ML18082B333

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Forwards Addl Info Re Util 800918 Environ Qualification Review Per NUREG-0588.Encl Provides Summary Listing in Terms of Safety Significance for Category 1.1 & 1.2 Items Re LOCA & Main Steam Line Break Qualification Profiles
ML18082B333
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/01/1980
From: Mittl R
Public Service Enterprise Group
To: Miraglia F
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8010160516
Download: ML18082B333 (7)


Text

.

e PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 October 1, 1980 Director of Nuclear Reactor Regulation

u. s. Nuclear Regulatory Conunission Washington, D. c.

20555 Attention:

Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:

ADDITIONAL INFORMATION ENVIRONMENTAL QUALIFICATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION Public Service Electric and Gas hereby submits, in the en-closure to this letter, a summary listing in terms of safety significance of those Category 1.1 and 1.2 items identified in our submittal of September 18, 1980.

In response to the September 26, 1980 telephone conversation with members of your staff, this list addresses compliance with NUREG-0588 and additional action to be taken.

In some cases compliance with NUREG-_0588 not required since plant safety would not be affected by equipment failure and sufficient information is available for the operator.

In such cases, pro-cedures have been revised to advise the operator.

In other cases, additional information to demonstrate compliance with NUREG- 05_88 will be submitted by November 1, 1980.

The comments section indicates the actions that will be taken if this additional in-formation does not show compliance with NUREG-*0-5 8~. The Detailed information can be found in our September 19, 1980 submittal in the justification section (Section 3) for each item.

CENTENNIAL OF LIGHT

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1879 1979 95-2001 (300M) 1-79

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Mr. Frank J. Miraglia, Cbief Licensing Branch 3 October 1, 1980 Page 2 In addition to the summary listing, we have attached additional clarification regarding NUREG-0588 compliance as described in Section 5 of our September 19, 1980 submittal.

Should you have any questions in this regard, do not hesitate to contact us.

Attachment CC:

Mr. Leif Norrholm Very truly yours, r:~K R. L. Mittl General Manager -

Licensing and Environment Engineeiing and Cbnstruction Salem Resident Inspector

SALEM GENERATING STATION UNIT NO. 2 ENVIRONMENTAL QUALIFICATION REVIEW Compliance with NUREG-0588 The follow1ng information provides a more definitive statement on compliance with various sections of NUREG-0588.

1.1 LOCA Qualification Profile The Salem LOCA profile was calculated by Westinghouse utilizing the methodology described in WCAP-8312A for calculating LOCA mass and energy release. Appendix A to NUREG-0588 indicates that this is acceptable to*

the Staff. The COCO model described in WCAP's 8327 and 8936 was used to establish the containment pressure and temperature time-dependent varia-tions following a LOCA.

Although this model has not received generic approval from the Staff, the NRC has found it acceptable on a number of plants including Salem as indicated in the Safety Evaluation Reports.

We believe that this is an acceptable approach in meeting the NUREG-0588 LOCA guidelines.

1.2 MSLB Qualification Profile The Salem MSLB profile was calculated by W~stinghouse utilizing the methodology described in WCAP 8822 for calculating the MSLB mass and energy release. The COCO model described in WCAP's 8327 and 8936 was used to establish the containment pressure and temperature time-dependent variations following an MSLB.

Although this model has not received generic approval from the Staff, the NRC has found it acceptable on a number of plants including Salem as indicated in the Safety Evaluation Reports.

The Salem information and methods were described in FSAR responses to Questions 5.62, 5.63, 5.82, 5.83, 5.84, 5.85.

In addition the NRC Staff themselves performed a confirmatory MSLB analysis utilizing their assumptions and the Contempt code for Salem.

The review of equipment qualification was done in accord with the values determined by the NRC and indicated in the Safety Evaluation Report.

The MSLB qualification profile is in compliance with NUREG~0588 requirements.

i.. 1.3 Chemical Spray The Salem review and requirements address chemical sprays in the manner prescribed by NUREG-0588 including single failure.

1.4 Radiation Doses The Salem review and requirements address radiation doses in the manner prescribed by NUREG-0588.

This includes the proper source tenns for both inside and outside containment and beta doses per the applicable requirements.

Items 1.5, 2, 3, 4 and 5 have been adequately addressed in our 9/19/80 sub-mitta 1.

~

A

'J SALEM GENERATING STATION UNIT NO. 2 ENVIRONMENTAL QUALIFICATION REVIEW:

NUREG-0588

SUMMARY

TABLE - ITEMS IDENTIFIED IN SEPTEMBER 19, 1980 REPORT ITEM NO.

