ML20056C339

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Forwards SSAR Markup Addressing COL Action Item 9.5.1.5-1 Re fire-related Administrative Controls
ML20056C339
Person / Time
Site: 05200001
Issue date: 05/12/1993
From: Fox J
GENERAL ELECTRIC CO.
To: Poslusny C
Office of Nuclear Reactor Regulation
References
NUDOCS 9305190272
Download: ML20056C339 (4)


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May 12,1993 Docket No. STN 52-001 i

Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Review Schedule - Fire-Related Administrative Camtrols

Dear Chet:

Enclosed are SSAR markup addressing COL Action Item 9.5.1.5-1.

Please provide a copy of this transmittal to Butch Burton.

Sincerely, Y

ack Fox Advanced Reactor Programs cc: Mohsen Nik-Ahd (GE)

Norman Fletcher (DOE)

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'ABWR col 2M00AH nev. s Standard Plant s

of a fire is that it may incapacitate one safety (3) if not such a graduate, shall have or safe shutdown division. This is consistent completed not less than 12 years of with the single failure design criteria used engineering practice of progressive throughout the plant. Regardless of the location importance indicative of growth in of a fire, sufficient operable equipment is engineering competency and achievement, assured for use in safely shutting the plant three of which shall have been in down.

responsible charge of fire protection engineering work.

The fire hazard analysis assumes that the function of a piece of equipment may be lost if 9.5.15.2 Quality Assurance (QA) Program the equipment is either involved in fire fighting activities or subjected to fire suppresion agents Quality assurance policies and procedures are and confirms that redundant equipment out of the described in Chapter 17. They provide compli-fire area is availabic. This redundant equipment ance with the criteria of 10CFR50 Appendix B.

is capable of performing the required safety or The program defines the requirements and con-shutdown function. The basis of the design is trols for activities affecting quality of struc-not to assume a questionable limit on damage tures, systems and components to an extent con-within a given fire area but to provide redundant sistent with their importance to safety.

equipment elsewhere.

93.1.5.3 Emergency Response Plan As described in Appendix 9A the fire detection systems are Class A, and therefore are tolerant Out of ABWR Standard Plant scope.

of single failure.s. The fire suppression systems are designed such that there are two suppression systems available to any givcn area. Areas cov-

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cred by sprinklers or foam systems are also cov-

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ered by the manual hose system. Areas covered by iN SGN A manual hose systems only may be reached from at least two hose stations. Standpipes are fed from two directions.

9.5.1.4 Inspection and Testing Requirements Preoperational inspection and testing requie-ments will be prepared for each fire protection system as described in Subsection 14.2.12.

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9.5.15 Personnel Qualifications and Traininb r tr 6 m m s % M v t Co vAv-c 9.5.1.5.1 Fire Protection Engineer The qualification requirements of tbc fire pro-tection engineer are as follows:

(1) a graduate of an engineering curriculum of accepted standing; (2) shall have completed not less than right years of engineering practice of progressive importance indicative of growth in engineer-ing competency and achievement, three of which shall have been in responsible change of fire protection e gineering work; or 9.5-13 Amendment 22 i

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4 9.5.1.5.(JAdministrativeControls q4h wRc wdl Thedescriptionofadmin[strativecontrols hat will be established to govern i

various details of operations of the plant conform to guidelines of BTP APCSB 9.5-1,4r: 1:c:pt F

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However, a detailed review and acceptance of the administrativecontrolshillbeperformedduringtheplant-specificlicensing process of a COL application.referer.:ing th: C: A0'"' 9:!A Items of interest under the administrative controls review will include but not be limited to:

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control of combustible materials such as combustible / flammable liquids and gases, fire retardant treated wood, plastic materials, and dry ion

.i exchange resins E.

transient combustible materials and general housekeeping, including health physics materials 3.

open-flame and hot-work permits and cutting and welding operations i

4 quality assurance with respect to fire protection systems components, installation, maintenance, and operation 5.

qualification of fire protection engineering personnel, fire brigade members, and fire protection systems maintenance and testing personnel 6

instruction, training, and drills provided to fire brigade members ne Coi a b

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~g cow 4c,l3 Desian certification riaieriei AsstatedaboveinSection9.5.1.3ofthisr7po~rt,GEprovidedTur1 design description and ITAAC for the fire protection system which are under staff a

review. The results of the staff's review will be provided in the FSER.

i (This is Open Item 9.5.1.3-1.)

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l 9.5.1.6 Summary The staff finds that the fire protection design for the ABWR will be accept-able upon approval of ITAAC.

Most of the fire protection features described in SSAR Section 9.5.1 and SSAR Appendix 9A (Fire Hazards Analysis) of the ABWR application conform to the applicable sections of APCSB BTP 9.5-1.

However, three exceptions to such conformance exist in (1) the main steam tunnel, (2) the main control room, and (3) inside containment.

In each of these three j

instances, the exceptions were fully justified by GE as previously discussed and found acceptable by the staff.

i Finally, as discussed in Section 9.5.1.5 of this report the administrative controls will be the responsibility of the COL applicant.

I 9.5.2 Communications Systems This topic is discussed in Section 7.7.15 of this report.

ABWR DFSEP.

9-83 October 1992 i

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cot 9. s. t. s - 1 Standard Plant

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nEv s 9.5.'13.16 NIJREG/CR-0660 Diesel Generator Reliability Recommendations Programs shall be develor ed to address NUREG/CR-0660 recommendations regarding training, preventive maintenance, and root-cause analysis of component and system failures.

'9.5.14 References 1.

Stello, Victor, Jr., Design Requirements Related To The Evolutionary Advanced Light Water Reactors (ALWRS), Policy issue, SECY-89-013, The Commissioners, United States Nuclear Regulatory Commission, January 19, 1989.

2.

Cote, Authur E., NFPA Fire Protection Handbook, National Fire Proteu,an Association, Sixteenth Edition.

3.

Design of Smoke Control Systems for Buildings, American Society of Heating, Refrigerating, and Air Conditioning Engineers, Inc., September 1983.

4.

Recommended Practice for Smoke Control Systems, NFPA 92A, National Fire Protection Association,1988.

5.

Life Safety Code, NFPA 101, National Fire Protection Association.

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