ML20024A889

Submits Info Identifying Electrical Equipment Important to Safety Per 10CFR50.49(g).Also Submits Schedules for Qualification or Replacement of Remaining Electrical Equipment

ML20024A889
Person / Time
Site:	Oyster Creek
Issue date:	06/23/1983
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 IEB-79-01B, IEB-79-1B, NUDOCS 8307010143
Download: ML20024A889 (13)

Text

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OPU Nuclear Ngg gf 100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:

June 23, 1983 Mr. Dennis M. Crutchfield, Chief Operating Reactors Brcnch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Subject:

Oyster Creek Nuclear Cenerat.ing Station Docket No. 50-219 Environmental Qualification of Safety-Related Electrical Equipment (10 CFR 50.49)

In accordance with 10 CFR 50.49(g) GPUN is supplying the following information to " identify the electrical equipment important to safety within the scope of Section 50.49(b) that is already qualified, and to submit schedules for either the qualification or replacement of the remaining equipment that is important to safety as defined in 10 CFR 50.49(b)." 10 CFR 50.49(g) requires each holder of an operating license issued prior to February 22, 1983 to respond by May 20, 1983. On May 18, 1983 in our phone conversation with the NRC Project Manager for Oyster Creek Nuclear Generating Station, we requested an extension of our response.

1) Scfety kelated Electrical Equipment GPUN report dated November 1, 1980 which was transmitted to you in response to IE Bulletin 79-01B, lists the safety related electrical equipment already qualified or requiring environmental qualification at Oyster Creek Nuclear Cenerating Station.

Justification for Continued Operation (JCO) with unqualified equipment was also transmitted by the November 1, 1980 letter. Subsequently, an updated JC0 was submitted by our March 16, 1983 letter.

Our letter dated October 23, 1981 concerning the subject matter also lists electrical equipment relative to backfit or modification in compliance with NUREG-0737 sections.

7hh 0

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GPU Nuclear is a part of the General Public Utilities System

We have recently added the torus vacuum relief transmitters (PT-52 &

IP-12) and dif f erential pressure switches (DPS 66 A & B) to the equipment qualification list.

System Component Evaluation Work (SCEW) sheets along with justification for continued operation of these items are attached. As it was indicated in our letter dated March 16, 1983, GPUNC plans to complete replacement or qualification of unqualified equipment or subcomponents by the end of the Cycle 11 refueling outage (the second refueling outage af ter March 31, 1982).

Installation of the environmentally qualified equipment, as required by NUREG 0737 will also be completed by the end of the cycle 11 outage.

Also attached are the SCEW sheets for the following NUREG 0737 items which have already been installed:

II. D. 3 Direct Indication of Relief and Safety Valve Fosition II.E.4.2 containment Isolstion Dependability We are in the process of modifying the Standby Gas Treatment System.

SCEW sheets for electrical equipment in this system will be transmitted to you prior to the modification becoming operational.

2) Non Safety Related Electrical Equipment JCP&L/GPU letter dated October 5, 1979 in response to IE Information Notice 79-22 states that our evaluation of interactions between non-safety systems and safety systems did not identify any adverse impact which would increase the consequences of any accidents analyzed in the FDSAR.

In addition, GPUN plans to conduct verification of proper selective coordination of protective devices or circuit breakers and fuses on vital buses to ensure that an electrical fault developed in non-safety system due to harsh environment will not be transmitted to the safe shutdown systems. This work will be conducted as part of the evaluation for the Fire Protection Program (10 CFR 50 Appendix R).

Isolation of the reactor protection system from non-safety systems was also reviewed by the NRC staff during Systematic Evaluation Program (SEP) for Oyster Creek Nuclear Generating Station (SEP Topic No.

VII-1A).

3) Certain Post Accident Monitoring Equipment (R.G. 1.97 Rev. 2)

As described in our October 23, 1981 letter, four new isolation valves will be installed to meet the Post Accident Sampling capability requirement.

These are solenoid valves to be supplied by Valcor.

Engineering Corporation. Installation of these valves will be completed within nine months following the Cycle 10 refueling outage.

Qualification information will be incorporated 'into the SCEW sheet at that time.

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4) Proprietary Information l

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Your letter dated March 30, 1983 requested GPUN to indicate if any portions of the previously submitted information require proprietary protection. As we indicated in our March 16, 1983 letter, review of our previously submitted information indicates that none is clacsified as-proprietary.

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Very truly yours, Vice President and Director Oyster Creek i

1r cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.

