ML20212F850

Corrected Page 2 to Transmitting Emergency Procedures Generation Package

ML20212F850
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/30/1986
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML20212F824	List: ML20212F819 ML20212F850
References
NUDOCS 8701120191
Download: ML20212F850 (1)

Text

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4 o u.

Director, Nuclear Reactor Regulation 2 Big Rock Point Plant Integrated Plan Issue BN-032 -

December 30, 1986 the BWR Owners Group Generic Technical Guidelines as a basis. The generic guidelines were modified to accommodate the design differences between the generic plant (Hatch) and Big Rock Point. All of the areas of concern in the generic guidelines were included or dispositioned in the Big Rock Point preliminary Plant-Specific Technical Guidelines (ie, the generic guidelines have a concern with suppression pool temperature and although Big Rock Point has no suppression pool, the temperature of the containment sump is a concern for recycle purposes and was therefore addressed).

The preliminary Plant-Specific Technical Guidelines were then compared to the table developed from the Big Rock Point PRA containing the operator actions

> versus equipment failure as well as existing alarm response and off-normal procedures. The guidelines were then modified to incorporate those actions which needed to be addressed by the Emergency Operating Procedures (EOPs).

The final Big Rock Point Plant-Specific Technical Guidelines contain actions identified in the dominant accident sequences of the Big Rock Point PRA as l well as meeting the intent of the generic guidelines which go beyond a plant's design basis. The above actions are considered to be the equivalent to a line '

by line description and therefore a comparison to the generic guidelines of the Big Rock Point Plant-Specific Technical Guidelines is not necessary.

Inasmuch as many of the conditions addressed in the Plant-Specific Technical Guidelines assume more accident scenarios then those included in the plant design basis, some of the actions proposed to mitigate the consequences of these additional scenarios are not required by or included in the Big Rock Point Technical Specifications. The following is a listing of those actions which are not permitted by the plant licensing basis during normal plant operation but which are considered prudent during emergencies and are specified in the Plant-Specific Technical Guidelines:

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• In the PCS Level Control guideline, opening MO-7073 and MO-7074 to add j

fire water to the condenser hotwell which has the potential of diverting core spray flow. (License Amendment 15 granted interim approval to use this makeup supply pending installation of a modified ring spray system.)

!

• In the Containment Pressure Control guideline, allowing containment pressure to increase above the design pressure of 27 psig.

• In the Containment Level Control guideline, allowing containment water '

level to increase above the design maximum elevation (596').

• In the Containment Level Control guideline, specifying "high pressure recycle" as a means of recycling and cooling water in the containment

! sump when normal use of the post incident system is not available.

This method will involve pumping water from the containment sump into the condensar hotwell via an isolated section of the fire system; P

fl OC1286-0181-NLO4

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