ML20198S258

Summary of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Md to Discuss Technical Issues Associated with Kaowool Fire Barriers Installed at Farley Nuclear Plant, Units 1 & 2

ML20198S258
Person / Time
Site:	Farley
Issue date:	12/31/1998
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9901110226
Download: ML20198S258 (32)

Text

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December 31, 1998 i

LICENSEE:

Southern Nuclear Operating Company, Inc.

FACILITY:

Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2

SUBJECT:

MEETING

SUMMARY

OF DECEMBER 15,1998 i

The U.S. Nuclear Regulatory Commission (NRC) held a meeting with Southern Nuclear Operating Company, Inc. (SNC), on December 15,1998, at NRC Headquarters in Rockville, Maryland. The pulposo of the meeting was to discuss technicalissues associated with the Kaowool fire barriers installed at the Farley Nuclear Plant, Units 1 and 2.

Enclosed is a 1:st of attendees and meeting handouts.

In accordance with Section 2.790 of NRC's " Rules of Practice," Part 2, Title 10 of the Code of Federal Reoulations, a copy of this meeting summary and its enclosure will be placed in the NRC's Public Document Room.

ORIGINAL SIGNED BY D. JAFFE FOR:

Jacob 1. Zimmerman, Project Manager Project Directorate Il-2 Division of Reactor Projects - 1/il Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosures:

As stated cc w/encis: See next page Distribution _;

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December 31, 1998 l

l LICENSEE:

Southern Nuclear Operating Company, Inc.

FACILITY:

Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2

SUBJECT:

MEETING

SUMMARY

OF DECEMBER 15,1998 j

l i

The U.S. Nuclear Regulatory Commission (NRC) held a meeting with Southern Nuclear Operating Company, Inc. (SNC), on December 15,1998, at NRC Hecdquarters in Rockville, Maryland. The purpose of the meeting was to discuss technicalissues associated with the Kaowool fire barriers installed at the Farley Nuclear Plant, Units 1 and 2.

Enclosed is a list of attendees and meeting handouts.

In accordance with Section 2.790 of NRC's " Rules of Practice," Part 2, Title 10 of the Code of Federal Reaulations, a copy of this meeting summary and its enclosure will be placed in the NRC's Public Document Room.

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y Jacob 1.

merma, Proj ct Manager Project Directorate 112 Division of Reactor Projects - l/ll Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosures:

As stated cc w/encis: See next page.

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l Distribution for Meetina Summary dated December 31, 1998 HARD COPY Docket File PUBLIC PD 11-2 Rdg.

J. Zimmerman OGC ACRS cc: Licensee & Service List (with enclosure)

' E-MAIL S. Collins /R. Zimmerman (SJC1/RPZ)

B. Boger (BAB2)

J. Zwolinski (JAZ)

H. Berkow (HNB)

T. Martin (e-mail to SLM3)

M. Tschiltz (MDT)

L. Plisco, Ril P. Skinner, Ril T. Marsh, SPLB K. S. West, SPLB P. Madden, SPLB M. Salley, SPLB T. Eaton, NRR/DSSA/SPLB A. Singh, ACRS J. Bartley, Region II A. Belisle, Region 11 J. Wiseman, Region 11 i

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Joseph M. Farley Nuclear Plant cc:

l Mr. L. M. Stinson Rebecca V. Badham l

General Manager -

SAER Supervisor

. Southern Nuclear Operating Company Southern Nuclear Operating Company Post Office Box 470 :

P. O. Box 470 l

/shford, Alabama 36312 Ashford, Alabama 36312 Mr. Mark Ajiuni, Ucensing Manager Southern Nuclear Operating Company

' Post Office Box 1295 Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard i

Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region it U.S. Nuclear Regulatory Commission

- Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303_

Resident inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319

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LIST OF ATTENDEES l

U.S. Nuclear Reaulatory Commissign Jacob Zimmerman, NRR/DRPE/PDil-2, Farley Project Manager Herb Berkow, NRR/DRPE/PDil-2, Director John Zwolinski, NRR/DRPE, Acting Director L. B. Marsh, NRR/DSSNSPLB, Branch Chief K. Steven West, NRR/DSSNSPLB, Section Chief Patrick Madden, NRR/DSSNSPLB

- Mark Salley, NRR/DSSNSPLB -

Tanya Eaton, NRR/DSSNSPLB Amarjit Singh, ACRS Jonathan Bartley, Region ll, Farley Resident inspector Al Belisle, Region 11 via video conference Jerry Wiseman, Region il via video conference Southern Nuclear Operatino Company. Inc.. et al.

t Dave Morey Mark Ajiuni David Jones l

Dom Sutton Les Bailey Ray Spronkle, Westinghouse l

Fred Emerson, NEl Bob Publ, Bechtel Jesse Love, Bechtel l

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AGENDA FOR l

MEETING BETWEEN NRC AND SOUTHERN NUCLEAR OPERATING,INC.