19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 t

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l Addendum 1 to Chapter 7 of March 16, 1983 Submittal (Justification For Continued Operation) i

51. Torus Vacuum Relief System a.

Pressure Transmitters IP-12* and PT-52*.

Both transmitters provide diverse torus pressure indication to the control ro om.

They are installed in different locations outside the drywell/ torus a re a. Also, these transmitters do not perform any automatic safety func tion.

b.

Pressure Switches DPS-66A* and B*.

These switches are used to control the air-operated Reactor Building to Torus Vacuum Breaker valves V-26-16 and 18, respectively. If these switches should feil, the control room operator can manually operate the valves by a' control switch at the 11F panel. Both V-26-16 and 18 will fail open upon loss of either power and/or air, and regardless of the control switch position.

52.

Direct Indication of Relief and Safety Valve Position The basis for the qualification of the valve position indication systems will be the results of the Owner's Group Valve Monitoring Systems Tests. It is expected that the environmental qualification requirements of NUREG 0737, Item II.D.3 will be met. These systems are not required for a large LOCA.

If a system should fail, there are other indications available to the operator to determine that a valve has lif ted.

In the case of a relief valve lifting, this would be indicated by an increase in the torus water level. For a safety valve lif ting, the indications would be an increase in the containment sump level and an increase in drywell pressure.

Equipment that is not required to mitigate the consequences of an accident outside of containment or to achieve a safe shutdown i; that accident. For a break inside containment, asterished items are needed to mitigate the accident; however, the environmental conditions for these asterisked items would be normal ambient co nditione.

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Facility: Oyster Creek Units.

I Rev.

Date:

m'l 5.55 5/W /23 EQUTPMENT DESCRilvrION mOMEW DOCMEE,iTION REF.

Qualification Outntanding Pa rametor Spee!!! cation Qualifiention Specification Qualificatio::

_ Mothod Ito m s System: Torus.Vacuun Relief Oporating 30 Days Duration Note C 3

Test Plant ID No.

PT52*

Time Summary Componen(Formerly PT-1P12)

.rempo rature t:

Test Pressure Transmitter

("F) 77 184 I

3 Summary Manufacturo:

GE/MAC Pressu ro 15 15 1

3 Test (PSIA)

Summary Model Number:

553 llelativo Anbient 95 1

3 Test Ilumidity Functioft: Torus-Drywell

{24 Suman Pressure Chemical Accuracy: Spoc:

Spray Demon:

quired ea,uired' pplicable

1. U 5

Pressure Indication 3.28x10 Note A Note B Note B (Rads.)

Location: R3-R4yRA Aging El. 23'-6" Rx Bldg (Yrs.)

40 Note A I

Note B Note B Flood Level Elev:

Not Not Abovo Flood Loyol:

Yes Submorgence Negligible Required 2

Required Analysis Documentation

References:

Notes:

1. EDS Nuclear Report No. 02-0370-1045.

A.

Not available at this time

2. EDS Nuclear Letter No. 0370-024-NY-013 dated 10/24/80.

B.

This transmitter will be replaced.

3.

G.E. letter #G-EN-0-163 dated 10/16/80 C.

Oyster Creek FDSAR Amend. 68 Indicates that equipment is not required to mitigate the consequences of the accident outside of contain-ment or to achieve a safe shutdown for that accident. For a break inside containment, asterisked items are needed to mitigate the accident, however, the environmental con'ditio2s for these asterisked items would be normal ambient conditions.

Facility: Oyster Creek Unit:

1 Rev. O Date:.5/24/83 SYSTEM COMPONENT EVAI.UATION WOltK SilEET Sheet 5.56 EQUTPMENT DESCRilvrION

- pfNVIRONMENT DOCUMI!,N_'fATION ILE F.

Pa ramotor Specif!callon Qualification Specification Qualification Method Ite m s System:

Torus Vaduun Relic f Oporating 30 Days Duration Note C 3

Test IP-12*

Plant ID No.

Tline Summary Component: Pressure Trans-Temporature mitter (op) 77 184 1

3 Test Manufacture:

Summary GE/MAC Pressu ro 15 15 pgg 1

3 Test Summary Model Numbor:

553 llelativo 1

Test liumidity Am en 95 3

Summan Function: Reactor Bldg. -

{%L-Torus Pressure Chemical Not Not Not Accuracy: Spec:

Spray Demon:

Required Requires Applicable 5

Pressure Indication Itadiation 6.26x10 Note A 1

Note B Note B (Rads.)

L cau n:R2-R3xRF 40 Note A 1

Note B Note B El. 23'-6" Rx Bldg.

