ML20059A599

Forwards Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f)

ML20059A599
Person / Time
Site:	Harris, Brunswick
Issue date:	12/22/1993
From:	Callan L Office of Nuclear Reactor Regulation
To:	Orser W CAROLINA POWER & LIGHT CO.
References
GL-92-08, GL-92-8, TAC-M85526, TAC-M85527, TAC-M85556, NUDOCS 9401030051
Download: ML20059A599 (11)

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['l*%n E- UNITED STATES i( ~j NUCLEAR REGULATORY COMMISSION gw ,/ WASHINGTON, D.C. 20555-0001 December 22, 1993 Docket No. 50-325, 50-324 and 50-400 Mr. W. S. Orser Executive Vice President Nuclear Generation Carolina Power & Light Company Post Office Box 1551 Mail Code: CPB 12 Raleigh, North Carolina 27602

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SENERIC LETTER 92-08, " THERM 0-LAG 330-1 FIRE BARRIERS," PURSUANi TO 10 CFR 50.54(f)

- BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2, AND SHEAR 0N HARRIS NUCLEAR POWER PLANT, UNIT 1 (TAC NOS. M85526, M85527 and M85556)

In your response of April 16, 1993, to Generic Letter (GL) 92-08, i "Thermo-Lag 330-1 Fire Barriers," you indicated that actions necessary to restore the operability of these barriers at the Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), and the Shearon Harris Nuclear Power Plant, {

Unit 1 (SHNPP) would be based on the results of the industry test ' program j being coordinated by the Nuclear Management and Resources Council-(NUMARC). >

During recent meetings with U.S. Nuclear Regulatory Commission (NRC) staff, J the Executive Director for Operations and the Commission, NUMARC described the scope of its Thermo-Lag fire barrier program, the results of the Phase 1. fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the  ;

development of guidance for applying the test results to plant-specific fire i barrier configurations. However, NUMARC's program is not intended to bound l all in-plant Thermo-Lag fire barrier configurations. -During a NUMARC-sponsored industry workshop on December 1 and 2, 1993, NUMARC presented the scope of its program and the Phase 1 test results to the licensees.

In view of the limited scope of the NUMARC program and the limited success of l the Phase 1 tests, it is clear to the staff that the-NUMARC program will not '

be sufficient to resolve all Thermo-Lag fire barrier issues identified-in GL 92-08. Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with their in-plant Thermo-Lag barriers.

To help ensure timely resolution of the fire barrier issues at Brunswick and  ;

SHNPP, the staff requires additional information on the configurations and i amounts of Thermo-Lag fire barriers installed in the plant and the cable  ;

loadings within particular.Thermo-Lag configurations. This information is necessary to review NUMARC's guidance for applying the test results to plant-  ;

specific barrier configurations and to identify configurations that are outside the scope of NUMARC's test program. For those configurations that are outside the scope of the program or for those configurations that you deem are 290c2o EC RLE CL97ER COPY #

9401030051 931222 'v PDR

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ADOCK 05000324 PDR. i l\

Mr. W. Orser December 22, 1993.

impractical to upgrade, we request that you provide plans and schedules for resolving the technical issues identified in GL 92-08. ,

You are required, pursuant to Section 182(a) of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f), to submit a written report that contains the information specified in the enclosure to this letter within.45 days from ,

receipt of this letter. Your response must be submitted under oath or affirmation. Please submit your response to the undersigned, with a copy to the Regional Administrator, Region II. Please retain all information and documentation used to respond to this request on site for future NRC audits or inspections.  ;

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994. The estimated average number of burden hours of 300 person-hours is anticipated to increase by an additional 120 person-hours for each addressee's response, including the time' required to assess the requirements for information, search data sources, gather and analyze the data, and prepare the required-letters. This revised estimated average number of burden hours pertains only to the identified response-related matters and does not include the time to implement the actions required to comply with the applicable regulations, license conditions, o.r- '

commitments. Comments on the accuracy of this estimate and suggestions to reduce the burden may tc directed to the Office of Information and Regulatory Affairs (3150-0011), NE0B-3019, Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Commission, Information and Records Management Branch (MNBB-7714), Division of Information Support Services, Office of Information and Resources Management, Washington, D.C.

20555.

