Text

Forwards Responses to NRC Positions Re Fire Protection Program
	ML19274E756
Person / Time
Site:	Calvert Cliffs
Issue date:	04/19/1979
From:	Lundvall A; BALTIMORE GAS & ELECTRIC CO.
To:	Reid R; Office of Nuclear Reactor Regulation
References
	013-261-OL-037, 13-261-OL-37, NUDOCS 7904240346
	Download: ML19274E756 (43)
	v • d • e

1 1 B ALTI M ORE GAS AN D ELECTRIC CO M PANY GAS AN D ELECTRIC B UILDING B ALTI M O R E, M ARYLA N D 21203 ARTH U R E. LUN DVALL, J R.

v.ce p.s..or~e April 19, 1979 so o Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Subject:

Calvert Cliffs Nuclear Power Plant Unit No. 1 & 2, Docket No. 50-317 & 50-318 Fire Protection Program, NRC Review File: 013-261-0, L-037-F

Reference:

NRC letter dated March 19, 1979 from Reid to Lundvall, same subject Centlemen:

The enclosure attached is submitted in response to the referenced letter which forwarded a list of twenty-two staff positions relative to fire protection. Positions P-3, P-4 and P-6 were previously resolved and Position F-14 was combined with P-8, therefore these are not referenced in the enclo-sure attached.

Very truly,yours, .

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cc: J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messrs. E. L. Conner, Jr. - NRC J.W. Brothers - Bechtel 79042403 %

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P-1. FIRE DOOR SUPERVISION Staff Position Fire door should be normally closed and locked er electrically super-vised with delayed alarm annunciation in a constantly occupied area.

Evaluation The BC&E response states that fire doors are normally closed, locked or monitored by the plant security system. The response does not pro-vide assurance that fire doors which are not locked or electrically supervised will be kept closed.

Action Requested BG&E agreed to provide additional information which identifies the doors which are not locked or electrically supervised and the fire hazards on both sides of such doors. Justification for not having these doors locked or electrically supervised should also be provided.

RESPONSE

The doors at Calvert Cliffs can be categorized in the following fashion:

Category No. 1 - Normally Closed and Key Locked No. 2 - Normally Closed and Alarmed Nc. 3 - Normally Closed and Alarmed and Locked No. 4 - Normally Closed and Equipped with Automatic Closers (U/L approved hardware)

No. 5 - Normally Open and Equipped with Automatic Fusible Link Releases (U/L approved hardware)

The doors in Category Nos. 1, 2 and 3 are not of concern to the reviewer as they are normally locked, alarmed or both locked and alarmed in the closed position. There are some 44 Fire Doors which are normally closed, key locked and/cr alarmed (i.e., Category Nos. 1, 2 and 3).

The Table "A" attached identifies Category No. 4 doors which are equipped with U/L approved hardware including automatic sulf-closers. These' doors are located in stair towers and passageways which serve as exit ways for safe egress and access. Characteristically these doors enclose stair towers which are devoid of combustible loading and the doors communicate to passageways or open areas with low fire loads (i.e., the maximum being an equivalent fire exposure of less than 12 minutes).

There are other Category No. 4 doors which are not utilized at stairways or passageways listed in Table "B". These fire doors are equipped with the same U/L approved hardware and closers. These doors are within con-trolled access areas. These doors, in almost every case, are provided for access to rooms equipped with fire suppression or smoke detection systems which are alarmed in the Control Room. The four doors in this category which separate areas devoid of smoke detection, isolate areas characterized by low combustible loading.

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Table "C" lists Category No. 5 doors, those equipped with automatic fusible link releases. These doors are designed and U/L approved for this fire protection application. In most every instance, these doors are rolling - steel type Class A fire doors.

In summation, fire doors are normally closed, locked or monitored by the plant security system. Fire doors which are U/L " approved" are equipped with automatic door closers and hardware sets. These doors self-close when released. They must be purposely blocked open. In addition, the Plant Fire Pretection Inspector performs periodic in-spections in safety related areas assuring that prompt and effective corrective actions are taken to correct conditions adverse to effec-tive fire protection, such as damaged or blocked open doors, in accor-dance with written Calvert Cliffs Instruction 1332 Characteristically passageways, corridors and stairways are not exposed by combustible loadings. Those areas containing concentrations of com-bustibles are provided with fire / smoke detection systems and these systems are alarmed in the constantly attended Control Room. Upon actuation of the fire detection and suppression systems, prompt response of the fire brigade will assure that fire doors are closed as may be necessary.

In addition, those doors in Tables "A" and "B" which are not in con-stantly attended areas or doors not opening to space protected by automatic detection or suppression systems will be verified to be closed end logged by operators once during each eight hour shift.

P FIRE DOOR SUPERVISION -

TABLE "A" Fire Load Door tio. Elevation Space Identification (Btu /ft2) Fire Rating Remarks Stair Tower AB-1, Auxiliary Building 101 (-)15-0 Corridor 100 ( 7,500) B Verified closed and logged by operators each shift.

201 5-0 Corridor 200 ( 6,200) 3 - do -

Stairway AB-2, Auxiliary Building 106 (-)l0-0 Corridor 103 ( 2,100) B - do -

208 5-0 Corridor 219 (15,000) B - do -

312 7-0 Passage 319 ( 2,600) B - do -

427 45-0 Passage 426 (Light) B - do -

535 69-0 Spent Fuel Pool Area (Light) B - do -

Stairway AB-3, Auxiliary Building 402 45-0 Vestibule 400 (Light) B - do -

509 69-0 Passage 513 (Light) B - do -

Stairway AB-4, Auxiliary Building 310 27-0 Passage 308 (Light) B - do -

412 45-0 Passage 410 (Light) B - do -

522 69-0 Personne ; Access 527 (Light) B - do -

TABLE "A" (Continued)

Fire Load Door No. Elevation Space Identification (Btu /ft2) Fire Rating Remarks Stairway AB-5, Auxiliary Building 315 27-0 Passage 308 (Light) B Verified closed and logged by operators each shift.

