit eria.

at ion has been est ablished. A plant-85 10PS-119(A-D) speelfic qualificat ion report t o DOR.

86,87 02-3 TIS-72(A-D)

Guideline requirements is on fila.

08,89' 02-JLIS-83A,8 99,92 02-3LIS-101(A-D) 95 23LS-91A,B 115 25fS-78 114,115 14FIS-45A,B 128 14PS-44A,8 129 14PS-4fA B 132 13DPIS-83,84 113 02-DPIS-116(A-D) 02-DPIS-117(A-D) 02-DPIS-118(A-D)-

02-DPIS-119(A-D) 134 0$PS-12(A-D) 135 23PS-86(A-D) 137 23PS-68(A-D) 188,189 23DPIS-76,77 191 02-3LIS-57A,8 192 02-5LIS-50A,8

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Q Page 2 of 3 RESOLUll0N OF'SPECifl0 IER QUALiflCAIION DEFICIENCIES Component Typer PRESSURE, Dif f ERENil AL PRESSURE, a LEVEL INSTRUMENTAll0N (Cont.)

QUALIFICAll0N SIAIUS RESului!ON 1ER NO.

JAf COMPONENI 10 IER DEF ICIENCIES

_IN PROGRESS

.These pressure transmitters are 56,57 02-3PI-178(A-D)'

Aging degradation.

scheduled to be replaced with fully Qualiified life.

qualified components by March, 1985.

Radiation criteria.

NOT Based on an evaluation of system. sad Documented evidence of qualificat ion.

component functions during postulated APPLICABLE 58,59 06PI-53A,B,C 94 23L1-2010 Aging degradat ion.

accidents, it has been determined that 96 23FI-82 Qualified life, these components are not within the lemp./ pressure envelope and duration, scope of 10EFR50.49.

140 1315-1 Radiation criteria.

QUAL! fled 65 14PI-38A,B Dorumented evidence of. qualification.

Ihis equipment has been replaced with fully qualified components. Plant 68 27PI-114 specific qualification reports to 95 0 3t S-2 31( A-0)

NUREG 0588, Cat. I requirements are on 97,100 10fl-40A,B file for all units.

98,101 10fi-109A,0 102,103 10ft-97A,B 99 27FI-103A,8 90 02-3 L I I S-7 3 Documented evidence of qualification.

These instruments are scheduled to be IN PROGRESS replaced with fully qualified com-Aging degradation.

ponents by March, 1985.

Qualified life.

. and duration.

Iemp./ pressure envelope Test sequence and functional testing.

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Page 1 of 1 RESULUIION OF SPECIFIC IER QUAL IFICAll0N' DEFICIENCIf 5 Component Types. PRESSURE, DiffERENilAL PRESSURE,-& LEVEL INST RUNE N T A T I ON (Cont.)

.QUALIFICAllON TER NO.

JAF CONPONENI ID TER btFICIENCIES.'

RES0t t!I t 0N SIAIUS 138 27PS-110A,8 Similarity. with' tested specimen.

Additional test' documentation has'been QUALiflED' Aging degradation.

obtained which has been supplemented Qualified life.

hy analysis. A plant specific.qualif-Temp./ pressure duration.

.ation report'to DDR GuidetinoJrequire-Radiation, ments is on file.

151,152 23LI-203A1,81, Documented ev idence of qualificat ion.

. The qualificat ion test program hos

. QUALIFIED A2,82 been completed. A plant specific 27PI-115A1,81, qualification report to NUREC 0508, A2,02 Cat. I requirements is on file.

'06PI-61A,8 23LI-202A,8

Page 1 of-2 RE50 Lull 0N Of SPEClflC IER QUALIFICATION DEflCIENCIES CAS ANALY/ERS Component Types.. RADIATION HONITORS, QUAllflCATION STAIUS RESutuTION TER NO.

JAf COMPONENT 10 IER DEFICIENCICS IN PROGRESS A3,165 270WA-PA,PB Documented. evidence of; qualification.

These items are the panels which con-tain the containment gas onalyzers (27HAZ-101A.B and 270 AZ-101A,8).

2 The H2 analyzer has previously been replaced and the 02 analyzer will be replaced by March, 1985. See TER Items 44, 45, 166 and 167.

The function of these items is now-NOT Documented evidence of qualification.

being performed by new fully-qualified APPLICAHLE 44,166 27HAZ-101A,8 Analyzer)

Hydrogen Analyzers (27HAZ-102A,8).