(Yrs.)

Flocxl Level Elev:

Not Not Abovo Flood Loyol:

Yes Submergonco Negligible Required 2

Required Analysis Documentation

References:

Notes:

1. EDS Nuclear Report No. 02-0370-1045.

A.

Not available at this time.

-2. EDS Nuclear Letter No. 0370-024-NY-013 dated 10/24/80.

B.

This transmitter will be replaced.

3.

GE letter #G-EN-0-163 dated 10/16/80 C.

Oyster Creek FDSAR Amend. 68

• Indicates that equipment is not required to mitigate the consequences of the accident outside of containment or to achieve a safe shutdown for that accident.

For a break inside containment, asterisked items are needed to citigate the accident, however, the environmental conditions for these asterisked items would be normal ambient conditions.

Facility: Oyster Creek Unit:

'I Rev. O Date: 5/24/83 SYRrEM COMPONI?NT EVALUATION WORK Sill?Er Sheet 5.57 EQUTPMENT DESCRIPTION

-ENVIRONMENT DOCU(1ENTATION IJEF.

Paramotor Specification Qualification Specification Qualification Method, _.

,,,_Ite m s _,,

System: Torus Vacuum Relief Oporating 30 Days Note B Note A Note C Note C Plant ID N DPS-66 A*a3*

Component:

Temporature Pressure Switch (op) 77 Note B 1

Note C Note C Manufacturo: ITT Barton pg (PSIA) 15 Note B Note C Note C Model Number: 277 (W/ Snap Acting Sw.)

IlcIntivo y

liumidity Ambient Note B Hote C Note C T. orus Vacuum Valve Q,)

Functiott:

Breaker Chemical Not Not Not Accuracy: Spec:

N/A Spray Applicable Required Required' Demon:

N/A Scrylco: Signal to Pres,ure 5

Transmitter Itadiation 5.26x10 Note B 1

Note C Note C (Rads.)

Location: R3-R4xRA Aging El. 23'-6" Rx Bldg.

. (Yrs.)

40 Note B 1

Note C Note C Flood Lovel Elev:

Not Not Abovo Flood Loyol:

Yes Submergenco Negligible Required 2

Required Analysis Documentation

References:

Notes:

1. EDS Nuclear Report No. 02-0370-1045.

A.

Oyster Creek FDSAR Amend. 68

2. EDS Nuclear Letter No. 0370-024-NY-013 dated 10/24/80.

B.

Not Available at this time.

C.

This switch will be replaced.

• Indicates that equipment is not required to mitigate the consequences of the accident outside of containment or to achieve a safe shutdown for that accident. For a break inside containment, asterisked items are needed to mitigate the accident, however, the environmental condition for these asterisked items would be normal ambient conditions.

Fac!!!ty: Oyster Crcok Unit:

1 SWE.M CommW WAI.UAMN WOE MU Sheet 10.01 Rev. O Date:

5/25/83 I

N ONmW

! EU AMAN IE EQUll'A1ENT DESCRIFfl0N Q alification Outstanding l'a rameter Specificallon Qualification tec!fication Qualificatlo:1 Method items

_ Direct Indication of Systent: Relief and 'afety S

O mrating i

Plant ID Mve Position Tlino 4 Hours See Note B Note C Note C Note C MS-VE-1 thru 21 Component:

Ten miature Note C Note C 600 Note C 4

Maniifacturo: E'devco n

c Pressu ro 68 Note C Note C Note C (l'SIA) 4 l

l Model Number: 2273AM20 I

l Itclativo l

HunildRy 100 Note C Note C Note C d')

Function: Safety / Relief Valv e Monitoring Cliemical Not i

Accuracy: Spec:

N/A Spray Applicable Demon: N/A Servico: Valve Position 6

Itadiation 5x10 Note C 4

Note C Note C Indication

_)

Location: Inside Contaimnent AC!n3 Note C (Yrs.)

40 Note C 4

Note C j

Flood Level Elev:

None Abovo Flood Level:

Yes Submorgonce Negligible htequired Required Analysis DocumerJation

References:

Notes:

1, GPU \\!eno GP.00380C dated 4/10/80.

A.

2. CR3 Pener -

'akage Calculatfon by Ken Goddard.

B.

Technical Specification 3 3 3.>JC?5L L' ector NRR dated 3/15/78.

C.

Will be qualified by B&W 4.

Oyster 2rement Specification No. 398-2.

