ML20210U754

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Confirms Discussions Re Relationship Between Allegations & Matters Before Aslab Concerning Design QA Matters.Effect of Matters on Evaluations Presented in Ssers 16,18 & 19 Should Be Considered
ML20210U754
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 01/13/1984
From: Chandler L
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Bishop T, Knight J
NRC
Shared Package
ML20210U520 List:
References
FOIA-86-197 NUDOCS 8610100175
Download: ML20210U754 (7)


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F January 13, 1984 Note to:

Jim Knight Tom Bishop DIABLO CANYON - RELATI0riSHIP BETWEEN ALLEGATI0tS AND MATTERS BEFORE APPEAL BOARD This is to confirm our several discussions during the past few weeks pertaining to current staff efforts related to Diablo Canyon allegations.

Specifically, I have asked that you advise me of any matters raised in the allegations which, based on the Staff's evaluations to date, in any way raise a concern regarding the design quality assurance matters now being considered by the Appeal Board.

In this respect, you should consider whether such matters would have an effect on the Staff's evaluations pre-sented in the several recent SER supplements (nos.16,18 and 19) regarding the IDVP and CCW and/or on the testimony given by the Staff at the hearing held in October-November-1983. To facilitate your consideration, I am attaching a copy of the issues which were litigated before the Appeal Board.

I cannot emphasis strongly enough the need to promptly bring to my attention any matter relating to the above which could affect the Appeal Board's deliberations so that I can inform the Appeal Board and parties if appropriate.

Lawrence J. Chandler Deputy Assistant Chief Hearing Counsel

Attachment:

As noted cc: John B. Martin Darrel G. Eisenhut/

Hans Schierling/

er 8610100175 860930 l

PDR FOIA

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HOLMF586-197 PDR

y, Appendix A ISSUES LITIGATED IN THE REOPENED DESIGN QUALITY ASSURANCE HEARINGS Upon the motions of the Governor and the joint intervenors and in acordance with the concessions of the applicant and the staff, the record in ' the Diablo Canyon operating license proceeding was reopened on the issue of design quality assurance.

The primary focus of the reopened proceeding, however, has now moved beyond the question of whether the applicant can demonstrate that the IDVP and the ITP verify the correctness of the Diablo Canyon design.

The licensing criteria contained in the PSAR, FSAR, Hosgri Report, SER, SER Supplenments and other licensing documents are outside the scope of the issues in this reopened proceeding and are not subject to challenge, except to the extent that such criteria may have been modified in the verification program.

The Governor and the joint intervenors assert that the verification programs have failed in the following respects:

1.

The scope of the IDVP review of both the seismic and non-seismic aspects of the designs of safety-related systems, structures and componehts (SS&C's) was too narrow in the following aspects:

(a)

The IDVP did not verify samples from each design activity (seismic and non-seitmic).

(b)

In the design activities the IDVP did review, it did not verify samples from each of the design groups in the design chain performing the design activity.

(c)

The IDVP did not have statistically valid samples from which to draw conclusions.

(d)

The IDVP failed to verify independently the analyses but merely checked data of inputs to models used by PG&E.

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(e)

The IDVP failed to verify the design of Unit 2.

2.

The scope of the ITP review of both the seismic and non-seismic aspects of the designs of the safety-related systems, structures and components (SS&C's) was too narrow in the following aspects:

(a)

The ITP did not verify samples from each design activity (seismic and non-seismic).

(b)

In the design activities the ITP did review, it did not verify samples from each of the design groups in' the design chain performing the design activity.

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y, (c)

The ITP did not have statistically valid samples from which to draw conclusions.

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(d)

The ITP has failed systematically to verify the adequacy of, the design of Unit 2.

3.

In various~ situations listed below, the ITP used improper engineering standards to determine whether design activities met license criteria.

In some of these situations, the IDVP either used or approved the use of such improper standards or did not verify them at all.

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(f)

The ITP's modeling of the soil properties for the containment and auxiliary buildings was improper in that:

(i) in the soil structure interaction analysis of containment for the DE and the DDE, use of boundary motion i.nputs to the model were improperly used; (ii) the soil structure interaction analysis for containment for the DE and the'DDE uses a 7 percent damping value for rock, which is unconservative, especially.for the DE; (iii) the dynamic analyses of the containment for all earthquakes omit any analysis of uplif ting of the foundation mat; (iv) the modeling of the soil springs for the auxiliary building does not specify soil properties; (v) in the modeling of the soil springs for the auxiliary building,.the motion inputs to the lower ends of the springs does not account for all soil structure j

interaction phenomena that could be expected.

(o)

The ITP has not demonstrated, and the IDVP has not veri fi.ed, that the fDCP modeling of the seismic response of '.

the fuel handling building is proper, in that the DCP has not adequately justified the use of the translational and torsional response of the auxiliary building as input to the i

f uel handling building nor has it demonstrated the validity of the 4gnamic degrees of freedom selected.

i (p)

The ITP has not demonstrated, and the IDVP has not verified, that the DCP seismic model of the slabs in the auxiliary building is proper, in relation to the use of vertical and rotational springs to model the columns, and the l.

motions used as input at the ends of the springs not I.'

connected to the slabs.

In addition, in the study of the diaphragms, the ITP has not adequately accounted for the 1

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inplane flexibility of these slabs, and has not adequately demonstrated that stresses are within allowable limits at all elevations.