(H2 These items will be removed fraw the plant.

IN PROGRESS These analyzera are scheduled to be 270 AZ-101A,0 Documented evidence of qualification.

ful'y-qualifind!, oxygen 2

replaced by new 45,167 (02 Analyzer) analyzers by March, 19u5, documentation has been obtained QUALITIED Test Docustited evidence of qualification.

and supple aer.ieu.. ~/e jy n i s.. ' e 153 27RE-104A,B actfic qualificut'fLn rdport (containment plant sp#

radiation to NUREb 0588, Cat. I requirements det ect or )

is on file.

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'W Page,2,of _2, IER QUAllflCA110N OfflCIENCIES HfSOLull0N Of SPECIfl0

. RADIATION HONif0RS, CAS AN AL Y 7E R S_ ( Cont. ) -

QUAllflCATION Component Type STAIUS RESOL Hi l 0N_

IER DEf!CifNCIES T E R No._

JAf COMPONENT ID Based'on an evaluation of system and

'NOT APPLICABLE functions during postulated Documented evidence of qualification.

component been determined that 17RE-430A B accidents, it had 46 within the these components are nnt

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scope of 10CfR50.49.

QUAllflED Test' documentation has been obtained' Documented ev idence of qualificat ion.

and su3plemented by analysis. A plant-speciftc qualification report.to NUREC 27HAZ-102A,8 155 (Hydrogen 0588, Cat. I requirements is on file.

Analyzer)

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Page-1 of 1 RESOLUTION Cf SPECIFIC IER QUAL IflCAll0N DEf1Clf NCIES' Component lype SOLENDID VALVES QUAtlflCAll0N IER NO.

JAf COMPONENT ID-IER DEflCIENCIES RESOLUTION 5:Alus 71,75 02-2SOV-39,40 Documented evidence of qualification.

These solenoid valves have been re-QUALIfifD 72 2950V-80(A-D) placed with valves fully qualified 81-2950V-86(A-D) to NUREG 0588, Cat. I requirements.

73 6650V-100A,B A plant specific ' qualification report is on file.

195 66SOV-101A,B 76 2750V-101A.H 77,194 2750V-111.112, 78.

-113,114,

-115,116

-117,118

.79 27SOV-131A,8 2750V-132A,8 80 2750V-125A,8 Documented ev idence of. quali ficat ion.

Additional test documentation has QUALIFIED 2750V-135A,0 been obtained, which has been supple-82 27 SOV-120 A,8 mented by analysis. Also component 2750V-121A,B traceability and similarity document-ation has been established. A plant 27SOV-122A,0 27SOV-123A,8 specific qualification report to DDR Cuideline requirements is on file.

193 27SOV-124A,B 2750V-119A,B

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Page 1 of. 2 Qtl At lF ICAll0N DEf f CIENCif S RES0tilTION Of SPECIFIC IER IEMPERAluRE INSIRUMENIAl!ON QUAltflCA110N Component types SIAIUS RE SOI.Ul l 0N IER DEF ICIENCIES JAf COMPONENT 10

_IER NO.

IN PROGRESS these temperature sensors are

' Documented evidence of qualificatiun.

scheduled to be replaced with fully 68tE-102,103, qualified units by March, 1985.

116 68tE-105.106 117 27 RID-112 27 RID-101A,H,C,0 11B and NOT APPLICABLE.

Based on an evaluation of system functions during postulated-Documented evidence of qualification.

component it has been determined that 120 131L-38A accidents, these components are not within the.

13fE-117A C.E 122

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scope of 10EFR50.49.

QUAllflED Additional t est documentation has Documented evidence of qualification.

been obtained, which has been supple-mented by analysis. Also component 123 13fE-100A,D and similarity document-131E-1060 t raceabil it y Plant 131E-1000,106A,C ation has been established.

121 124 131E-106D specific qualification reports to DDR 125 13fE-1000 Guideline requiremente are on file.

126 23lE-114A,0

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.i Page. 2 of 2 RESutull0N OF SPECIFIC IER ut?AL IF IC AIION DEF ICl[NCIES Component lypes TEMPERAIURE INSTRUMENIAll0N (Cont. )

.QUALiflCATION STAluS RE50LHll0N

' IEN NO.

JAF COMPONENI ID TER DEFICIENCIES Additional test documentation has' QUALIFIED 112' 02iS-121.(A-D)

Aging degradation.

been obtained, which has been supple-02I5-122 (A-D)

Quali fied. li fe.