If you have any questions about this matter, please contact Patrick D. Milano with any questions regarding Brunswick at (301) 504-1457 or N. B. Le with questions regarding Shearon Harris at (301) 504-1458 or call Patrick Madden at (301) 504-2854 with questions on either facility.

Sincerely, ORIGINAL SIGNED BY:

L. J. Callan >

Acting Associate Director for Projects Office of Nuclear Reactor Regulation ,

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page OFFICE LA:PP[I4fi PM:PDII-l PD:POII_-1 PD:PDil-1 (A)6DS NAME PAnNerIn NLe M/r- PMilN SBajwa/k LJbrbn DATE~ 12/Ql/93 12/2//93 12hi/93 12/1//93 12/F2 /93 0FFICIAL RECORD COPY FILENAME: G:\ HARRIS \THERMO.HAR l

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Mr. W. Orser impractical to upgrade, we request that you provide plans and schedules for resolving the technical issues identified in GL 92-08.

You are required, pursuant to Section 182(a) of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f), to submit a written report that contains the information specified in the enclosure to this letter within 45 days from receipt of this letter. Your response must be submitted under oath or affirmation. Please submit your response to the undersigned, with a copy to the Regional Administrator, Region II. Please retain all information and documentation used to respond to this request on site for future NRC audits or inspections.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which. expires June 30, 1994. The estimated average number of burden hours of 300 person-hours is anticipated to increase by an additional 120 person-hours for each addressee's response, including the time required to assess the requirements for information, search data sources, gather and analyze the data, and prepare the required letters. This revised estimated average number of burden hours pertains only to the identified response-related matters and does not include the time to implement the actions required to comply with the applicable regulations, license conditions, or commitments. Comments on the accuracy of this estimate and suggestions to reduce the burden may be directed to the Office of Information and Regulatory Affairs (3150-0011), NE08-3019, Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Commission, Information and Records Management Branch (MNBB-7714), Division of Information Support Services, Office of Information and Resources Management, Washington, D.C.

20555.

If you have any questions about this matter, please contact Patrick D. Milano with any questions regarding Brunswick at (301) 504-1457 or N. B. Le with questions regarding Shearon Harris at (301) 504-1458 or Patrick Madden at (301) 504-2854 with questions on either facility.

Sincerely, L. . Callan Ac ng Associate Director for Projects Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page I s

I DISTRIBUTION

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' NRC & Local PDR PD 11-1 Rdg SVarga LCallan CMcCracken PMadden CBerlinger RJenkins

.0GC SBajwa MGamberoni RIngram, PMSB Region II ACRS (10)

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cc: Carolina Power & Light Company Mr. H. Ray Starling Mr. H. W. Habermeyer, Jr.

Manager - Legal Department Vice President '

Carolina Power & Light Company Nuclear Services Department Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602 Post Office Box 1551 - MCode OHS 7 -

Raleigh, North Carolina 27602 Karen E. Long Assistant Attorney General Resident Inspector / Harris NPS State of North Carolina Shearon Harris Nuclear Power Plant Post Office Box 629 Nuclear Regulatory Commission Raleigh, North Carolina 27602 Route 1, Box 315B New Hill, North Carolina 27562 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Mr. W. R. Robinson 101 Marietta Street, N.W., Ste. 2900 Plant Manager Atlanta, Georgia 30323 Carolina Power & Light Company Shearon Harris Nuclear Power Plant Mr. Dayne H. Brown, Director Post Office Box 165 <

Department of Environmental, New Hill, North Carolina 27562 Health and Natural Resources Division of Radiation Protection Mr. R. A. Anderson, Vice President Post Office Box 27687 Carolina Power & Light Company Raleigh, North Carolina 27611-7687 Brunswick Steam Electric Plent Post Office Box 10429 Mr. Robert P. Gruber Southport, North Carolina 28461 Executive Director Public Staff - NCUC Mr. Kelly Holden, Chairman Post Office Box 29520 Board of Commissioners Raleigh, North Carolina 27626-0520 Post Office Box 249 Bolivia, North Carolina 28422 Resident Inspector i U. S. Nuclear Regulatory Commission Admiral Kinnaird R. McKee Brunswick Steam Electric Plant 214 South Morris Street Star Route 1, Post Office Box 208 0xford, Maryland 21654 l Southport, North Carolina 28461 '