REGARDING FARLEY NUCLEAR PLANT KAOWOOL FIRE BARRIERS l

i DECEMBER 15,1998 l

l PURPOSE:

l-Discuss raceway barrier fire protection issues related to enforcement, compliance, and safety at l

Farley Nuclear Plant (FNP).

l AGENDA:

i l

Introductions and Remarks -(J. Zimmerman, NRCID. Morey, SNC) 8:15 a.m.

introduction of Participants e

Purpose of Meeting l

o' SNC Manaaement Overview (D. Jones) 8:30 a.m.

Historical Perspective o

e Conclusions Discussion of Knowool fire barrier issues at FNP (D. Jones) 8:45 a.m.

Explain FNP's licensing basis as it relates to raceway fire protection and associated exemptions, including the conservatism built into our program.

Discuss regulatory violations and experiences regarding raceway fire protection.

Describe plans to ensure continued compliance with NRC requirements e

NRC Manaaement Overview (L.B. Marsh) 10:00 a.m.

I e

Historical Perspective e

Conclusions NRC Technical and Licensina lasues (M. Sallev) 10:15 a.m.

e Region 11 request i-e Licencing Basis l-e RAl/FNP Response e

NRC Formal Correspondence:

e Generic Letter 92-08 e

information Notices 93-40 & 93-41 e

Review of FNP Response Fire Tested Configuration vs. Plant Configuration e

Discuss of Fire Test Reports e

Installation Procedures & Ampacity Derating e

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Conclusion i

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Future Direction - NRC and SNC oorsonnel 11:15 a.m.

Closina Remarks - NRC and SNC oorsonnel 11:45 a.m.

NRR Staff will be available from 1:00 p.m. to 4:00 p.m. to continue detailed discussion of the technical and licensing issuer, if requested by SNC.

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RACEWAY FIRE BARRIER HISTORY & REGULATORY ACTIONS

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1981 Appendix R effective

- 1,3-hour rated barriers required 1991 Thermo-Lag Fire Barrier Technical Issue

- Affected majority ofplants

- Regulatory Activity

- 2 Bulletins & Supplements

- 1 Generic Letter

- 14 Information Notices & Supplements 1993 NRC Self-Assessment

- Major Findings

- Appendix R is Effective

- Staff review & follow-up not always thorough & consistent

- Need improvement in staff programs & practices 1994-Present Other Fire Barrier Systems (3M, Kaowool, Versawrap)

- Affects minority of plants

- Regulatory Activity l

- 5 Information Notices 1

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Kaowool Fire Barriers - Farley Nuclear Plant 1996

- September / October - Inspection reports 50-348 364/96-09

- Kaowool 1-hour Fire Barriers do not appear to be bounded by testmg

- November Region II requests NRR Technical Review (TIA)

- December-Notice of Violation (Level III) 1997

- August - Additional Region II Inspection reports 50-348 364/97-12

- October - SNC request meeting with Region II and NRR l

- Meeting postponed pending enforcement and NRR Tech. Review

- November - Additional Information on TIA to NRR

- December - NRR requests additional information from FNP 1998

- February - SNC submits exemption for Kaowool protected Charging Pump Cables j

- March - SNC responds to RAI, intensive review begins

- June - SPLB briefs Office Director

- October - NRR completes preliminary review l

- November - SPLB briefs Office Director

- December - NRC/SNC meeting 2

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.t NRR REVIEW DOCUMENTING INFORMATION r

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Region II Inspection results l

Region II Task Interface Agreement j

Region II TIA Supplemental information SNC response to TIA

- Design Basis of Kaowool barriers t

- Supporting fire test

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- Date of barrier installation

- Appendix A to BTP ASB 9.5-1

- Appendix R to 10CFR50 Other Tests, Standards and Data I

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FARLEY INSTALLED CONFIGURATIONS About 6,300 linear feet of Kaowool fire barriers i

Plant protected raceways i

- 1" to 5" diameter steel conduits

- 3/4" to 5" diameter aluminum conduits

-12" to 24" wide aluminum ladder back cable trays

- 4" wide aluminum cable channel l

i Kaowool Configurations

- Type 'R' - Two 1" layers w/ Zetex wrap

- Type 'H' - One 1" layers w/ Zetex wrap r

- Type 'J' - One 1" layer on bottom & sides only w/ Zetex wrap i

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NRR REVIEW DESIGN BASIS Reviewed 23 fire test documents submitted by SNC (Ref. E.4-E.27)

Observations:

- Tests-prepared, performed, & documented by the vendor

- Non-stanoard test fumace

- Non-standard test fire, e.g., heptane pan fires l

- No hose stream test

- Configuration different than those installed @ FNP

- Different material

- Different number oflayers of material

- Different installation techniques

- Different raceway sizes & materials

- Different cable sizes & fill i

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.- t 23RR REVIEW i

i DESIGN BASIS Fire Test Results

- No tests met NRC acceptance criteria Observations:

- Electrical failbre of cables occurred early for single layer of Kaowool

- Cable damage common in majority of tests.