428 45-0 Passage 410 (Light) B - do -

535 69-0 Personnel Access 525 (Light) B - do -

Corridor Doors, Auxiliary Building 325 27-0 Vestibule to Passage -

A - do -

300 324 27-0 Passage 300 to -

A - do -

Vestibule AB-3 512 69-0 Passage 513 to -

A - do -

Locker Room Passage

_P_ FIRE DOOR SUPERVISION TABLE "B" AUXILIARY BUILDING Door Fire Load Fire Load Fire No. Elevation Space Identification (Btufft2) Space Identification (Btu /ft2) Rating Remarks 308 27-0 Purge Air Room 318 ( 11,000) Switchgear Room 317 ( 26,000) B Fire Detection 303 27-0 Passage 300 ( 0 ) Cable Spreading (107,000) B " "

Room 306 302 27-0 Vestibule AB-3 ( 0 ) Cable Spreading (107,000) B " "

Room 302 329 27-0 CSR 306 (107,000) CSR 302 (107,000) A " "

318 27-0 Purge Air Room 312 ( 11,000) Switchgear Room 311 ( 26,000) B " "

449 45-0 Cable Chase IB (148,000) Switchgear Room 430 ( 43,000) A " "

448 45-0 Cable Chase 1A (178,000) Switchgear Room 430 ( 43,000) A " "

451 45-0 Cable Chase 2B (125,000) Switchgear Room 407 ( 43,000) A " "

450 45-0 Cable Chase 2A (145,000) Switchgear Room 407 ( 43,000) A " "

429 45-0 Electrical Penetra- ( 16,000) Piping Area 428 ( 38,000) B " "

tion Room 429 433 45-0 Computer Room 431 ( 12,000) Control Room 405 ( 8 '00) B Constantly attended and Fire Detection.

407 45-0 Computer Room 406 ( 12,000) Control Room 405 ( 8,300) B Constantly attended and Fire Detection.

411 45-0 Electrical Penetra- ( 16,000) Piping Area 408 ( 38,000) B Fire Detection tion Room 409 425 45-0 Electrical Penetra- ( 70,000) Passage 426 (Light) B tion Room 423

TABLE "B" (Continued)

Door Fire Load Fire Load Fire No. Elevation Space Identification (Btu /ft2) Space Identification intu/ft2) Rating Remarks 413 45-0 Electrical Penetra- ( 72,000) Cask and Equipment ( 1,900) B Fire Detection tion Room 414 Hoom 419 420& 45-0 Solid Waste Room 418 ( 2,100) Cask and Equipment ( 1,900) A Fire Detection 445 Room 419 512 69-0 Corridor 519 ( 7,500) Passage 513 (Light) A Constantly attended

$42 69-0 Clean Locker Room 506 ( 7,500) IIVAC Room 512 ( 8,200) A Verified closed and logged by operators.

540 69-0 Exhaust Equipment (Light) Cable Chase lA (178,000) A Fire Detection Room 524 541 69-0 Exhaust Equipment (Light) Cable Chase 2A (145,000) A Fire Detection Room 526 526& 69-0 Spent Fuel Pool (Light) Passage 553 (Light) B Verified closed and 534 logged by operators.

532 69-0 Electrical Room 529 ( 36,000) Spent Fuel Pool (Light) B Fire Detection 527 69-0 Electrical Room 532 ( 33,000) Cask llandling ( 180) B Fire Detection Area 530 82-9 Ilorizontal Chase 1A ( 93,000) Electrical Room 529 ( 36,000) A Fire Detection 82-9 llorizontal Chase 2A ( 88,000) Electrical Room 53" ( 33,000) A Fite Detection 502 69-0 Clean Locker Room 506 ( 7,500) Turbine Room Unit 1 ( 27,000) A Verified closed and logged by operators.

P FIRE DOOR SUPERVISION TABLE "C" AUXILIARY BUILDING Door Fire Load Fire Load Fire No. Elevation Space Identification (Stu/ft2) Space Identification (Utu/ft2) Rating Remarks 510 69-0 Corridor 508 (7,500) Passage 513 (Light) A Passageway

P-2. ELECTRICAL CABLE PENETRATION QUALIFICATION Staff Position The cable penetration fire barriers should be tested to demonstrate a three-hour rating, as is required for fire barriers. The test should be performed or witnessed by a representative of a qualified indepen-dent testing laboratory. The tests should be performed in accordance with ASTM E-119 and the following conditions:

(1) The cables used in the test should include the cable insulation materials used in the facility.

(2) The test sample should be representative of the worst case con-figuration of cable loading, cable tray arrangements, anchoring and penetration fire barrier size and design. The test sample should also be representative of the cable sizes in the facility.

Testing of the penetration fire barrier in the floor configura-tion will qualify the fire stop for use in the wall configuration also.

(3) Cables penetrating the fire barrier should extend at least three feet on the unexposed side and at least one foot on the exposed side.

(4) The fire barrier should be tested in both directions unless the fire barrier is symmetrical.

(5) The fire barrier should be tested with a pressure differential across it that is equivalent to the maximum pressure differential a fire barrier in the plant is expected to experience.

(6) The temperature levels of the cable insulation, cable conductor, cable tray, conduit, and fire stop material should be recorded for the unexposed side of the fire barrier.