Mr. Robert D. Martin l Mr. J. M. Brown 3382 Sean Way l Plant Manager - Unit 1 Lawrenceville, Georgia 30244 i Carolina Power & Light Company Brunswick Steam Electric Plant Mr. Mark S. Calvert Post Office Box 10429 Associate General Counsel Southport, North Carolina 28461 Carolina Power & Light Company Post Office Box 1551 Mr. C. C. Warren Raleigh, North Carolina 27602-Plant Manager - Unit 2 Carolina Power & Light Company Mr. Norman R. Holden, Mayor Brunswick Steam Electric Plant City of Southport Post Office Box 10429 201 East Moore Street ,

Southport, North Carolina 28461 Southport, N.C. 28461 Public Service Commission 1 State of South Carolina  !

Post Office Drawer 11649  :

Columbia, South Carolina 29211  !

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ENCLOSURE 1

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08

" THERM 0-LAG 330-1 FIRE BARRIERS" PURSUANT TO 10 CFR 50.54(f)

1. Thermo-Lag Fire Barrier Configurations and Amounts A. Discussion Generic Letter (GL) 92-08,"Thermo-Lag 330-1 Fire Barriers," applied '

to all 1-hour and all 3-hour Thermo-Lag 330-1 materials and barrier systems constructed by any assembly method, such as by joining preformed panels and conduit preshapes, and trowel, spray, and brush-on applications. This includes all fire barriers, all barriers to achieve physical independence of electrical systems, radiant energy heat shields, and barriers installed to enclose  ;

intervening combustibles.

B. Required Information -'

1. Describe the Thermo-Lag 330-1 barriers installed in the ,

plant to

a. meet 10 CFR 50.48 or Appendix R to 10 CFR Part 50,

b. support an exemption from Appendix R, 1

c. achieve physical independence of electrical systems,

d. meet a condition _of the plant operating license, ,

e. satisfy licensing commitments.

The descriptions should include the following information:

the intended purpose and fire rating of the barrier (for example, 3-hour fire barrier,1-hour fire barrier, radiant energy heat shield), and the type and dimension of the barrier (for example, 8-ft by 10-f t wall, 4-f t by 3-ft by .

2-ft equipment enclosure, 36-inch-wide cable tray, or "

3-inch-diameter conduit).

2. For the total population of Thermo-Lag fire barriers described under Item I.B.1, submit an approximation of:

a. For cable tray barriers: the total linear feet and ,

square feet of 1-hour barriers and the total linear j feet and square feet of 3-hour' h rriers. '

b. For conduit barriers: the total linear feet of 1-hour barriers and the total linear feet of 3-hour barriers. )

c. For all other fire barriers: the total square feet of 1-hour barriers and the total square feet of 3-hour barriers.

d. For all other barriers and radiant energy heat shields: the total linear or square feet of 1-hour barriers and the total linear or square feet of_3-hour barriers, as appropriate for the barrier configuration or type.

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II. Important Barrier Parameters A. Discussion-In a letter of July 29, 1993, from A. Marion, NUMARC, to C. McCracken, NRC, NUMARC stated: " Relative to bounded configurations, ... [i]t will be the utilities' responsibility to verify their baseline installations are bounded." Furthermore, NUMARC stated that the parameters of importance for utility use of data from the industry Thermo-Lag fire barrier test program are: ,

1. Raceway orientation (horizontal, vertical, radial bends)

2. Conduit

3. Junction boxes and lateral bends

4. Ladder-back cable tray with single layer cable fill

5. Cable tray with T-Section

6. Raceway material (aluminum, steel)

7. Support protection, thermal shorts (penetrating elements)

8. Air drops '

9. Baseline fire barrier panel thickness

10. Preformed conduit panels

11. Panel rib orientation (parallel or perpendicular to the '

raceway)

