ML20117P824
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DECEMBER 7, 1987 4
Docket Nos. 50-317 and 50-318 DISTRIBUTION Docket m le' PREDECISIONAL INFORMATION PDI-1 Reading S.Varga B.Boger MEMORANDUM FOR:
Lowell E. Tripp, Chief R.Capra Reactor Projects Section No. 3A, PB 3 S.McNeil Division of Peactor Projects, RI J.Wiggins B.Clayton THRU:
Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II, NRR FROM:
Scott Alexander McNeil, Project Manager Project Directorate I-I Division of Reactor Projects. I/II. NRR
SUBJECT:
NRR INPUT FOR THE DECEMBER 21, 1987 VISIT OF COPHISSIONER CARR TO CALVERT CLIFFS NUCLEAR POWER PLANT i
SIGNIFICANT LICENSING ACTIVITIES A.
Outstanding Plant-Specific Issues 1.
24-month operating cycle - Currently, Unit 2 is in the sixth month of the first 24-month operating cycle at Calvert Cliffs. Numerous technical specification amendments have been issued to support this cycle length, however, several are still undergoing review and 1
many required for the cycle have not yet been requested by BG&E.
2.
Feedline Break Event (FLB) - The FLB was characterized as a jesign basis event (DBE) in BG&E's justification that the upgrade of their auxiliary feed actuation systems to safety system status was complete.
BG&E also added the FLB to the FSAR as a DBE. BG&E now contends that the FLB is not a DBE as it was not in the plant's original design basis. Resolution of this issue is a restart item for the Spring '88 Unit I refueling outage.
3.
EPZ Reduction Request - BG&E has requested a reduction in their EPZ radius from 10 to 2 miles. NRC review deferred until completion of the Severe Accident Core Damage study scheduled for July 1988.
4 Three Emergency Diesel Generators (EDGs) for Two Units - BG8E has one EDG dedicated to each unit and one that can swing to either unit. As a result, the probability of a station blackout is greatly increased.
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c PREDECISIONAL INFORMATION B.
Significant Generic Issues All TMI Action Items, GL 83-28 (Salem ATWS) items and other pre-1987 generic licensing activities have been completed with the exception of the following issues which are undergoing NRC review:
1.
Procedures Generation Package Review [THI Action Item I.C.I.2/3.B]
2.
Relief Valve and Safety Valve Testing [TMI Action Item II.D.I]
3.
ReactorCoolantPumpTrip[TMIActionItemII.K.3.5]
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Detailed Control Room Design Review Summary Report I.TNI Action Item i
I.D.I.2]
5.
Safety Parameter Display System Operability [TNI Action Item I.D.2.3]
6.
Inadeouate Core Coolin GL 83-28 Items 2.2.2 (g Instrumentation [TMI Action Item II.F.2.3]
7.
Vendor Interface for Safety Related Components),
4.2.3 and 4.2.4 (Preventative Maintenance for Reactor Trip Breakers),
and 4.5.3 (Reactor Trip System Functional Testing).
8.
10 CFR 50.62, ATWS Rule Review.
Scott Alexander McNeil, Project Manager Project Directorate I-1 Division of Reactor Projects, I/II
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PDI-I PDI-1 SMcNeilM'"
RCapra RN 12/'/ /87 12/1 /87 i
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