(7) Acceptance Criteria - The test is successful if:

(a) The cable penetration fire barrier has withstood the fire endurance test without passage of flame or ignition of cables on the unexposed side for a period of three hours, and (b) The temperature levels recorded for the unexposed side are analyzed and demonstrate that the maximum temperature is sufficiently below :he cable insulation ignition tempera-ture, and (c) The fire barrier remains intact and does not allow projec-tion of water beyond the unexposed surface during the hose stream test.

If previous tests can be shown to meet the above position, the licensee should provide the results of the tests to show that the above position is met.

Evaluation BGaE takes exception to this requirement for testing the cable pene-trations. They provided the sketches of the penetration designs and contended that various components in the designs have been success-fully tested and the design was approved and accepted by NELPIA. The information provided is not sufficient to establish the fire resistance rating of the penetration. It did not describe the tests, the results or the extent of NELPIA's review.

Action Requested BG&E is requested to provide additional information concerning the tests and NELPIA's documentation that is sufficient to establish the fire rating of the penetrations.

RESPONSE

In our Fire Protection Program Evaluation, we described in detail the materials of construction and design of cable and cable tray penetra-tion fire stops and seals of fire barriers, both vertical and horizon-tal. The following noncombustible materials are utilized in this sub-stantial design:

(1) 1/2-inch Marinite 36A boards: These are composed of noncombustible asbestos fibres, diatomaceous silica and hydrothermally produced inorganic binder.

or 1/2-inch Marinite XL boards: These are composed of calcium sili-cate with inert fillers and reinforcing agents, all of which are noncombustible.

(2) Flamemastic 71A: This is composed of a polyvinyl acetate binder and fire retardant additives which include antimony oxide and a phosphate plasticizer. These materials function synergistically to inhibit the flammability of the binder and all flammable substrates to which the coating is applied.

(3) Verntculite: This is a hydrated magnesium-aluminum-iron silicate (a micaceous mineral ore).

(t ) Kaowool: This is a ceramic fibre, made from Kaolin, a naturally occurring, high-purity alumina-silica fireclay with a melting point of 3200 F.

As indicated in Subsection 8.5.6 of the Calvert Cliffs FSAR, a test was performed te determine the effectiveness of 1/2-inch silicate fire barriers with 3/4-inch separation (Mar'7ite boards). This three-hour test showed that the temperature just above the upper barrier was less than 165 F with an 1800 - 2000 F temperature main-tained just below the lower barrier. (Test data was previously sub-mitted.)

The design of the fire stops are shown on Drawing No. 6150-E-406, Raceway Notes, III, Sheet 22 and 23. These drawings were reviewed and approved by Mr. D. L. Bennett, Engineer-In-Charge, Factory Insurance Association (FIA) acting as the engineering representatives for the Nuclear Energy Liability Property Insurance Association (NELPIA) now kncwn as American Nuclear Insurers (ANI). The design shown on Sheet 22 was used throughout the plant. It is important to recognize that each individual trey is grouted in place to the full thickness of the wall. This grout consisted of a design mix of Port-land cement and sand. The galvanized steel cable trays have covers attached, top and bottom, and have solid metal sides. The covers encapsulate the symmetrical application of Flamemastic 71A, 3" Kaowool and vermiculite to the thickness of the wall as shown on Sheet 22.

The galvanized sheet metal covers, top and bottom, provide physical protection to prevent damage to the in-tray fire stop. Further, the trays are restrained from moving in the blockouts since they are grouted into the wall.

The only deviation to the fire stop and seal described above is that used in blockouts for the Control Room floor to the Cable Spreading Room below. These fire stops and seals are shown on Sheet 23. The blockouts are not over 15" x 14" and they are individually fire stopped and sealed with Flamemastic 71A, Marinite board and vermicu-lite to the depth of the iloor (minimum 2'-3" deep). The conduits and wireways installed in these blockouts are individually sealed where they terminate above the floor. They are packed with 3" Kaowool ceramic fiber and then scaled with Flamemastic 71A.

In addition to the cable penetration fire stops and seals being entirely of and covered by fire resistive material, the cables installed in the trays are for the most part silicone rubber insulation covered with glass braid and an overall asbestos braid jacket. Characteristically, the areas subdivided by three hour fire barriers at Calvert Cliffs con-tain less than two hour fire exposures.

Only three areas have greater than two hour equivalent fire exposures Cr 160,000 Btu /ft2) and all three are equipped with fire detection; two have automatic suppression systems.

Following the Browns Ferry fire, NELPIA surveyed all insured nuclear power plants to evaluate the cable installation and fire stops.

NELPIA's August 18, 1976 report showed that no modifications or tests were recommended for Calvert Cliffs fire stops and seals as a result of the lessons learned frem the Browns Ferry incident.

It is known that other plant fire stop designs were required to be tested under June, 1975 and subsequent guidelines established by NELPIA and in some cases, fire stops were required to be modified.

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P-5. RCS PUMP LUBE OIL COLLECTION SYSTEM Staff Position Each reactor coolant pump should be provided with an oil collection system to contain lube oil leakage and drain the leaked oil to a safe place.

Fealuation BC&E has said that RCS pumps have been equipped with an oil collection system. The information provided is not sufficient to permit an eval-uation of the collection system.

Action Requested BG&E agreed to provide sketches and a description of the RCS pump lube oil collection system.

RESPONSE

To collect potential oil leakage, we will ensure that each reactor coolant pump is provided with two (2) pans whica are tubed (run to) to the containment floor. The oil lift assembly at the upper bearing is provided with a drip pan and the lower guide bearing will be fitted with a large donut shaped pan to collect drip and spray. A sketch (DCN M-825) and photos of the lower pan are attached. Installation of this collection system will be completed during the next refueling outage of each unit.