0215-12) (A-D)

Temp./ pressure exposure and duration.

mented by analysis. Component trace-ability and -similarit y document ation 02iS-124 (A-D)

Radiation, has been est ablished. A plant specific qualification report to DOR Guideline requirements is on file.

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a Page 1 of 1 RESOLU110N Of SPECifl0 IEH QUAllflCAIION DEflCIENCIES Component Types VALVE Hol0H ACIDAIORS QUAllf! Call 0N STATUS RES0tCTION s

TER NO.

.) Af COMPUNENI 10.'

IER DfflC.cNCIES Additional test documentation has QUALiflED Documented evidence of qualification.

been obtained, which has.been supple-1 10HOV-25A,B-156 13HOV-15 Aginq degradation.

mented by enalysis. Also component 6,7 14HOV-11A,8 Peak temperature and it s duration, traceability and similarity document-2,179 10HOV -31 A,8 Qualified life.

aticn has been established. A plant.

14HOV-128 Qualified life.

specific qualification report to DDR 17 02HOV-54A,0 Radiation criteria.

Guideline requirements is on file.

Hotors,' torque and limit switches QUAllflED 8,18 2OHOV-94 Aging degradation.

have been replaced ' wit h fully qualified components. Ihe original 20HOV-82 Qualified life.

Radiation criteria.

documentation has been supple-test mented by. analysis including docu-mentation of component traceability and cimilarity. A plant specific qualificat ion report to Dall Guideline requiremente is'en file.

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. o f-3 RESOLHil'ON OF SPECIFIC IER QUAtlFICATION' DEFICIENCIES VALVE' MOTOR ACIU AIORS '(Cont.)

Component Types

'QUALIFICA110N

'STAIUS HES0tull0N IEH NO.

JAf COMPUNENT ID TFR DEFlcifNCIES Add it ional test documentation has

QUAttflED Documented evidence of qualification.

.been obtained, which has been suppla-10,19' 23MOV-58 _

Aging degradation.

mented by analysis.. Also cos onent 23 02MOV-53A,8 e

23MOV-57 Qualified life.-

traceabilit y and similarity document--

Radiation criteria.

ation has been~ established. A plant specific qualification report to 00R Guitteline requirements is on file.

Additional test document ation has Qtl AL iflED 12,13 29MOV-77

.nocumented evidence of qualification.

been obtoined, which has been supple-10MOV-67 Aging degradation.

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~ mented by analysis. Also component Qualified life.

traceability and similarity document-ation has been established.

'A plant to 00R specific qualification report Guideline requirements is on file.

a Similarity between equipment and test Additional test documentation has QUALIFIED been obtained, which has been supple-20 10MOV-18 specimen.

mented by analysis. Also component Aging degradation.

t raceability and similarity document-Qualified life.

ation has been established. A plant specific qualification report to DDR Guideline requirements is on file.

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-page 3 - of 3 RF50tull0N OF SPECIFIC'IEH QU AL If lCAllON DEF I C IE NC IE S Component Typer VALVE MOIOR ACIUATORS (Cont.)

QUAllfl' Call 0N Rf S4t ul lnN STATUS TER NO.

jar COMPONENT 10 TE,R DEFICIENCILS 5,15 2)MOV-19 Documented evidence of qualification.

Based. im an, evaluat ion of system and NOT APPLICABLE 23H0v-17 Aging degradation.

' component functions during postulated i

Qualified life; accidents, it.has been determined that these components are not-within the~

scope.or 10CfR50.49 I

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I ENCLOSURE 2 I

I RESOLUTION OF-ADDITIONAL QUALIFICATION DEFICIENCIES FOR THE JAMES A. FITZPATRICK PLANT I

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Page 1

of' 3' RESOLUTION OF QUALIFICATION DEFICIENCIES NOT ADDRESSED BY TER-Component Type: '

ELECTRICAL DISTRIBUTION AND MISC.. ELECTRICAL EQUIPMENT QUALIFICATTON JAF COMPONENT ID QUALIFICATION DEFICIENCY RESOLUTION STATUS 01-125E-5A, B Documented evidence of The plant-specific qualification report IN PROGRESS qualification for this gas train heater and its as-sociated controls was.recently received by the Authority (March, 1984).

This report is presently undergoing. engineering review.

