ML20058P906

Forwards SSAR Markup of GSI 82 That Responds to Issues Raised by Plant Sys Branch During 931008 Telcon

ML20058P906
Person / Time
Site:	05200001
Issue date:	10/20/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
REF-GTECI-082, REF-GTECI-NI, TASK-082, TASK-82, TASK-OR NUDOCS 9310250293
Download: ML20058P906 (5)

Text

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. 8X. I il~ '93 (f8: 44d1 P.E GE Nucinar En:rgy Generr hettre camcs'v I15 grtrer A,e%n ht Jose, CA 95125 -

Docket No. 52 001 October 20,1993 Chet Posiusny, Senior Project Manager e

i Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Schedule GSI 82

Dear Chet:

Enclosed is a SSAR markup of OSI 82 that responds to the issues raised by the Plant Systems Branch during an October 8,1993 telephone call.

I' lease provide copies of this transmittal to Butch Hurton and Melinda Malloy, Sincerely,

(

• N Jack Fox Advanced Reactor Programs cc:

Alan Beard (GE)

Norman Fletcher (DOE)

Bernie Genetti GE)

Doug Mcdonald (OE) 1747:6 9310250293 931020 t

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23A8100 Rev. 2 stentient setety Analysis nepors ABWR owner opemtor must perform penodic inservice inspection in accordance with ASME r

Code Section XI and References 19B.2.62 3.19B.2.62-4 and 19B.2.62-5. In addition, for c.itical pressure boundary applications such as the reactor vessel head closure, redundant seals and leak monitoring further assure the integrity of the RCPB.

Therefore, this issue is resolved for the ABWR Standard Design.

t References I9B.2.62-1 NUREG-0933, A Pnontizatwn of Generic Safety Issues (with Supplements), U.S.

NRC, July 1991 19B.2.62 2 Amentan Society ofMechanicalEngineers Boiler and Pn"ssure Vessel Code, Section ill (Nuclear) and Section XI, American Society of Mechanical Engineers.

9 198.2.62-3 NUREG-1339 Resolution of Gmenc Safety Issue 29: BoltingDegradation or Failure un Nuclear Power Plant.s. U.S. NRC, June 1990.

19B.2.62-4 EPR1 NP 5769. Degmdation and Failure of Bolling in Nuclear Power Plants.

19B.2.62-5 Generic Letter 91-17, Genenc Safety issue 29, 'BoltingDegradation orFailure in Nuclear Power Plants *, U.S. NRC.

198.2.63 82: Beyond Design Basis Acoldents in Spent Fuel Pools Issue Issue 82 in NUREG-0933 (Reference 19B.2.63-1), addresses the potential for a beyond-design basis accident in which the water is drained out of the spent fuel pool. In such an event the discharged fuel from the last two refuelings may have sufficient decay heat to melt, ignite the zircaloy cladding and release fission products to the aunosphere.

Acceptance Criteria The acceptance criteria for the resolution ofissue 82 is that the design of the spent fuel pool, storage racks, fuel pool cooling and cleanup system and the load handling equipment in the spent fuel pool area shall meet applicable current requirements,i.e.,

the guidance of the Standard Review Plan (SRP) Sections 9.1.2 -9.1.5 (Reference 19B.2.63 2) and Regulatory Guide 1.13 (Reference 19B.2.63 3).

Resolution ThhAB%) design includes a spent fuel storage facility, a fuel pool cooling and cleanup -

k-A i 0 Ip' syste)b add a fuel hand!ing system that meets the intent of Regulatory Guide 1.13 and 3 'A ii 5 SRP 9M2 - 9.1.5 as described in Section 9.1, Fuel Storage and Handling. Since the acceptake criteria are met for the spent fuel storage facility, this issue is resolved for the'ABhb i

198 107 l

Resolutlon of App!rcable Unresolved Safety Issues and Generic SafetyIssues - Amendment 32

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- P.4 Insert 19B.2.63 The ABWR design includos a spent fuel storage facility, a fuel pool cooling and cleanup system and a fuel handling system that meet the intent of Regulatory Guide 1.13 and SRP 9.1.29.1.5 as described in Section 9.1, fuel Storage and Handling. A brief summary of the design features relating to the Regulatory Guide and the SRP follows.

The spent-fuel pool and storage racks are Seismic Category I structures.

The spent-fuel pool is in the Reactor Building which is also Seismic Category I. There are no non-seismic systems, high or moderate energy pipes, or rotating machinery located in the vicinity of the spent-fuel pool or cask loading area on the refueling floor.

• The Reactor Building protects the fuel and spent-fuel pool from tornadic winds and the missiles generated by these winds. The Reactor Building also prevents turbine missiles from effecting the spent-fuel pool.

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• Interlocks prevent the movement of heavy loads over the spent fuel pool.

Heavy loads are defined such that if inadvertent operations or equipment malfunctions either separately or in combination, could (1) a release of radioactivity, (2) a criticality accident, or (3) the cause:

inability to cool fuel within the spent-fuel pool.

= The Standby Gas Treatment System limits the potential release of radioactive iodine and other radioactive materials from the Reactor Building which encloses the spent fuel pool.

The travel of the Reactor Building crane which handles heavy loads, including the fuel casks, is limited by interlocks to preclude movement I

over the spent-fuel storage pool.

• No inlets, outlets or drains are provided that might permit the pool to be drained below a safe shielding level. Lines extending below this level are equipped with siphon, breakers, check valves, or other suitable devices to prevent inadvertent pool drainage.

• A level switch is provided in the spent fuel pool to alarm locally and in the control room on either high or low level. The Fuel Handling Area Ventilation Exhaust Radiation system monitors the offgas radiation levelin the fuel handling area ventilation exhaust duct. A high-high radiation trip results in the initiation of the Standby Gas Treatment System and in the isolation of the secondary containment (including.

closure of the containment purge and vent valves and closure of the Reactor Building ventilation exhaust isolation valves).

• The Fuel Pool Cooling and Cleanup (FPC) System provides the primary means of maintaining the water level in the spent-fuel pool utilizing a connection to the Condensate System. The Suppression Pool Cleanup

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- (SPCU) System can be used as a backup. Both the FPC and SPCU Systems are Seismic Category I designs. Additionally, connections from the RHR System to the FPC System provide a Seismic Category I, safety-related makeup capability to the spent-fuel pool. The FPC System from the RHR connections to the spent fuel pool are Seismic Category I and safety-related. The RHR system cormections will he protected from the effects of pipe whip, internal flooding, internally generated missiles, and the effects of a moderate pipe rupture. Furthermore, fire hoses can he used to supply water from the fire protection system to the spent-fuel pool.

Since the acceptance criteria are met for the spent fuel storage facility, this issue is resolved for the ABWR.

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This page plus _L_ page(s)

Mail Code azz.

From act rox 175 Curtner Avenue San Jose, CA 95125 FAX (408) 92 5 1193 Phone (408) 925-3 824 _

or (408) 925168/

Subject suemittel sucoortina Accelerated ABWR Review Schedule -

GSI R2 Message I

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