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P-7. BATTERY ROOM VENTILATION AIR FLOW MONITOR Staff Position A ventilation air flow monitor should be installed in each of the station battery rooms to alarm and annunciate, in the control room, the loss of the ventilation air flow.

Evaluation BG&E does not accept this position on the ground that the ventilation system consists of two fans (one supply and one discharge as verified in the exit meeting) with independent power supplies and that hydrogen are only generated during occasional high-charging periods which are supervised.

The BG&E responsa does not include sufficient information; (1) tc sub-stantiate their contention that two fans, one supply and one discharge, do provide redundancy for the battery rooms ventilation system; (2) describing the method of supervision to be provided. There is no ind' cation to alert the operator of the interruption of ventilation air flow and the subsequent hydrogen buildup if a damper in the ventilation system were to close inadvertently. Hydrogen generation is not limited to the high-charging periods and hydrogen buildup cannot be detected by physical senses of the human being.

Action Recuested BG&E is requested to provide the air flow monitor for the battery rooms as indicated in our staff position.

RESPONSE

BG&E does not concur with the need for a continuous air flow menir .

for the battery rooms. Calculations demonstrate very low hydrogen generation rates. The provision of two fans, one exhaust and one supply, for ventilation of the battery rooms assures against hazardous buildup of hydrogen concentrations.

Hydrogen is generated during charging periods at a maximum rate of 0.3059 cubic feet / hour as shown by calculations attached. The smallest battery room is 221 square feet. If there was no ventilation and it was assumed that there was no circulation of air within the room, we calculate to reach 25% of the lower explosive limit in the top one foot space at the ceiling would take 7.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (221 cubic feet x 4.1% L.E.L.

, of hydrogen x 25% + 0.3059 cubic feet / hour - 7.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). It is hip'ily

, unlikely that this condition could ever occur in view of the fact that:

', (1) There are two fans, one supply and one exhaust. Just the opera-tion of the supply air fan assures circulation and mixing of the 4

hydrogen throughout the room and not just collecting in the one

$ foot space at the ceiling. To reach 25% of the lower explosive limit in the room would take 9 times as long or 66.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . This assumes that none of the hydrogen would be displaced out of the room through the nonoperating exhaust system. (See the attached start up test sheet - H&V Unit 11 - 319 cfm).

4 (2) On the other hand, if only the exhaust fan were to operate, all the hydrogen generated would be removed from the ceiling area.

(See the attached start up test sheet - Battery Exhaust Fan VU 430 cfm).

(3) The likelihood of both fans being out of service simultaneously is minimized by two separate power supplies and individual breakers.

(4) The likelihood of both fire dampers, one in the supply air open-ing and one in the exhaust air duct opening, being closed simul-taneously is extremely remote. These dampers are equipped with individual fusible links.

(5) The hydrogen generation rate used in the calculation represents the highest rate which occurs only when the 59 cell battery is being charged. This high charging rate or hydrogen gas genera-tion takes place rarely and then for periods up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months if the battery should be fully discharged. The batteries are fully discharged once every five years for test and, under such test conditions, operators are assigned to carefully monitor the recharging operation by checking temperatures, voltage, current and other criteria to prevent a hazardous condition from develop-ing.

In view of the staff's concern relative to potential accumulations of hydrogen, we have added instruction. that the operator shall verify air flow through observation of te11 tales at the exhaust and supply air grille in each batterv room twice each shift.

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P-8.* CABLE SPREADING ROOM PROTECTION Staff Position In addition to detection and manual suppression capabilities:

(1) An automatic fire suppression system should be installed in the cable spreading room, and (2) Shutdown capability independent of cabling and equipment in the cable spreading room should be provided unless it can be demon-strated that at least one division of cabling and equipment can be preserved for safe shutdown during and following a major fire.

This position combines previous positions P-8 and P-14.

Evaluation There are two cable spreading rooms in the plant; one for each unit.

Each cable spreading room contains, in addition to redundant safety and shutdown system cables, both divisions of safety-related elec-trical equipment cabinets that are susceptible to heat and water damage. The minimum separation between cable trays from redundant divisions is about 9" vertically and essentially nothing horizontally because trays from redundant divisions cross cach other in several instances. In these cases, Marinite boards, flush with the width of the tray, are provided at the top and the bottom of trays of one divi-sion until they are approximately 3' away from trays of the other divi-sion. Conduits of redundant divisions are routed to within a couple of inches of each other, or of trays, in many places. Trays are generally stacked 5 - 6 trays deep. The access for manual fire fighting is fair, each cable spreading room has one access from outside in addition to the interconnecting doorway between the two rooms. Smoke detectors and por-table extinguishers are provided to protect cabling in the room while total flooding Halon 1301 systems, actuated automatically by heat detec-tors protect electrical equipment cabinets in the room. A manual hose station is available from outside the rooms; however, it has not been demonstrated that the existing hose can effectively reach every point in the rooms. The licensee indicated that he does not favor using water to suppress a fire in the room. Effectiveness of portable extinguishers in fighting a major fire is not demonstrated. The existing detection and manual fire fighting system may not be adequate to ensure that at least one division of cables and equipment can be preserved for safe shutdown in the event of a fire in these rooms.

BG&E does not accept the position that automatic fire suppression systems should be installed in the room on the grounds that the superior fire resistance of the silicone rubber insulated cables have been verified by their own tests.

Silicone rubber insulated, asbestos jacketed cables are used for instru-mentation, control and small power application. All medium and large power applications use cables insulated with conver.tional materials such as cross-linked polyethylene, ethylene proplyene rubber and hypalon.

