ML20133J324

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Responds to Request for Proposed Implementation Schedule for 10CFR50.62 Requirements for Reduction of Risk from Atws.Exemption from 10CFR50.62(c)(5) Requested Due to Limited Benefits of Automatic Recirculating Pump Trip
ML20133J324
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 10/14/1985
From: Frisch R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Office of Nuclear Reactor Regulation
References
GL-85-06, GL-85-6, NUDOCS 8510180380
Download: ML20133J324 (3)


Text

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Consumers Power Company General offices: 1945 West Parnall Road, Jackson, MI 49201. (517) 788-0550 October 14, 1985

Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

IMPLEMENTATION SCHEDULE FOR 10CFR50.62 REQUIREMENTS FOR REDUCTION OF RISK FROM ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS)

In July,1984 the NRC published requirements (10CFR50.62) for the reduction of risk frcm anticipated transients without scram (ATWS). This rule requires licensees to submit a proposed schedule for meeting the requirements of paragraphs (c)(1) through (c)(5) by 180 days af ter the issuance of QA guidance for non-safety related components. The QA guidance was issued in Generic Letter 85-06 dated April 16, 1985. Accordingly, the requirements that apply to Big Rock Point are summarized as follows:

10CFR50.62(c)(3)

Alternate rod injection system (diverse from the existing reactor protection system) 10CFR50.62(c)(4)

Liquid poison control system which has an equivalent capacity of 86 gpm of 13 weight percent sodium pentaborate solution 10CFR50. 62(c) (5)

Automatic recirculating pump trip Our response to these requirements is as follows:

Alternate Rod Injection System - 10CFR50.62(c)(3)

Consumers Power Company will perform risk based evaluations to determine the efficacy of alternate rod injection. This work will be ranked and scheduled as part of the Big Rock Point Living Schedule. Future updates and status reports will be provided with Living Schedule. updates.

8510180380 851014

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o Director, Nuclear Reactor Regulation 2

Big Rock Point Plant Implementation Schedule - ATWS October 14, 1985 Liquid Poison Control System - 10CFR50.62(c)(4)

Equivalent control capacity for standby liquid control was defined by the NRC in a letter dated January 28, 1981 (Generic Letter 85-03). The Big Rock Point liquid poison system exceeds the requirements of this rule. Smaller vessels

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require proportionally less sodium pentaborate flow to meet the rate of poison i

injection requirement of 10 CFR 50.62(c)(4) than does the 251 inch diameter vessel on which the rule was based., The Big Rock Point reactor vessel has a diameter of only 106 inches and sodium pentaborate solution is on the order of 19 weight percent.

Injection rate with the reactor at power is 132 gpm.

It should be noted that because of unique operating features associated with plant design that the injection rates established by the rule are probably not appropriate for Big Rock Point.

It is useful to get a sufficient amount of l

poison to the core to shut the reactor down quickly during a Big Rock ATWS.

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The effectiveness of the poison system in providing a relatively quick shutdown of the reactor and a detailed description of the poison system itself was provided as a part of our February 26, 1981 Automatic Recirculating Pump Trip risk evaluation. The system operates on natural circulation and requires no charging pumps. A high pressure nitrogen accumulator is available to l

provide initial force to establish poison flow to the reactor. With the reactor at power, sufficient sodium pentaborate can be injected to the primary coolant to result in reactor shutdown on the order of one minute following actuation. Five minutes of natural circulation injection provides a sufficient amount of poison to permit suberiticality even at cold conditions.

l The Big Rock Point poison system has been designed to requirements more restrictive than this portion of the rule and therefore no further action is required.

Automatic Recirculating (RPT) Pump Trip (RPT) - 10CFR50.62(c)(5) f Automaticrecirculatingpumptrip(RPT).hasbeendemonstratedtobeofminimal safety significance at Big Rock Point because of several unique plant design features: oversized safety relief valso capability on the order of 200% rated power precludes the potential for primary system overpressurization and a large containment volume relative to primary system stored and decay energy minimizes the potentici for containment overpressurization.

Unlike other BWRs, the principle benefit of an automatic recirculating pump trip is limited to an extension of time for operator initiation of the liquid poison system. Extensive evaluation of this issue by the NRC and Consumers Power Company has been performed in recent years:

October, 1975 NEDE-21065 Anticipated Transients Without Scram Study for the Big Rock Point Power Plant.

February 21, 1980 Staff Confirmatory Order to install automatic RPT at Big Rock Point.

December 3, 1980 CPC request for deferral of automatic RPT based on preliminary insights from risk assessment.

OC1085-0302-NLO4

g Director, Nuclear Reactor Regulation 3

Big Rock Point Plant Implementation Schedule - ATWS October 14, 1985 January 15, 1981

- Amendment 38 to Big Rock Point license deferring RPT until staff review of PRA was complete.

February 26, 1981

- Consumers Power Company's risk assessment of automatic RPT and alternatives.

September 10, 1981

- Response to staff questions on efficacy of

& December 17, 1981 automatic RPT.

May, 1984

- NUREG-0820 Integrated Plant Safety Assessment Section 5.3.18 concluding that the benefits of automatic RPT are limited at Big Rock.

May 17, 1984

- NRC Safety Evaluation of the Big Rock Point Probabilistic Risk Assessment and requested deferrals concluding that the benefits of automatic RPT are limited at Big Rock.

May 30, 1984

- Response to NRC request concluding automatic RPT is not cost-beneficial even if non-safety grade equipment is procured.

Based on the limited benefits of an automatic RPT as demonstrated in the referenced NRC and Consumers Power Company evaluations, an exemption from the requirements of 10 CFR 50.62(c)(5) is requested.

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Ral h R Frisch Senior Licensing Analyst CC Administrator, Region III, USNRC NRC Resident Inspectors - Big Rock Point Plar.t OC1085-0302-NLO4