12. Unsupported spans

13. Stress skin orientation (inside or outside)

14. Stress skin over joints or no stress skin over joints

15. Stress skin ties or no stress skin ties

16. Dry-fit, post-buttered joints or prebuttered joints

17. Joint gap width

18. Butt joints or grooved and scored joints

19. Steel bands or tie wires

20. Band / wire spacing

21. Band / wire distance to joints

22. No internal bands in trays i

23. No additional trowel material over sections and joints or additional- trowel material applied

24. No edge guards or edge guards Each NUMARC cable tray fire test specimen includes 15 percent cable fills (i.e., a single layer of cables uniformly distributed across the bottom of the cable tray). This approach requires consideration of plant-specific cable information during the assessments of tested configurations and test results in relation to plant-specific Thermo-Lag configurations; for example, cable trays with less thermal mass (cable fill) than the NUMARC test specimens, different cable  ;

types, and the proximity of the cables to the Thermo-Lag (e.g., cables may be installed in contact with the unexposed surface of the Thermo-Lag or may come into contact during a fire if the Thermo-Lag material sags). In its letter of July 29, 1993, NUMARC stated: <

" Utilities using the results of the NUMARC testing will need to evaluate their installed cable fill and ensure that it is bounded by the tested cable fill." NUMARC is not conducting any cable functionality tests or evaluations and stated that cable functionality

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evaluations will be performed by utilities using data from the generic program.

The parameters of importance concerning cables protected by fire '

barriers are: -

1. Cable size and type (power, control, or instrumentation).

2. Cable jacket type (thermoplastic, thermoset) and materials.

3. Cable' conductor insulation type (thermoplastic, thermoset plastic) '

and materials.

4. Cable fill and distribution of cables within the protected conduit '

or cable tray.

5. Proximity of cables to the unexposed (inside) surfaces of the fire ,

barrier.

6. Presence of materials between the cables and the unexposed side of '

the fire barrier material (for example, Sealtemp cloth, which is -

used in the NUMARC test specimens).

7. Cable _ operating temperature.

8. Temperatures at which the cables can no longer perform their  :

intended function when energized at rated voltage and' current. 1 Other parameters that are unique to particular barriers, such as interfaces between Thermo-Lag materials and other fire barrier '

materials or building features (walls, etc.) and internal' supports,  ;

are also important. In addition, because of questions about the.  !

uniformity of the Thermo-Lag fire barrier materials produced over time, NUMARC stated in its letter of July 29, 1993, that "[c]hemical analysis of Thermo-lag materials provided for the program, as well as samples from utility stock, will be performed, and a test report prepared comparing the chemical composition of the respective l samples." The results of the chemical analyses may indicate that -  !

variations in the chemical properties of Thermo-Lag are significant j and may require additional plant-specific information in the future. .j B. Required Information-

1. State whether or not you have obtained.and. verified each of the aforementioned parameters for each Thermo-Lag barrier installed'in the plant. If ~ not, discuss the parameters you have not obtained or verified. Retain detailed information on site for NRC audit where the aforementioned parameters are known.

2. For any parameter that is not known or has not been verified, describe how you will evaluate the in-plant barrier for acceptability.

'3. To evaluate NUMARC's application guidance, an understanding of the types and extent of the unknown parameters is .needed. . Describe the type and extent of the unknown parameters at your plant in this context.

III. Thermo-Lag Fire Barriers Outside the Scope of the NUMARC Program

. . o A. Discussion In your response of to GL 92-08, you indicated that actions necessary to restore the operability of these barriers would be based on the results of the NUMARC test program. During recent meetings with the NRC staff, the Executive Director for Operations and the Commission, NUMARC described the scope of its Thermo-Lag fire barrier program, the results of the Phase 1 fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the development of guidance for applying the test results to plant-specific fire barrier configurations. However, NUMARC's program is not intended to bound all in-plant Thermo-Lag fire barrier configurations. In view of the  ;

scope of the NUMARC program and the limited success of the Phase 1 tests, it is clear that the NUMARC program will not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL 92-08.

Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with in-plant Thermo-Lag barriers.

B. Required information  !

1. Describe the barriers discussed under Item I.B.1 that you have determined will not be bounded by the NUMARC test program.

2. Describe the plant-specific corrective action program or plan you expect to use to evaluate the fire barrier configurations particular to the plant. This description should include a discussion of the evaluations and tests being considered to i resolve the fire barrier issues identified in GL 92-08 and to demonstrate the adequacy of existing in-plant barriers. .