Flame propagation tests were conducted in the process of selecting such

cables for these services. The procedures and the results of the tests were summarized in the paper titled, " Flame Propagation Tests on 600 volt Control and Power Cables in Trays for Calvert Cliffs Nuclear Power Plant" which was submitted to IEEE International Symposium on January 28, 1971. This paper was referenced in page D-29 of the licensee's submittal, "The rire Protection Program Evaluation."

The flame propagation tests were conducted on a single tray and a hori-zontal stacked tray (2 trays) configurations which include an 8' hori-zontal section with a 4' vertical section on each end. Each tray was loaded with one layer of test cables, one-half diameter apart and sub-jected to 5 minute exposure to transil oil fire in a 5 gallon open-top can. " Circuit integrity" was indicated by measuring leakage currents in open circuits.

Among the major test conclusions are:

1. Silicone rubber cables can maintain the " circuit integrity", pro-vided no water spray was applied, under the fire condition for 40 minutes or more when energized with 120V circuit fused for one ampere.

2. Silicone rubber burns but produces less visible smoke.

3. Under the test condition (maximum of 2 tray stacking, one layer cable fill, 5 minute exposure) silicone rubber cables exhibited a limited flame propagation and self-extinguished 20-25 minutes after the ignition source was removed.

4. Metal conduits delayed, but could not prevent failure of contained cables.

5. With properly applied flame retardant coating, the cable fire self-extinguished under the test conditions as soon as the fire source was removed while the uncoated silicone rubber cable fires generally lasted 20-25 minutes after the ignition source was removed.

The licensee cites these test results as justification for taking excep-tions to guidelines of Appendix A to BTP 9.5-1. The staff has reviewed the report cited above and concludes that these tests results alone do not provide adequate justification for taking such exceptions. For example:

1. Section F.3.(a).1 of Appendix A to BTP 9.5-1 provides: "The primary fire suppression in the cable spreading room should be an automatic water system".

The licensee contends that automatic water systems are not necessary because safe shutdown of the plant is assured by the capacility of sili-cone rubber cables to maintain the " circuit integrity" during and fol-lowing a fire and because the cables are difficult to ignite, slow to propagate fire and self-extinguishing in the absence of an ignition source.

. The staff concludes that while these statements may be true for the test configuration they may not be true for the actual configuration.

In the configuration observed in the CCNF' cable spreading room, a large concentration of cables presents i- a confined space (stacks of 5-6 trays, less than one foot between trays, up to and exceeding 100*4 tray fill). A fire involving cables in such a configuration is likely to be prolonged and sustained because of a heat energy feedback to the fire that is higher than that of the test configuration. The licensee's tests do not establish that such a cable fire would self-extinguish.

While the tests showed that when silicone rubber cables are exposed to a fire, leakage current in open circuits is less than 1 ampere at 120 volts they do not demonstrate that silicone rubber cables involved in a fire are capable of actually carrying 1 cads required by their functions for an extended period of time during and following c fire. Moreover, the rooms also contain some conventional cables that are susceptible to fire damage. The licensee's contention that the circuit integrity can be maintained to preserve the safe shutdown capability in the event of a fire in the cable spreading room, therefore, cannot be substantiated.

Furthermore, the licensee has not shown that he has casualty procedures that benefit from such circuit continuity or how fire fighting effort would be affected by such procedures.

The cable spreading rooms also contain electrical equipment which are susceptible to heat and water damage. The licensee has not evaluated the effects of a fire or fire fighting activities on such equipment.

It has not been demonstrated that the plant can be safely shut down without these equipment.

2. Section F.3(a).3 of Appendix A to BTP 9.5-1 provides: "Each cable spreading room should have divisional cable separation by 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months rated fire wall. For cable spreading room that do not provide divisional cable separation by 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months fire wall, all cables should be coated with a fire retardant coating and adequate divisional cable separation should be provided."

The licensee contends that the silicone rubber cables are covered with glass braid and asbestos jacket which by design has a fire retardant coating (asbestos). An additiional fire retardant coat-ing is,therefore, not required.

The staff concludes that based on the licensee's tests, the asbestos jacket is not equivalent to retardant coating. The licensee has not evaluated the effects of non-silicone rubber cables which are in the cable spreading room on flame propagation.

Divisional separation of cables in trays and in conduits were discussed in the " Staff Concern". The licensee contends that the separation is adequate. The staff concludes that the licensee has not provided ade-quate evidence to justify his contention that at least one division of safety-related cables can be preserved for safe shutdown in a room with the above described configuration when the effects of a fire or fire fighting activities, including a possible spray of fire water, are taken into account.

Action Requested BG&E is requested to provide: (1) an automatic fire suppression system in the cable spreading room; and (2) an alternate shutdown capability independent of the cabling and equipment in the cable spreading room.

RESPONSE

The arrangement of the Calvert Cliffs cable spreading rooms as described above in the staff evaluation for this Position is unique. Silicone rubber insulated, asbestos-jacketed cable with clearly superior fire resistive qualities and demonstrated lower heat content has been used almost exclusively in these rooms. The cable installation also meets separation criteria established in Regulatory Guide 1.75. Potential ignition sources in relay cabinets have been protected by individual fixed automatic Halon 1301 systems. An early warning fire detection system has been installed to alarm to the Control Room and assures prompt response by the fire brigade. Manual fire fighting equipment in the form of portable extinguishers and pre-connected 1 inch hose lines have been installed; the adequacy of hose lines was demonstrated by hose stretch tests performed to meet Position P-13. We strongly believe that the foregoing represents a well designed fire protection system that provides good assurance that the function of the cable spreading room cannot be impaired by fire.

However, to alleviate staff coicerns regarding the effectiveness of manual fire fighting capability and applicability of " Flame Propaga-tion Tests on 600 Volt Control and Power Cables in Trays for Calvert Cliffs Nuclear Power Plant", we will design and install a fixed auto-matic Halon 1301 fire suppression system for each of the cable spread-ing rooms.