(q)

The ITP has not demonstrated and the IDVP has not verified, that the soils analysis for the buried diesel fuel oil tanks is proper in that the values of the exponent shown in figure 14 of ITR 68 have not been demonstrated 'to be hppropriate and the variation of shear velocity with depth is not properly justified.

(r)

The ITP has not demonstrated and the IDVP has not verified that the soils' analysis for the auxiliary saltwater piping and circulating water intake conduits is proper in that the selection of the modulus versus strain curve utilized is not justified.

(s)

The ITP has not demonstrated and the IDVP has not verified that the seismic analysis of the turbine building is proper in that bolt bearing capacities were taken from an i

inappropriate source.

( t ).

The ITP has not demonstrated and the IDVP has not

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verified that the seismic analysis of the turbine building is proper in that the use of four different models for the vertical analysis has not been justified.

4.

The IDVP accepted deviations from the licensing criteria without providing adequate engineering justification in the following respects:

a.

Contrary to the requirements of FSAR Section 17.1 regarding compliance of the as-built installation with ~the design documents, the IDVP review of the AFWS ditelosed that the as-built installation f ailed to meet the design drawings in that (i) a steam trap on the turbine-driven AFW pump steam supply line is not provided and (ii) there are discrepancies in the arrangement of the long-term-cooling water supply line.

b.

Contrary to FSAR Sect ion 8.3.3, the electrical design does not fclly comply with the commitments regarding sepai.aO on. nd color coding,

h.

Contrary to PG6E's September 14 and December 28, 1978, licensing commitments, CRVPS equipment identified in the FSAR as necessary to maintain control room habitability during safe shutdown has i

not been evaluated'regarding the effects of a moderate energy pipe break.

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i.

The fire protection for the motor driven AFW pump room is not consistent with the PG&E licensing commi tment for fire zone separation as stated in its November 13, 1978, Supplemental Info' mation for r

Fire Protection Review ("SIFPR") in that:

1) there. is a large grated ventilation opening in the ceiling of the room; 2) a fire damper has gaps when it is closed.

j.

The fire protection for the AFW pump room is not consistent with the P,G&E licensing commitment for cable separation as stated in its SIFPR of November 13, 1978, in that:

1) the pumps for the motor driven AFW pumps and the control circuitry for a flow control valve necessary for operation of the tarbine driven AFW pump are located in a single fire zone; 2) cables for some AFW c'ircuits are not routed in accord with descriptions in the SIFPR and four AFW-circuits PG&E committed to identify and review in the SIFPR were not included in that document.

k.

Contrary to the licensing commitment set forth in its SIFPR of November 13, 1978, each of the three 4160 volt cable spreading rooms has a ventilation opening leading up to the 4160 volt switchgear rooms.

1.

Contrary to FSAR Section 3.6, possible jet impingement loads have not been considered in the design and qualification of safety-related piping and equipment inside containment.

q.

Contrary.to PG&E's December 28, 1979, licensing '_

commitment letter to the NRC, modifications to protect two Auxiliary Feedwater valves from the l

effects of moderate energy line breaks were not l

implemented.

1 r.

Contrary to the licensing commitment to maintais minim'um system redundancy as stated in FSAR Section 3.6A (NSC evaluation of pipe break outside con ta inme nt ), four components were identified for which high energy line cracks could cause temperatures in excess of the specification temperatures of the components.

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4 s.

Contrary to the licensing commitment to maintIain minimum system redundancy as stated in FSAR Section 3.6A (NSC evaluation of pipe break outside containment), a conduit was identified whose f ailure due to a high energy line crack could i

eliminate redundant Auxiliary Feedwater system flow.

t.

Contrary to the FSAR Section 8.3 commitment to provide switchgear buses with adequate short circuit interrupting capability, the calculated duties for circuit breakers on 4160 V buses F, G, and H were above the nameplate ratings for those buses.

u.

Contrary to single failure criteria stated in FSAR Section 3.1.1, reviews of the Auxiliary Feedwater and Control Room Ventilation and Pressurization systems identified cir'cuit separation and single failure deficiencies.

Similar deficiencies were identified in additional verification reviews, which included other safety-related systems.

5.

The verif'ication program has not verified that Diablo Canyon Units 1 and 2 "as built" conform to the design drawings and analyses.

6.

The verification program failed to verify that the design of safety-related equipment supplied to PG&E by Westinghouse met licensing criteria.

7.

The verification program failed to identify the root causes for the failures in the PG&E design quality assurance program and failed to determine if such failures raise generic Concerns.

8.

The ITP failed to develop and implement in a timely manner a design quality assurance program in accordance with 10 C.F.R. Part 50, Appendix B to assure the quality of the recent design modifications to the Diablo Canyon facility and the IDVP failed to ensure that the corrective and preventative action programs implemented by the ITP are sufficient to assure that the Diablo Canyon facilities will meet licensing criteria.

9.

Contrary to General Design Criteria 44 (GDC-44) of Appendix A to.10 C.F.R. Part 50, PG&E has failed to provide adequate assurance of component cooling water system (CCWS) heat removal safety function capacity in that the maximum ocean water temperative of 64 degrees F. is not conservative because it has already been exceeded in 1983.

Furthermore, a technical specification limitation which permits plant operation at reduced i

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t power levels in lieu of enlarging the capacity of the CCWS does not provide an equivalent level of safety as compliance with the requirements of GDC-44 (SSER 16 (Aug. 1983) and September 1983 ocean water. temperature readings).

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