3. If a plant-specific fire endurance test program is anticipated, l describe the following:

a. Anticipated test specimens.

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b. Test methodology and acceptance criteria including cable  !

functionality. j i

IV. Ampacity Derating

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A. Discussion i l

NUMARC has informed the staff that it intends to use the Texas Utilities (TV) Electric Company and Tennessee Valley Authority (TVA) 4 ampacity derating test results to develop an electrical raceway .

component model for the industry. Additional information is needed to I determine whether or not your Thermo-Lag barrier configurations (to  !

protect the safe-shutdown capability from fire or to achieve physical  !

independence of electrical systems) are within the scope of the NUMARC i i

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e program and, if not, how the in-plant barriers will be evaluated for the ampacity derating concerns identified in GL 92-08.

i B. Required Information

1. For the barriers described under Item I.B.1, describe those that  ;

you have determined will fall within the scope of the NUMARC '

program for ampacity derating, those that will not be bounded by  ;

the NUMARC program, and those for which ampacity derating does not l apply. l

2. For the barriers you have determined fall within the scope of the NUMARC program, describe what additional testing or evaluation you will need to perform to derive valid ampacity derating factors.

3. For the barrier configurations that you have determined will not be bounded by the NUMARC test program, describe your plan for-evaluating whether or not the ampacity derating tests relied upon  ;

for the ampacity derating factors used for those electrical  !

components protected by Thermo-Lag 330-1 (for protecting the safe-shutdown capability from fire or to achieve physical independence  ;

of electrical systems) are correct and applicable to the plant I design. Describe all corrective actions needed and submit the .

schedule for completing such actions. l

4. In the event that the NUMARC fire barrier tests indicate the need to upgrade existing in-plant barriers or to replace existing Thermo-Lag barriers with another fire barrier system, describe the alternative actions you will take (and the schedule for performing i those actions) to confirm that the ampacity derating factors were derived by valid tests and are applicable to the modified plant design.

Your response to Section IV.B may depend on unknown specifics of the NUMARC ampacity derating test program (for example, the final barrier j upgrades). However, your response should be as complete as possible. l In addition, your response should be updated as additional information becomes available on the NUMARC program.

V. Alternatives A. Discussion On the basis of testing of Thermo-Lag fire barriers to date, it is not i clear that generic upgrades (using additional Thermo-Lag materials) I can be developed for many 3-hour barrier configurations or for some 1-hour barriers (for example,1-hour barriers on wide cable trays,  ;

with post-buttered joints and no internal supports). Morecver, some upgrades that' rely on additional thicknesses of Thermo-Lag material (or other fire barrier materials) may not be practical due to the effects of ampacity derating or clearance problems.

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B. Required Information  ;

Describe the specific alternatives available to you for achieving compliance with NRC fire protection requirements in plant areas that contain Thermo-Lag fire barriers. Examples of possible alternatives to Thermo-Lag-based upgrades include the following-

1. Upgrade existing in-plant barriers using other materials.

2. Replace Thermo-Lag barriers with other fire barrier materials or systems.

3. Reroute cables or relocate other protected components.

4. Qualify 3-hour barriers as 1-hour barriers and install detection -

and suppression systems to satisfy NRC fire protection requirements.

VI. Schedules A. Discussion The staff expects the licensees to resolve the Thermo-Lag fire barrier  !

issues identified in GL 92-08 or to propose alternative fire protection measures to be implemented to bring plants into compliance with NRC fire protection requirements. Specifically, as test data  :

becomes available, licensees should begin upgrades for Thermo-Lag i barrier configurations bounded by the test results.

B. Required Information Submit an integrated schedule that addresses the overall corrective action schedule for the plant. At a minimum, the schedule should ,

address the following aspects for the plant: '

l. implementation and completion of corrective actions and fire ,

barrier upgrades for fire barrier configurations within the scope  ;

of the NUMARC program, i

2. implementation and completion of plant-specific analyses, te; ting, -i or alternative actions for fire barriers outside the scope of the  !

NUMARC program, l VII. Sources and Correctness of Information j l

Describe the sources of the information provided in response to this request for information (for example, from plant drawings, quality  !

assurance documentation, walk downs or inspections) and how the j accuracy and validity of the information was verified. j l

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