VMS Owner's Test Program.,

Facility: Oyster-Creek Unit:

1 Rev.

O' Date: 5/24/83 SYSTEM COMPONEtif EVAI.UATION WOltK SilEET Sheet 10.02 I

ENVIRONMENT

! IX'CU MENTATION llE F.

EQUIPMENT DESCRII*IION Qialification Outsinnding Pa raineter Specification Qualification Spec!fication Qualification h!cthol ite m s Direct Indication of Systein: Relief and Safety Opo rating 4 Hours Note C Note C Note C 3"" N t* B Plant ID No. Valve Position Timo Coml>onent:Line Driver

[cheratiire t

("F) 281 Note C 4

Note C Note C Manufacturo: Unholtz Dickie Pressu ro 68 Note C (psgA) 4 Note C Note C

' Model Number:

U-D 22 CA-2TR ltclative llutnidity 100 Note C 4

Note C Note C Function: : Safety / Relief g,}

Valve Monitoring Chemical Not Accu racy: Spec:

N/A Spray Applicable Demon: N/A Se rvice:

Valve Position 6

I,ndication Itadiation 5x10 Note C 4

Note C Note C (Rads.)

Location: Inside Containment A !DK I!

Note C 4

Note C Note C (Yrs.)

40 Flood I,cvel Elev:

Abovo Flood Level:

Yes Submon;once Negligible None R uired Pe uired Analysis Documerjation

References:

Notes:

1-. GPi' >!c 10 CP.00380C dated 4/10/80.

A.

2. CR3 Penetration Leakage Calculation by Ken Coddard.

B.

Technical Specification 3 3

3. JCP5L Letter to Director NRR dated 3/15/78.

C.

Will be qualified by B&W

4. Oyster Creek's Procurement Specification No. 398-2.

VMS Owner's Test Program i

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Facility: Opter Creek Unit:

1 EM COMI'ONIWf EVA1 UATION Wold SHEET Sheet 10,03 Rev. 0 'Date:

5/24/83 E NVHIONNENT

DCCUMErfrATION ILE F.

EQUIPMENT DESCRIIvf10N Qualification Outstaniling l'a t:nnete r Specification Qualificafton Spec!fication Qualification Mclitod ite m s Direct Indication of System: Relief and' Safety 0;mrathy Plant ID No. Valve Position Time Note C Note C Note C mmon Component:

Temperature

("F) 600 Note C 4

Note C Note C Manufacture, (Coaxial)

Endevco l'ressu ro 68 Note C Note C Note C (p3gA) 4 Model Number: 3075M6 itelativo Safety / Relief Valve ilumidity 199 Note C 4

Note C Note C Function: Monitoring O')

Cliornical Accu racy: Spec:

N/A Spray Not Demon: N/A Applicable Servico: Valve Position 6

Indi, cation Itadiation 5x10 Note C 4

Note C Note C (Rads.)

Location: Inside Containment A ID3 R

(Yrs.)

40 Note C 4

Note C Note C Flood Level Elev:

Abovo Flood Level:

Yes Submergonce Negligible uired P quired Analysis Documertation

References:

Notes:

1. C?E '!e to CP.003 SOC dated 4/10/80.

A.

2. CD Penetration I.eakage Calculation by Ken Goddard.

B. Technical Specification 3'.3

3. JC?!,L 1.etter to Director !!RR dated 3/15/78.

C.

Will be qualified by B&W 4.

Dyster Creek's Procurement Specification No. 398-2.

VMS Owners Test Program.

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FacIJity: Oyster Creek Unit:

'1 O

5/24/83 SYsrEM COMPONP.NT EVAI. uni'!ON WOltK S!!EET

,yg,,g 10.04 Rev.

Date:

1 ENVIRONNENT

! DOCUMENTATION llE F.

EQUIPMENT DESCRIIrflON Q'salification Outsinnding Pa ramelor Specification Qualification 3; ec!fication Qualification Method Itcans Direct Indication of System: Relief and Safety "i"'" I'M 4 Hours Note C See Note B Note C Note C Plant ID No. Valve Position Time Conq>onent:\\TB-NR-108A-E Tchmrature TB-NR-28A-H,J-N

("F) 281 Note C 4

P-R Note C Note C I

Maninfacturo:

Terminal' Block Pressu ro TRW Cinch 68 Note C Note C Note C p3g) 4

- Model Number:

3-542 itelativo Ilutnidity 4

Note C Note C 100 Note C Functio:t Safety / Relief d')

Valve Monitoring Chemical Not Accuracy: Spec:

N/A Spray i

Demon: N/A Applicable 6

ndicat on Iladiallon 5x10 Note C 4

Note C Note C (Rads.)

