ML20151K652

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Forwards Sser Re Verification in Nonseismic Design Areas,Per 850111 Request.Licensee Program for Assuring Compliance W/ Licensing Criteria in Nonseismic Design Areas Acceptable. Input Re Applicability of UHS Tech Spec & SALP Encl
ML20151K652
Person / Time
Site: 05000000, Diablo Canyon
Issue date: 01/29/1985
From: Rubenstein L
Office of Nuclear Reactor Regulation
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML082390693 List:
References
FOIA-88-192 NUDOCS 8502050109
Download: ML20151K652 (3)


Text

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i JAn 2 01965 i

MEMORANDUM FOR: Thomas H. Novak, Assistant Director for Licensing, Division of Licensing FROM:

L. S. Rubenstein, Assistant Director for Core and Plant i

Systems, Division of Systems Integration

SUBJECT:

DIABLO CANYON UNIT 2 SUPPLEMENTAL SAFETY EVALUATION REPORT INPUT j

As requ(sted by memorandum from Oarrell Eisenhut to Robert M. Bernero dated

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January 11, 1985, enclosed is our supplemental safety evaluation report (SSER) input for Diablo Canyon Unit 2 regarding the verification in nonseismic design areas. This SSER input is based on licensee letters dated November 11, 1984

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and December 7, 1984. We conclude that the licensees Unit 2 program for assuring compliance with licensing criteria in nonseismic design areas is acceptable. We have also included input concerning the applicability of the ultimate heat sink technical specification Unit 2 resulting from the rereview of the component cooling water system.

OrhincI riped by

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..e uiln L. S. Rubenstein, Assistant Director for Core and Plant Systems Disisinn of Systems Integration

Enclosure:

As Stated i

cc w/ enclosure:

R. Bernero F. Miraglia J. P. Knight

0. Parr C. Grimes G. Knighton J. Wermiel H. Schierling

Contact:

J. Wermiel X29462 Distribution Docket File ASB Rdg. File LRubenstein i

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OFFICIAL RECORD COPY

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i SUPPLEMENTAL SAFETY EVALUATION REPORT INPUT DIABLO CANYON UNIT 2 AUXILIARY SYSTEMS BRANCH 4.0 Systems 4.1 Nonseismic Design l

The staff has reviewed the licensees Internal Review Program (IRP) in those areas regarding nonseismic design verification for Diablo Canyon Unit 2 as described by the licensee in letters dated November 11, 1984 and Decerr.ber 7, i

1984 These submittals include those findings identified from the Unit 1 IDVP/ITP in tabular form and a description of the application and resolution of those items for the Unit 2 design. The licensee's program implements Unit 2 design modificctions necessary in a similar manner to those resulting from the Unit 1 IDVP/ITP and as documented in staff SSERs Nos. 18, 19 and 20. The staff has compared its findings from those SSERs and confirms that the concerns have been satisfactorily resolved for Unit 2.

Based on that review, the staff con-cludes that the IRP adequately provides for those Unit 2 changes required to assure compliance with licensing criteria in r.onseismic design areas, and properly incorporates the findings of the Unit 1 design verification program.

4.2 Component Cooling Water System As a result of the rereview of the component cooling water system (CCWS) docu-i mented in SSER No.16, the staff imposed a technical specification on the operation of the CCWS based on the temperature of the ultimate heat sink (Pacific Ocean). The technical specification was incorporated for Diablo Canyon Unit 1, and is also applicable for operation of Unit 2.

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s SALP INPUT Plant: Diablo Canyon Unit 2 1.

Management Involvement and Control in Assuring Quality: Not Applicable 2.

Approach to Resolution of Techr.ical Issues from a Safety Standpoint:

Category 1 3.

Responsiveness to NRC Initiatives: Not Applicable 4

Enforcement History: Not Applicable 5.

Reporting and Analysis of Reportable Events: Not Applicable 6.

Staff (IncludingManagement): Not Appliedble 7.

Training and Qualification Effectiveness: Not Applicable The licensee's information regarding the Unit 2 design verification program adequately addressed staf' concerns.

, s Ytl0 FEB 12 W 4

Docket No. 50-323 MEMORANDUM FOR:

Frank J. Miraglia, Ac. ting Director Olvision of Licensing Office of Nuclear Reactor Regulation FROM:

James G. Partlow; Acting Director Division of Quality Assurance, Safeguards, and Inspection Programs Office of Inspection and Enforc uent

SUBJECT:

DIABLO CANYON UNIT 2 REVIEW Your memorandum dated January 11, 1985, on the above subject requested IE's SSER input on the QA program applicable to the design of Unit 2 (identifying any difference from Unit 1).