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- Failure modes included:

- Thermal performance i

- Structural (joint) failures l

- Minimal information on supports / intervening items i

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TIIERMO-LAG 330-1 VS. KAOWOOL THERMAL COMPARISON Time Kaowool Temp.

Thermo-Lag Temp.

(Minutes)

( F)

( F) 00:10 120 104 00:20 200 205 00:30 390 305 00:40 550 427 00:50 700 506' 00:60 850

'NEI test terminated at 48 minutes.

- Kaowool results from 10/24/78 B&W test. Temperature recorded on cables a the cable tray rail interface.

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- Thermo-Lag 330-1 results from NEI base-line test 2-7. Maximum temperatures recorded on cable tray rail.

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APPENDIX R EXEMPTIONS SER approves Appendix R exemptions based on:

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l "One-hour barrier enclosures wi'l be installed..."

" Raceway... will be protected by a one-hour fire barrier."

Kaowool barrier technical review calls into question the basis for the exemptions.

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NRC FORMAL CORRESPONDENCE

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i Generic Letter 92-08: "However the staff expects that the recipients of this generic letter will review the information to determine ifit applies to other barrier materials and systems used at their facilities and consider actions, as appropriate, to avoid similar problems."

SNC response to GL 92-08: " Thermo-lag 330-1 fire barrier material is not used at the Farley nuclear plant facility."

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t NRC FORMAL CORRESPONDENCE Information Notice 93-40 " Fire endurance test results for Thermal Ceramics FP-60 i

fire banier material" SNC response to IN 93-40: "SNC has determined that FP-60 fire barrier systems are 1

not installed in either unit 1 or unit 2 at FNP."

- SNC RAI response - March 1998, Reference E.26 and E.27 FP-60 fire test, Reference E.30 FP-60 installation instructions.

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NRC FORMAL CORRESPONDENCE Information Notice 93-41 "One-hour fire endurance test results for Thermal a

Ceramics Kaowool,..."

very small-scale test horizontal sample-onejoint-no direction change non-standard furnace - 1 TC. - control

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no hose stream exhibited cable damage not independently performed l

SNC/Bechtel performed review ofIN 93-41

-Conclusion: "Kaowool would provide adequate protection."

NRR review does not reach the same conclusion l

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SAFETY SIGNIFICANCE Kaowool fire barrier performance issues similar to Thermo-Lag e

Fire resistive performance of the Kaowool fire barrier system is indeterminate.

The fire endurance test results used as the licensing basis for Kaowool fire barriers have not adequately demonstrated the validity of the associated tests and their applicability to installed plant designs.

The fire endurance test do not demonstrate the installed Kaowool fire barriers meet NRC fire protection requirements, granted exemptions, and guidance (e.g., GL 86-10).

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Impact on Defense-in-Depth Incomplete and inconclusive fire endurance / hose stream testing of Kaowool fire barrier systems does not provide the reasonable assurance needed to assure barrier integrity will be maintained during significant fire condition.

t Flie barrier integrity important in reducing the likelihood that both post-fire safe shutdown trains will be damaged by fire or Re fighting operations.

j Safety margins implied by Appendix R exemptions may be impacted j

e Fire loading and the potential energy release from fire hazards may exceed the f

fire rating of the Kaowool barrier (due to inadequate qualification testing, fragility of the barrier system, and unproven installation practices).

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OTHER NUCLEAR PLANTS USING KAOWOOL Sequoyah U' nits 1 & 2 - remove / replace with Thermo-Lag 330-1 l

Susquehanna Units 1 & 2 - remove / replace with another material Salem Units 1 & 2 - remove / replace with another material Prairie Island - renove/ replace with another material 1

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NRR CONCLUSIONS FARLEY KAOWOOL i

Design Basis documents submitted do not establish 1-hour fire rating Tests do not bound installed configurations

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Kaowool installed at Farley t

- less than required 1-hour fire barrier

- thermal performance is indeterminate l

Ampacity derating

- Installed configurations differ from limits established in tested configuration Distinction between Appendix R vs. Appendix A requirements Not in compliance with approved Appendix R exemptions 16

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The NRC Inspection Report from September of 1985 no1:es that " Included in the NRC~

review was an evaluation of the acceptability of the barrier or enclosure construction and configuration... as used in the plant."

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required by the technical requirements of 10 CFR 50 Appendix R, Section Ill.G.~2."

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GENERIC LE I l ER 86-10 Documentation Required to Demonstrate Compliance:

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L GENERIC LE I TER 86-10, Supplement 1 l

"This guidance will be used by the Staff to review and evaluate j

the adequacy of fire endurance tests and fire barrier systems proposed by the licensee in the future to satisfy existing NRC fire protection rules and regulations.

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"...this... supplement will be used by the Staff for review and evaluation of the adequacy of fire barrier systems and fire endurance tests that may be proposed in the future to satisfy existing NRC fire protection rules and regulations."

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