1.lA FUNCTION Main Steam Atmospheric Relief Valve Control Equipment NUREG-0588 COMPLIANCE Not required.

L_,

COMMEN°TS Analysis indicates that equipment failure does not pose a safety hazard.

,:J------------------------------------------------------4

{

J 1.lB 1.lC 1.10 Main Steam Isolation

1. Solenoids (MS7, MS167, MS18)
2. PAT (MS18)
3. Control Switch (MS167)
4. Limit Switches (MS7)

Residual Heat Removal

l. E/P (RH18, RH20)
2. Flow Switches (RH29)

Containment Pressure Vendor supplying addition~l supporting data for review 11/1/80. Information avail-able provides reasonable assurance that solenoids will operate for completion of function.

Not required.

Not required.

Vendor asked to supply addi-tional qualification data for review 11/1/80.

Not required - Vendor is supplying additional data for review 11/1/80.

Not required.

If review indicates data is not in full com-pliance, the solenoids will be replaced with fully qualified NP series solenoid valves by

  • Junt 1982
  • Vendor delivery time about 6 mon hs.

Engineering judgment indicates tha"t....

equipment will operate.

Circuitry has been modified to eliminate potential misoperation causing safety problems.

Administrative control.

Procedure Modification.

Replacement with qualified limit switches by 1st refueling. Vendor delivery is on order of 4 months.

Administrative control.

Procedure modification.

Additional qualification data If review indicates data is not. in full complianc has been requested for 11/1/80 the pressure transmitters will be replaced by review.

June_._ 1982.

Vendor delivery is expected

.. 1st gtr *. - 1982

  • Procedures will be modified to alert operator of potential misoperability, how-ever, information available provides reasonable assurance that transmitters will operate to perform safety functions.

.. ~

ITEM NO.

1.1E 1.1F 1.1G 1.lH 1.2A

1. 28 FUNCTION Containment Isolation
1. Flooded MOV's and Solenoids (Inside Containment).
2. Flooded Limit Switches (Inside Containment).
3. Limit Switches Outside Containment.

Boron Injection Tank Valves (SJ78, 79, 108) Limit Switches Fan Cooler Unit Control

1. Solenoid Valves
2. Flow Controllers Excore Neutron Detectors Hydrogen Analyzers Containment Temperature Page 2 NUREG-0588 COMPLIANCE COMMENTS Yes except for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> opera~

Analysis demonstrates that devices perform their-bility which under these cir-function prior to flooding and no safety hazard cumstances is not required.

is created once devices are flooded.

Yes except for flooding Vendors asked to supply additional qualification Vendor has been requested to supply supporting info to confirm qualification.

Review for 11/1/80 Vendor will supply support-ing data for review 11/1/80.

Information available pro-vides reasonable assurance that solenoids will operate to perform function.

Vendors requested to supply additional qualification data for review 11/1/80.

Not required.

Not required.

Not required.

Procedure Modification.

Procedure Modification. Replacement with qualified limit switches by 1st refueling.

Vendor delivery is approximately 4 months.

If review indicates data is not in full com-pliance, the limit switches will be replace~

by Sept. 1, 1981

  • Vendor delivery is on order of 4 months~ Procedure modification will be in-stituted. Devices are located in area where available data provides reasonable assurance of operability.

Procedure Modification. Solenoid~ will be replaced with fully qualified NP series solenoid valves by 1st Refueling. Vendor delivery is on order of 6 months.

Procedure Modification. Circuitry will be re-designed and/or components replaced with suit-ably qualified devices by 1st Refueling.

Analysis in9icates that equipment failure does not pose a safety hazard.

Procedure Modification.

Procedure Modification.

ITEM NO.

1.2C

1. 20
1. 2E FUNCTION Incore Thermocouples Containment Radiation Containment Humidity NUREG-0588 COMPLIANCE Not required.

Not required.

Not required.

Page 3 COMMENTS Existing procedures are adequate.

Procedure Modification. New qualified monitors to be installed in Spring 1981 per NUREG-0578 commitments.

Procedure Modification.

The remaining items which would be considered as Category 1.1 and 1.2 have been qualified and reviewed per NUREG-0588 requirements except that some devices have not had their aging review completed.

These were identified as group 11.4

  • with adequate justification for continued operation pending completion. A supplement will be submitted 11/1/80 pre-senting the results of the review and appropriate maintenance/replacement schedules.