In response to the second action requested, we are performing an analy-sis to demonstrate that with all the foregoing fire protection systems a fire in the cable spreading room will not cause simultaneous loss of function to redundant cables or equipment required for safe shutdown.

In the unlikely event this cannot be demonstrated, modifications neces-sary to preserve the operability of at least one system required for safe shutdown will be made.

P-9. SEPARATION CRITERIA Staff Concern The tests, as referred in the licensee's submittal, " Fire Protection Program Evaluation", dated March 1977, which were performed during the process of selecting silicone rubber insulated, asbestos jacketed cables to be used at Calvert Cliffs Nuclear Power Plant (CCNPP) do not represent actual configurations of tray loading and raceway arrangement generally observed in the plant. In addition, silicone rubber cables are used only for instrumentation, control and small power application.

Cables insulated with cross-linked polyethylene, ethylene proplyene rubber, and hypalon are used for larger power application. The staff, therefore, is unable to conclude that cables used in CCNPP combined with the separation provided at the plant provide adequate protection in the event of an unmitigated fire.

Staff Position Provide the results of tests or analysis to demonstrate the effective-ness of CCNPP cables, in the configuration found at the plant, in pre-venting simultaneous loss of function to redundant divisions of cables required for shutdown from an exposure fire; or provide modifications necessary to preserve the operability of at least one division of systems required for safe shutdown.

RESPONSE

All areas containing cable to equipment required for shutdown /cooldown and for Regulatory Guide 1.29 radioactivity release control are being reevaluated to ensure at least one method of shutdown /cooldown is available following the applicable maximum exposure fire. Modifica-tions will be provided if necessary to meet the above criteria.

o P-lO CABLE IN CONDUIT Staff Concern The information provided in Section 8.5.5.h of Calvert Cliffs FSAR Rev. 5/3/73 and the observations during the site visit revealed that no separation criteria have been established for the routing of conduits containing safety related cabic.

Staff Position

1. Provide the results of test or analysis to demonstrate that the asbestos jacketed silicone rubber cable routed in conduit will maintain its function during and following a fire.

2. For other types of insulated (safety-related)I cables routed in conduit within a fire area additional protection should be pro-vided unless it can be demonstrated that the loss of such cables will not produce adverse effects on the shutdown capability of the plant or result in excessive radioactivity release.

RESPONSE

The analysis discussed in P-9 is an investigation of all cable required for shutdown /cooldown and for Regulatory Guide 1.29 radioactivity release control. All situations involving redundant cables in conduit and the applicabic exposure fire will be evaluated to determine whether (a) additional tests are needed to demonstrate adequacy of separation, or (b) additional protection is necessary.

1 Safety-related systems are systems serving those functions as identified in Regulatory Guide 1.29.

P-11. FIRE HAZARDS ANALYSIS Staff Concern The licensee's analysis, dated March 15, 1977, has not provided suf-ficient information for the staff to conclude that the capability to safely shutdown the plant will be preserved in the event of a major fire.

Staff Position Provide an analysis which will demonstrate that a safe shutdown capa-bility will be maintained, and excessive radioactivity release will not result, in the event of a major fire in any area of the plant.

The size of the postulated fire should be based on the combustibles in the area and a maximum amount of transient combustible that may be reasonably expected to be brought into or moved through the areas for maintenance and routine operation. The analysis should include the following consideration:

1. Loss of offsite power simultaneous with the fire,

2. Damage to cabling and equipment resulting from the fire water application and froe other fire fighting related activities,

3. Spurious system transients resulting from fire induced faulting of electrical ccbles.

4. Effects of smoke and heat building up within the fire ares and their propagation via vnsealed openings and penetrations in barriers,

5. Where assumptions are made as to the operability of cables or equipment during and/or following the postulated fire such assumptions should be demonstrated by tests and/or verified by analyses.

Where it cannot be shown that a safe shutdown capability exists during and following the postulated fire, the licensee shall propose appro-priate modifications such as an alternate shutdown capability or bar-riers to p:otect the equipment. Additional suppression in lieu of barriers may be considered on a case by case basis.

RESPONSE

The analysis discussed in P-9 will include equipment as well as cable, and is therefore the " fire hazards analysis" requested here. The assumptions of the analysis include the " considerations" l'sted in the staff position. It is expected that substantial equipment modifications and/or additions will be required because of the several significant constraints added by the staff since our initial analysis. Decisions on equipment modifications / additions will include consideration of adding fire suppression capability in lieu of additional shutdown /

cooldown equipment if such an option is advantageous.

P-12. DETECTION Staff Concern During the site visit it was observed that many safety related areas are not provided with automatic fire detection. Thttefore, a fire in these areas may not be promptly detected.

Staff Position Fire detection should be provided in all areas which contain redundant division of safety related cables and/or components.

RESPONSE

Many areas containing redundant divisions of safety related cables and components are currently provided with automatic fire detection.

These are Rooms 311, 317, 302, 306, 405, 430, 407, 429, 409, 423, 414, 416, 421, 422, 532, 529 Vertical Cable Chase Arez 1A, IB, IC, 2A, 2B, 2C and Horizontal Cable Chase Area U-1 and U-2 as identified in our Fire Protection Program Evaluation. The analysis discussed in P-9 will identify those additional areas which contain necessary cables and components for shutdown /cooldown and for meeting Regula-tory Guide 1.29 radioactivity release controls. We will provide automatic fire detection in those rooms which contain divisions as determined by the analysis.

P-13. FIRE HOSE C0VERACE Staff Concern During the site visit it was observed that many plant areas are beyond the reach of presently provided interior hose.

