ML20206P597

"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.

Summary of 860724 Meeting W/Util,Inel,Wyle Labs,Sargent & Lundy & Tenera in Bethesda,Md Re Util Draft Documentation to Justify Qualification of safety-related Cabling at Plant. List of Attendees Encl

ML20206P597
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/15/1986
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Berkow H Office of Nuclear Reactor Regulation
References
TAC-42527, NUDOCS 8608270247
Download: ML20206P597 (5)

Text

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i p ara UNITED STATES y

g NUCLEAR REGULATORY COMMISSION O

j WASHINGTON, D. C. 20555

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August 15, 1986 Dccket No. 50-267 MEMORANDUM FOR: Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B THRU:

0. D. T. Lynch, Jr., Section Le h 1

Standardization and Special Projects Directorate Division of PWR Licensing-B FROM:

Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

SUBJECT:

SUMARY OF JULY 24, 1986 MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) TO DISCUSS CABLE QUALIFICATION This meeting was held at the Nuclear Regulatory Commission's offices, Room P-422, Bethesda, Maryland at 9:00 a.m. on July 24, 1986. The purpose of this l

meeting was to discuss, in detail, the draft documentation prepared by PSC to justify qualification of safety related cabling at the Fort St. Vrain Nuclear GeneratingStation(FSV). Meeting attendees are listed in the enclosure.

PSC's staff and consultants briefly reviewed three licensee-selected sample cable qualification packages for the staff. Typically, the qualification packages used a thermal lag analy.;is to demonstrate that the actual environ-ment which could be experienced by the cable during an accident was within the envelope of available qualification test data. This is because the predicted FSV environment typically exceeded this envelope for less than a minute, and only for very severe pipe breaks. Where test data and reports were i

not available for the specific cable in question, PSC used qualification data for similar cables made by another manufacturer. Similarity arguments were based on the fact that the cables were all fabricated from polyvinylchloride materials. PSC stated that similarity analyses of this type had been previously accepted by the NRC.

Of particular interest were details of the cable qualification process for i

cables which could not be specifically identified by manufacturer's type.

Certain " generic" cables at FSV were' originally purchased by Eastern Cable, one of the contractors during the construction of FSV. The specific manufacturer for these cables.is not known. However, short duration high temperature test results were available to demonstrate the qualification for these cables during high temperature transients. Long-tem operability for these cables was demonstratec by a comparison of the manufacturing standards for these cable types. The minimum acceptance levels of the manufacturing standards for these cables are adequate to assure long-term operability.

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.. t The thermal lag analysis used in demonstrating qualification utilized aThe consulta specific thermal model for each cable type.

heat transfer to the cable by radiation, convection and cond PSC also noted that thermal lag to model cable internal f. eat generation.

These included:

analysis had been used to qualify certain other components.

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- Terminal Blocks,

- Cable Splices, and

- Switchgear at Motor Control Centers.

The staff commented that PSC's general approach to cable qualification, as However, the indicated by the sample packages, appeared to be acceptable.

staff noted several areas for potential improvements of the cable qualification packages. These included:

(The

- Clarifying the qualification goals of each qualification pa and difficult to meet than for lower category packages.)

- Including a signoff sheet indicating review and acceptance by etch qualification package.

ptckage should also be noted.

- Having qualified FSV Quality Assurance personnel review each package upon receipt from the contractor.

- Evaluating the role of the end devices in assessing potential leakage currents for instrumentation cables.

The need for

- Eliminating inconsistencies in qualification packages.

quality control in the development process of these packages should be emphasized.

The staff requested that PSC provide specific reference to their thermal lag PSC agreed to add this to the forthcoming update of the methodology.

equipment list (MEL).

as fieldwork continued.

PSC stated that their current projections indicated that the fielfork would

However, be complete and the plant ready to operate by about O program could take two to four weeks longer.@ M b. b Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure:

See next page

Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc.

Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager

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Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colcrado 80203 l

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6 Enclosure NRC - PSC Meeting: July 24, 1986 (Cable qualification)

Name Organization K. L. Heitner NRR/DPWRL-B/SSPD Paul Shemanski NRR/PWR-B/PEICSB John M. Fehringer INEL/NRC Contractor R. E. Ireland NRC - RIV G. T. Hubbard NRC - IE/VPB Rob Burg Tenera Phil DiBenedetto DBA Inc.

Sam Marquez PSC Mike Niehoff PSC Jim Anderson WYLE LABS James Selan PSC Jim Gleason WYLE William H. Schwartz DBA Inc.

i James Grossman SN Labs Charles Hinson NRR/DPWRL-B/SSPD John C. McKinley NRC/ACRS Staff J. Sinnappan S&L Bill Adams Sargent & Lundy

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0<AWA August 15, 1986 3, g p g AccAt PDR The thermal lag analysis used in demonstrating qualification utilized a specific thermal model for each cable type. The consultant's model considered heat transfer to the cable by radiation, convection and condensation.

Consistent assumptions were used to model flow parameters around the cable and to model cable internal heat generation.

PSC also noted that thermal lag analysis had been used to qualify certain other components. These included:

- Terminal Blocks,

- Cable Splices, and

- Switchgear at Motor Control Centers.

The staff comented that PSC's general approach to cable qualification, as indicated by the sample packages, appeared to be acceptable. However, the staff noted several areas for potential improvements of the cable qualification packages. These included:

- Clarifying the qualification goals of each qualification package.

(The staff noted the requirements for Category 1 packages were more extensive and difficult to meet than for lower category packages.)

- Including a signoff sheet indicating review and acceptance by PSC in each qualification package. Open items relevant to that qualification package should also be noted.

- Having qualified FSV Quality Assurance personnel review each package upon receipt from the contractor.

- Evaluating the role of the end devices in assessing potential leakage currents for instrumentation cables.

- Eliminating inconsistencies in qualification packages. The need for quality control in the development process of these packages should be emphasized.

The staff requested that PSC provide specific reference to their ther;ral lag methodology. PSC agreed to add this to the forthcoming update of the master equipment list (MEL). However, PSC noted that further MEL updates were likely as fieldwork continued.

PSC stated that their current projections indicated that the fieldwork would j

be complete and the plant ready to operate by about October 1,1986. However, completion of the files required to support the equipment qualification program could take two to four weeks longer.

Original signed by Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure:

See next page

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