This.temorandum is in response to that request, and our SSER input is enclosed.

It reflects an acceptable OA program description since before the construction permit for Unit 2 was issued in late 1970.

Any questions on the above or en the enclosure should be addressed to the QA Branch reviewer, Jack Spraul, on x-24530.

CMTUt Smin Oy:

Jaws t. s

..y James G. Partlow, Acting Director

% 5~850413 nivision of Quality Assurance, Safeguards, J

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/g id Inspection Programs w.

ice of Inspection and Enforcement

Enclosure:

SSER Input cc:

L. J. Chandler, NRR C. I. Grimes, NRR H. E. Schierling, NRR G. W.

Knighton, NRR Distribution-J. H. Taylor, IE R. H. Vollme*, IE J. G. Partlow, IE B. K. Grimes, IE G. T. Ankrum, IE J. L. Hilhoan, IE J. G. Spraul, IE QASIP Reading QQUABReading

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QUAB I UAB:C 5P IE: QA P:A0 JGSpraul:ric JLH 1hoan GTXnkrum uH.es GJPartlow

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QA BRANCH SSER INPUT 4

DIABLO CANYON UNIT 2 OESIGN VERIFICATION 6.

QA/QC I

The QA Manual for Diablo Canyon Unit 2 was issued in January 1970; 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants" was issued in June 1970; and the provisional construction permit was approved for Unit 2 in December 1970.

The manual was to be used for Unit 1 only "to the extent possible...," but was to be fully applied to j

safety-related activities and items for Unit 2.

Thus while the QA Manual was identified for Units 1 and 2, the commitment to apply the program at Unit 2 was stronger than the commitment to apply it to Unit 1.

As noted in the report to the ACRS concerning design and g

E construction of Diablo Canyon Unit 2 (September 23,1969),the l

"organizational arrangement satisfies our (i.e., Division of Reactor Licensing, AEC) requirements... Many aspects of the applicant's QAP will require further definition; however, his commitments and the extent of his planned approach in each of the critical areas are satisfactory for the construction permit stage.... "

With the institution of the Diablo Canyon Project (DCP) in the 1981 time frame, the staff reviewed the QA program description to be applied to the OCP verification effort by PG&E.

The program was based on the QA programs of Bechtel and PG&E, The staff fourd that the QA program described requirements, procedures, and controls that, when properly implemented, comply with the requirements of Appendix 8 to 10CFR Part 50.

Thus, from 1969 until today PG&E has been committed to a QA program which meets NRC requirements.

In $$ER 18 concerning the operation of Diablo Canyon, the staff concluded that "shortcomings found in and as a result of earlier QA programs (implementation) for certain design activ! ties are being compensated by verification of the design under the IOVP, that construction was done under acceptable QA controls, and that current corrective actions ard the 10VP work itself are being performed in accordance with acceptable QA programs."

These conclusions are applicable to both Units 1 and 2.

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d, FEB 12 W Docket No. 50-323 HEMORANDUM FOR:

Frank J. Miraglia, Acting Director Division of Licensing Office of Nuclear Reactor Regulation FRCH:

James G. Partlow; Acting Director Division of Quality Assurance, Safeguards, and Inspection Programs Office of Inspection and Enforcement

SUBJECT:

DIABLO CANYON UNIT 2 REVIEW Your memorandum dated January 11, 1985, on the above subject requested IE's SSER input on the QA program applicable to the design of Unit 2 (identifying any dif ference from Unit 1).

This memorandum is in response to that request, and our SSER input is enclosed.

It reflects an acceptable QA program description since before the construction perttit for Unit 2 was issued in late 1970.

Any questions on the above or on the enclosure should be addressed to the QA Branch reviewer, Jack Spraul, on r 24530.

CF!0"4L fl0NTD By:

JAM!$ C. W,*,a James G. Partlow, Acting Director Division of Quality Assurance, Safeguards, and Inspection Programs Office of Inspection and Enforcement

Enclosure:

SSER Input ec:

L. J. Chandler, NRR C. I. Grimes, NRR H. E. Schieriing, NRR G. W. Knighton, NRR Distribution:

J. H. Taylor, IE R. H. Vollmer. IE J. G. Partlow, IE B. K. Grimes, IE G. T. Ankrum, IE J. L. Hilhoan, IE QiS WWH OW g

QUAB Reading y'.

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