This-review is expected to confirm the report's conclusions.which establish qualification based on the postulated environmental conditions to DOR Guideline requirements.

02-3AU-178 (A-D)

Pressure These components are scheduled to be IN PROGRESS Radiation relocated to a mild environment by.

March, 1985.

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RECOLHilLN OF QUALIFICAll0N DEFICIENCIES NOT ADDRESSED BY TER g4 I

Component type:

ELECTRICAL DISTRIBUTION AND HISC. ELECIRICAL EQUIPMENT (Cont.)

QUAltflCAll0N JAF COMPONENT ID QUALIFICAll0N DEFICILNCY RES0lutinN STAIUS 71HCC-151,152 Documented evidence ar qualificallon.

The New York Power Authoraty, as a IN PROGRESS I

-161,162 member of a joint utility group of l

710HCC-4,6 BWR owne r s, has cont ract ed wit h f

General Electric Co. t o qualify the l

CE Series IC770D motor control centers l

tHCC).

Phase I of thle program 1

demonst rat ed successful quali ficat ion t e, an eaveloping utility environment for 15 major HCC components. Phase II l

of the program addresses plant -

l specific qualification. A final qualification report for the James l

A. FitzPatrick eqaJipment IS scheduled t o be complet ed by August, 1984.

71ACA5 Documented ev idence of qualificat lon.

Two safety-related electrical IN PROCHESS 71ACBS circuits provided power from theno

'71PT-7tACAS power sources will be relocated to a 71PI-71ACB5 mild environment. This work is acheduled to be gerformed by March, 1985 w

o Page 1 of 3 RESOLUT ION Of QUAttflCATION DEFICIENCIES NOT ADDRESSED HY IER Component Type:

ELECTRICAL DISTRIHUTION AND HISC. ELECTRICAL EQUIPMENT (Cont.)

QUALiflCAi!ON JAf COMPONENI ID QUALIFICATION DEFICIENCY RESului10N SIAIUS 711NV-3A, -38 Documented ewidence of qualification.

The New. York Power Aut horit y is' IN PROGRESS presently engineering enclosures around the entire charger-inverter units.

Vent ilat ion equipment. powered from the emergency buses will, main-tain the enclosure temperat ure, pres-sure, and relative humidity at normal levels during all postulated accident environmental conditions.

The effects of radiation are being addressed per the requirements of the 00R Guide-lines.

The enclosureu and qualifica-tion report is scheduled for com-plation by March, 1985.

270WA-HTA.HIB Dncomented evidence of qualification.

These items are part of the old con-IN PROGRESS 27HID-102A1,81 tainment at mosphe r e analyzer system.

-102A2.B2 the Hydrogen analyzer has already IHROUGH been replaced with a fully qualified

-107A1,81

. Hydrogen Analyzer.and sample line

-107A2,82 heat tracang system.

The Oxygen Analyzer is scheduled to be replaced by March, 1985. With the new qualified system in operation, these items will not be within the scope of 10CFR50.T77 I

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Page of

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' Component Type ~

.POSlilON SWIICHES/POSlil0N INDICAIUHS~

QUALIFICAllDN jar COMPONENT 10

-QUAllflCAlinN DEFICIENCY RESOLUTION ST AIUS _

20PNS.82 Documented evidence of quellficat ion.

These. items are scheduler to be IN PROGRESS 20PNS-95 replaced with fully qual fled 20PNS-LS4 position switches by Mal h,

1985,

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Page. 1 of I RE Silltli l 0N OF QUALIflCATION GEFICIENCIES NOT ADDRESSED BY IER -

Component types PRESSUNE, DiffEHENTIAL PRESSURE, AND LEVEL INS T HUMENT AT ION

, - ~,,

QU ALIFICAll0N % d. w

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JAf COMPONEN! ID QUAllflCAlltlN DEIICIENCY HE Sill Ul l0N STAIUS 10PI.120A,8 Documented evidence of.qdalifleatIon.

These componenta are scheduled io be.,

IN, PROGRESS ~

replaced by equipment qualified to

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u-NUREC 0588, Cat. I requirements by March, 1985

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y RESOLull0N OF QUALIFICAIION DEFICIENCIES NOT ADDRESSED RY IEN Component Typer SOLENOID VALVES QUALIFICATION JAF CONPONENI ID QUALIFICATION OFFICIENCY RESOLUTION SIAIUS 03SOV-117 Documented evidence'of. qualification, fest data shows that the valves'are.

jN PROGRESS 0350V-118 qualified to the J.A.FitzPatrick postulated accident environments. A plant-specific report to DON Cuide-line.- requi r ement s is-being. finalized and-is scheduled for completion by July, 1984.