Staff Position Hose stretch tests should be performed and additional interior hose or hose station provided as necessary to ensure that all points in each safety related area and area containing large fire hazards which may expose safety-related equipment can be reached by at least one effec-tive hose stream. The length of the hose at each station should be limited to 100 feet maximum.

RESPONSE

Hose stretch tests have been performed. Additional lh" fire hose has been added to existing hose stations at Elevation 45'-0" and 27'-0" so as not to exceed 100 feet at each station. Eight additional hose stations are proposed for the Auxiliary Building, Elevation 69'-0" and 45'-0" and for the Intake Structure, Elevation 12'-0". Hose sta-tion design and installation will be as shown on Figure E-1 of the Fire Protection Program Evaluation (see the detail of Type "C" Hose Station).

Preliminary engineering and design is being performed now to provide hose stream protection in those areas containing safety related areas and areas containing large fire hazards.

P-15. COMMUNICATION Staff Concern A fire at the common electrical penetration containing both normal sound powered and page/ party systems could disabic both cnmmunication systems into the containment.

Staff Position These two systems should be separated in such a manner that a single fire will not disable both communication systems into the containment.

RESPONSE

We have performed a successful test of existing radio communication equipment from within the containment. Operating and security per-sonnel are issued this type of equipment which will serve as the separate and independent communication system.

P-16. VALVE IDENTIFICATION Staff Concern P.I.V.'s and control valves for Fire Suppression Systems should be easily identified to permit rapid control for the Fire Suppression Systems in the event of need due to failure or fire control requirements.

Staff Position Provide identification tags, stencils, labels or appropriate signs, on the valve that will allow for the ready identification of each of the valves conttol area without need for reference to written descrip-tions or reference numbers.

RESPONSE

Each valve in the fire suppression water system, except instrument stops, will be provided with an identification tag. Each stainless steel tag will identify the valve by number and provide a sufficient description to facilitate identification of the valves function by a qualified plant operator.

P-17. MANUAL FIRE FIGHTING EQUIPMENT Staff Concern Manual fire fighting is either the primary or the sec,ndary fire srppression system for many areas of the plant and requires ade-quate fire fighting equipment to effectively carry out the func-tiens of fire fighting.

Staff Position Provide the following ad,ditional equipment for each exterior hose cabinct; 200' - 2 " hose (single jacket-lined-synthetic); one (1) 2h" x 1h" x 1h" gated wye; one (1) 2h" combination fog / straight stream nozzle rated at 250 CPM (or more); one (1) 14 fog / straight stream nozzle rated at 60-90 CPM, 2 cach of 2h" ano at" hose gaskets.

All hoses, 2h" and th" stored in the exterior hose cabiner.s should be stored in donut rolls.

All exterior hose cabinets should be cleaned and equipment contained therein should be maintained in proper working order at all times.

Interior standpipe hose stations should be provided with one (1) universal type hose spanner that can be used as a hose valve wrench and as a hose coupling spanner for both 2h" and ik" hose.

Additional fire fighting equipment to be provided in each portable fire equipment cabinet includes the following:

50' - 2h" Fire llose 1 - Halligan type forcible entry tool 100' - 1 " Fire Hose Fire fighting equipment that should be provided at a suitabic central location should include: one (1) heat seasing device; ten (10) sets of fire fighting protective clothing 1.e. - 10 (ten) fire fighting helmets; 10 turnout coats w/ removable liner; 10 pa*r fire fighting boots; 10 pair gloves.

Provide proper sanitizing solution for the sanitization of self-contained breathing apparatus face masks.

Relocate the self-contained breathing apparatus recharging system from the present location in warehouse #1 to a suitable central location within the Unit 1 - Unit 2 operating areas.

Provide a cooling water tank for each cascade system for air cylin-ders being recharged.

RESPONSE

BG&E intends to comply with the staff position.

P-18. EMERGENCY LIC!! TING Staff Concern Many of the fixed sealed beam emergency lighting units were observed to have a rating of only 1h hours as compared to the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rating prescribed by appendix A to BTP9.5-1.

Staff Position Fixed sealed beam lighting units should be provided to facilitate access for fire fighting, egress, and emergency operation of equip-ment in safety related areas. Each lighting unit should have a rating of at least 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

RESPONSE

The Control Room has a permanently installed emergency lighting cir-cuit which is supplied from 125 VDC battery #22. All other areas of the plant contain fixed emergency lighting supplied from individually contained batteries which automatically actuate upon loss of normal AC lighting power. The battery power supplies. rated at I hours, are sufficient to facilitate personnel egress from the affected areas.

Fixed emergency 'd;hta. whether rated at 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or lh hours must be positioned to facilitate e3rass and are therefore not placed in the most favorable location to support operation of equipments or fire fighting. Another more effective approach would be to maintain a number of portable sealed beam lanterns which may be concentrated at the affected areas. Accordingly we intend to store a sufficient num-ber of such lanterns in each Emergency Fire Equipment Locker to pro-vide fire fighting and operations personnel with adequate lighting for a period of eight hours. As these portable units may be posi-tiened to best advantage at the scene of the fire or elsewhere as required, they will be more affective than a much larger number of fixed units. Since installation of 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rated fixed units would not eliminate the need for the more effective nortable units and would add little to the effectiveness of fire fighting or operations personnel their installation is not warranted.

P-19. FIRE PUMP SEPARATION Staff Concern Redundant fire pumps as well as diesel day tank are located in the same room and are subject to damage from a single fire in the pump house.

Staff Position A three-hour rated fire barrier should be provided to separate the redundant fire water pumps so that the availability of at least one fire water pump can be assured in the event of a fire in the pump house.