Location: Inside Containment Al! D3 (Yrs.)

40 Note C 4

Note C Note C Flood Lcycl Ele :

Abovo Flood Level:

Yes Submergence Negligible R uired quired Analysis Documercation

References:

Notes:

1. GPU '!ena GP.00380C dated 4/10/80.

A.

.2. C D Penetration Leakage Calculation by Ken Goddard.

B. Technical Specification 3.3

3. JC?st Letter to Director NRR dated 3/15/78.

C. Will be qualified by B&W

4. Oyster Creek's Procurement Specification No. 398-2.

VMS owners test program.

i

Facility: Oyster Creek Unit:

1 Rev. O Date: 5/24/83 SYSI'E?1 COMi'ONENT EVAI.UATION WOltK Sill?ET Sheet 10.05 ENVIRONMENT

. DOCUMENTATION ILE F.

EQUll' MENT DESCRIIvrION l

Quallfleation Outsinnding l'a rameter Specification Qualification Itec!fication Qualificattor, Melltod ite m s Direct Indication System: of Relief & Safety O mratiM 1 Hour Duration 5

Test i

Plant ID Np. Position Tline Similarity Common Component: Cable-#16AWG Tennporature 281 346 5

Test 2/C twisted &

("F) 4 Similarity Manufacturo: shielded 600V Rockbestos l'a cssu ro 68 130 4

5 Test (l>s[A}

Similarity Model Number: Firewall III igegaggyo ilumidity 100 4

5 Test igg Function: Safety / Relief

'I

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Cliernical Not Valve Monitoring

- Accuracy: Spec:

N/A Spray Applicable Demon: N/A Se rvice: V"alve Position 6

8 Indication Itadiation 5 x 10 5 x 10 4

5 Test (Rads.)

Similarity Location: Inside Containment A IM R

(Yrs.)

40 40 4

5 Test Si'allerity Flood Level 1; lev:

Abo-fo Flood Level:

Yes Submon; onco Negligible Rc uired F uired Analysis Documer,iation

References:

Notes:

1. - GPU \\!caa CP.00380C dated 4/10/80.

A.

2. CR3 ?enetration leakaste Calculation by Ken Goddard.

3. JC?5L Letter to Director NRR dated 3/15/78.

B.

Technical Specification 3.3

4. Cyster Creek's Procurement Specification No. 398-2

5. Rockbestos Qualification Report QR - 1807.

m Facility: Oyster Creek Unit:

1 Rev.

O Date: 5/24/83 SYSrEM COMI'ONENT EVAI.UATION WOltK SIIEET Sheet 11.01 5

l EQUll' MENT DESCRIIFIION ENVmONMENT

! DCCUMErfrATION ILE r.

l'a rameter Specificat!on Qualification.tec!fication Qualificattori Mclliod Iterns Containment Isolation System: Dependability 0;mrating 2 Minutes Duration Plant ID No.

Time See Note B 6

Test Simulated Cable - #12AWG

.I-Component: 600 Volt, 7 "I

Strands 305 340 4

6 Test Manufacturo: Boston Insulated Fig. 1. P 7-;

._Si elotad Wire l's omi to (l'SL1) 3S 130 4

6 Test

- f.fodel Number-12894-H-009 Itclativo 12893-H-007 ilonnidity 100 100%

4 6

Test Function:

12892-H-002 C)

-Siruhted Chemical Not Accuracy: Spec:

N/A Spray Applicable Demon: N/A Senicc:

Control Cables 1.84x10 2x10

,g,g,9 5

6 Test (Rad.s. )

Simulated Location: Inside Containment Aging (Yrs.)

40 40 5

6 Test Rimlnted Flood Level Elev:

fuired Abovo Flood Level:

Yes Submergence Negligible R uired Analysis Documer,'ation

References:

Notes:

1. GPU >!eno CP.00380C dated 4/10/80.

A.

2. CD Penetration leakage Calculation by Ken Goddard.

B.

Oyster Creek FDSAR Amend.68.

3. JC?SL Letter to Director NRR dated 3/15/78.

4. Oyster Creek Contain:nent Temperature Profile for Environmental Qualification of Equipment prepared by GPU Service Corp.

Control and Safety Analysis, Chapter 2 of 10/28/80 submittal.

5. ED5 Nuclear Letter No. 0370-024-NY-015 dated 11/7/80.

6.

Boston Insulated Wire & Cable Report No. B-915

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