NRC Generic Letter 80-52, Five Additional TMI-2 Related Requirements - Erata Sheets to 5/7/80 Letter

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GL80052

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

TO: ALL OPERATING REACTOR LICENSEES

By letter dated May 7, 1980, we transmitted five additional TMI-2 related requirements to operating reactors. Attached is a set of errata sheets which correct errors in our designation of applicability of certain items. The item involved are II.K.3.25, II.K.3.29 and II.K.3.44. A corrected table of the Implementation Schedule and Summary is also attached.

Sincerely,

Darrell G. Eisenhut, Director Division of Licensing

Enclosures:

Errata Sheets

cc: Service Lists

.

EFFECT OF LOSS OF AC POWER ON PUMP SEALS (II.K.3.25)

POSITION

The licensees should determine by analysis or experiment, on a plant-

specific basis, the consequences of a loss of cooling water to the reactor recirculation pump seal coolers. The pump seals should be designed to withstand a complete loss of alternating current power for at least two hours. Adequacy of the seal design should be demonstrated.

CLARIFICATION

This item is applicable to BWRs.

DISCUSSION

NUREG-0626, Section A-2.14

SCHEDULE

January 1, 1982

ACTION: (Class I)

Licensee to provide results of evaluation to staff by scheduled date.

.

STUDY TO DEMONSTRATE PERFORMANCE OF ISOLATION CONDENSERS

WITH NON-CONDENSIBLES (II.K.3.29)

POSITION

If natural circulation plays an important role in depressurizing the system (e.g., in the use of isolation condensers), then the various modes of two-

phase flow natural circulation, including non-condensibles, which may play a significant role in plant response following a small-break LOCA should be demonstrated.

CLARIFICATION

This item is applicable to all BWRs.

DISCUSSION

NUREG-0626, Section F-4.5

SCHEDULE

April 1, 1981

ACTION: (Class I)

(1) Licensee to provide, results of evaluation to staff by scheduled date.

.

EVALUATION OF ANTICIPATED TRANSIENTS WITH SINGLE FAILURE

TO VERIFY NO FUEL FAILURE (II.K.3.44)

POSITION

For anticipated transients combined with the worst single failure and assuming proper operator actions, licensees should demonstrate that the core remains covered or provide analysis to show that no significant fuel damage results from core uncovery. Transients which result in a stuck-open relief valve should be included in this category.

CLARIFICATION

This item is applicable to BWRs.

DISCUSSION

NUREG-0626, Section F-4.3

SCHEDULE

1/1/81

ACTION: (Class 1)

(1) Licensee to provide results of evaluation to staff by scheduled date.