RESPONSE

The fire pump house is protected by automatic sprinklers. The auto-matic sprinkler wager supply is not solely dependent on the redundant fire pumps for voluno and pressure. The sprinkler system volume and pressure is assured by the 10,000 gallon pressure tank installed at Construction Warehouse No. 1. This pressure tank is equipped with an attomatic air compressor which maintains adequate pressure to supply all automatic sprinkler nozzles operating simultaneously. The tank is equicoed with supervisory alarms connected to the Control Room to assure that the pressure tank is kept filled and pressurized.

The autom3 tic s;r nklar system serves as both a fire suppression and detection system. It is equipped with an alarm check valve with water flow pressure indicator and valve monitor switch connected to the Plant Control Room. In addition, the system is equipped with a local water motor gong alarm. Motors, controllers, the dicsci engine end other equipment are drip proof, shielded or capable of operating with sprinklers operating in the room. The American Nuclear Insurers specifically recommended automatic sprinkler protection for this Fire Pump House.

Finally, the pumps are covered by Technical Specification 3/4.7.11 which establishes that the fire pumps shall be operable "at all times" or corrective steps shall be taken. The occupancy of the Fire Pump llouse is limited to the fire protection water supply function. The Fire Pump House is separated from other structuies by clear space to preclude potential damage from fire exposures and mechanical injury.

The building is locked and secured from unauthorized entry. The fire pump availability and operation are supervised and alarmed in the Plant Control Room.

When all of the above facts are considered, availability of at least one fire water pump is assured without the addition of a fire barrier.

r .. e P-20. FIRE WATER USAGE Staff Concern The licensee's Fire Protection Program Evaluation, dated March, 1977 (page E-12), stated that when water stored in fire water tanks is used for services other than fire protection it will be drawn through the internal standpipe thereby assuring that the minimum of 300,000 gallons per tank will be reserved for fire pror.ection. However, during the site visit it was observed, contrary to the above statement, that fire water drawn through the fire pumps was used for unidentified purposes other than fire protection.

Staff Position (1) Fire sater should be physically dedicated for fire use. Use of water stored in the tanks for services other than fire protection should be limited to that drawn through the inter-nal standpipe without using the fire pumps.

or (2) Identify all other uses (including purpose, flow rate, con-sumption etc.) of fire water and provide the results of an analysis to demonstrate that such uses will have no adverse effects on the availability of water for fire use.

RESPONSE

Technical Specification 3.7.11.1 states that the fire suppression water system shall be operable with two water supplies, each with a minimun contained volame of 300,000 gallons and specifies actions to be taken by the licensee if either supply is not available.

Therefore restriction on water usaga provided that the above Limiting Condition for Operation (LCO) is satisfied,is not appropriate. Cal-vert Cliffs design incorporates several features which insure that the LCO will not be violated. These include a low water level alarm on each tank, remote level indication on each tank, and auto.natic makeup to each tank via redundant (3) well water pumps. Additionally the level in each tank is noted and logged every four hours by plant operators.

Water is withdrawn from the pretreated water storage tanks periodi-cally on a non routine basis for washing intake screens, condenser waterboxes, heat exchanger bulleting, and other similar uses. In each case the withdrawal is accomplished via a single 1% inch hose.

Therefore the withdrawal of water for non-fire fighting purposes is less than the capacity of the well water pumps (300 gym each) which automatically maintain the centained volume of each tank at greater than 450,000 gallons.

In the event of a fire, plant procedures insure that non-fire fighting water usage is immediately terminated, thus insuring that the full capacity of the fire pump will be available to combat the fire.

. .. e Though our evaluation demonstrates that pressure and volume require-ments for fire usage are not impacted adversely by the identified intermittent use, it is prudent that we provide a larger make-up pump to reduce wear and tear on the electric fire pump. To prevent repetitive starts of the fire pump, we intend to provide a centrifu-gal pump to take suction from the pretreated water tank standpipe and to discharge to the fire protection syctem header with adequate capacity to meet the intermittent use.

. .. I P-21. CONTROL OF COMBUSTIBLES Staff Concern Excessive combustible materials were observed in some plant areas, posing unnecessary fire hazards.

Staff Position Combustible materials which are not required for routine plant opera-tional and maintenance activities should be removed from the safety related areas. Storage of combustible materials in safety related areas which are needed for plant operational and maintenance should be restricted to approximately one week's supply. Storage of combus-tible materials in the close proximity or directly under safety related cabling or components (e.g., hot machine shop and nearby hallway) should be prohibited.

RESPONSE

Storage of combustible material within safety related areas will be restricted to approximately a one week's supply. Storage of addi-tional combustible materials inside or adjacent to safety related buildings or systems will be prohibited except where such combus-tibles are stored in covered metal containers (i.e., drums or cabi-nets). No combustible material will be stored directly under safety related cabling or components.

% s )

P-22. FIRE WATER SYSTEM OVERPRESSURE Staff Concern During the site visit, steady pressure of up to 275 psig were observed in the sprinkler systems in the turbine building, the fire pump house, and elsewhere. Fire pump shut-off head as confirmed by the licensee is 175 psig. The cause of such abnormally high pressure in the fire water system is unknown; it cannot be produced by the fire pump. Such over-pressurization could be detrimental to the fire water system.

Staff Position The cause of overpressurization should be identified and corrected.

unless it can be demonstrated that the cause and consequences of such overpressurization are not detrimental to the fire water system or to the plant safety.

RESPONSE

The cause of "overpressurization" has been identified with the on-off operation of the electric motor driven fire pump and its check valve.

A work order will be issued to install h" pressure relief valves on all thirteen alarm check valves which trap pressure surges. These relief valves will be set to open at 175 psi. This work should be completed in 1979.

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