20SOV-03 Documented' evidence of qualification.

These items are' scheduled to be IN PROGRESS 2050V-95 replaced with fully qualified' solenoid valves by March, 1985.

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.Page

-1 of 1 R E Sot.U T ION Of QUAllflCATION DEflCIENCIES NOT ADDRESSED BY.IER Component Type RADIATION MONITORS /CAS ANALY7ERS QUALIFICATION JAf COMPONENT ID QUAllflCAll0N DEflCIENCY RESOLUTION SIAIUS 17RC-50A,8 Radiation criteria.

The existing shielding provided for IN PRGGRESS 17RE-53A,0 these radiation monitors is presently 17RT-53A,6 being evaluated to determine if it is 17RE-431,-432 adequate to protect the subject 17RE-434A.D equipment from sample stream radia-17RI-434A,B tion. This effort and any additional shielding which may be required will 17RE-458A B 1

17RE-463A,0

.be completed by March, 1985.

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.QUAllflCAll0N

.1Af Cf4MPONENI-ID QUALiflCAIION DEflCIENCY -

RE SOL UT ION SIAIUS 16-1 RID.107

' Documented evidence of qualification.

These' items are sche'uled to be'

'IN PROCHESS d

16-1HID 108

. replaced by fully' qualified 681E-201 thru

_ temperature sensors'by March. 1985.

212 (total of~12)

. 6810-301 thru...

310 (total'of 10) 60lE-102,.103 68tE-105, 106

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1 RESOLUTION Of tru At iflCAT ION DEF ICIENCIES NOT ADDRFSSED BY IER Component types

- VALVE ACIUATORS i

QUAllflCAi!ON JAf CUMPONENI ID-QUAtlf lCAlluN Off lCIENCY

. RE S0t til l 0 N

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'SIAIUS 13HOV-16 Documented evidence of qualification.

Additional test documentation t.as QUALiflED been obtained, which has been supple-mented by analysis. Also component traceability and similarity document-ation has been established. A plant specific qualification report to DDR Guideline requirements is on file.

23MOV-14 Documented evidence of qualification.

A new fully-qualified actuator meeting IN PROGRESS NUREG 0588, Cat.

I.

requirements is scheduled to be installed by by October, 1984.

27E/P-103A,8 Documented evidence of qualification.

These electro-pneumatic controllers-IN PROGRESS for flow contruf valves will be relocated to an area which does not emperier+ce postulated harsh environ-ment accident conditions by March, 1985.

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1 ENCLOSURE 3 i

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SUMMARY

OF-METHODOLOGY FOR IDENTIFYING ELECTRICAL EQUIPMENT

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WITHIN THE SCOPE OF 10CFR50.49

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Suemary of! Methodology for Identifying Electrical

'I' Eqdipment Within the Ecope of 10CFR50.49

.1.

Paragraph'(b) (1) -- The safety design basis of safety systema as described in the FitzPatrick FSAR were reviewed along with existing plan emergency operating procedures.

Based on this-freview systems and components required to remain functional'in order to mitigate postulation design basis events were identified.

The environmental conditions at the specific

' location.of the safety-related equipment was then determined.

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, Safety-related equipment determined to experience postulated harsh environments as a result of these events were included in

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-the 10CFR50.49 equipment listing.

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-2.

. Paragraph-(b) (2) - A review of the' electrical elementary diagrams.for the safety-related equipment identified under paragraph (b) (1) was performed.. This review confirmed the application of the original plant design criteria for electrical separation of safety-related electrical equipment and circuit-

-coordination / protection schemes.

As a result, no non-safety

related electrical equipment whose failure under postulated l

environmental conditions could prevent satisfactory i

accomplishment of safety functions were: identified.

3.

Paragraph (b)'(3) - Regulatory Guide l.97, Rev. 2

" Instrumentation...uto Assess Plant and Environs During and e

Following an Accident"'was: reviewed as it applies to Boiling l

Water Reactors (BWR).

Instruments were then identified which l

'were' presently installedfin the FitzPatrick Plant and which meet the required design criteria.

If these instruments required-i environmental qualification (categories.1 and 2), the associated components were included in the 10CFR50.49 component listing.

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