United States Nuclear Regulatory Commission - Protecting People and the Environment

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



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. 

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