ML19220B707
| ML19220B707 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/03/1977 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19220B713 | List: |
| References | |
| NUDOCS 7904270242 | |
| Download: ML19220B707 (3) | |
Text
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Docket No. 50-320 FE.MORANDUM FOR:
Domenic B. Vassallo, Assistant Director for Light Water Reactors, DPM FROM:
Robert L. Tedesco, Assistant Director for Plant Systems, DSS
SUBJECT:
METROPOLITAN EDISON COMPANY, JERSEY CENTRAL POWER AND LIGHT CCMPANY AND PENNSYLVANIA ELECTRIC COMPANY, THREE MILE ISLAND UNIT NUMBER 2; INSTRUNENTATION, CONTROL, AND ELECTRIC POWER SYSTDtS, SUPPLDIENTAL SAFETY EVALUATION REPORT Plant Name:
Three Mile Island Uni Number 2 Docket Number:
50-320 G :ensing Stage:
Operating License Milestone Number:
27-22 Responsible Branch LWR 4 and Project Manager:
H. Silver Requested Completion Date:
December 15, 1976 Review Status:
Complete The enclosed Supplemental So -.y Evaluation Report (SSER) was prepared by DSS:PS, Instrumentation and Control Systems Branch.
This SSER provides updated information for the appropriate sections of the published Safety Evaluation Report dated September 1976, and reflects our review of the infor ation (and discussions with the applicant) through and including Amendment Number 50 to the Final Safety Analysis Report.
This supple =ent addresses three categories of items. These being:
(1) items which have been resolved subsequent to publishing of the above Safety Evaluation Report, (2) items whict continue to be under staff review and (3) items identified in the ACRS letter for Three Mile Island Uni Number 2, dated October 22, 1976.
The categories, along with items in each category and the section where they are.ddressed in this supplemental report are stated below.
Contact:
F. Ashe X 7276 7904270242-wcHo 81-293
s Donenic B. Vassallo 2
A.
Items Resolved Subseouent to the Safety Evaluation Retort Dated Sectemoer 1976, for Three Mile Island Unit Number 2 1.
Concerns associated with selected safety related display instru=entation (Section 7.5);
2.
Concerns relating to changeover from the inj ection mode to i
the recirculation mode following a loss-of-coolant accident (Section 7.6.1);
3.
Feismic qualification (Section 7.3.1);
4.
Concern relating to the containment electrical penetrations (Section 7.9);
5.
Protective trip devices and associated circuitry for the diesel generators (Section 8.3.1); and 6.
Provisions included in the design for periodically testing the undervoltage relays at the 4.16 kilovolt engineered safety feature buses (Section 8.3.1).
3.
Items Under Staff Review 1.
Sit. visit and general updating information (Section 7.1 and 8.1);
2.
Main feedwater and steam line isolation (Section 7.3.3);
3.
Electrical design for the Emergency Feedwater System (Section 7.4.1);
4 Environmental qualification of Class 1E electrical equip-ment within the balance-of-plant secpe of supply (Section 7.S.2);
5.
Concerns relating to the electrical power system resulting from the Millstone. nit Number 2 occurrence (Section 8.2); and 6.
Additional documentation concerning the safety features actuation system output relays (Section 8.3.1).
C.
Items Identified in the ACRS Letter for Three Mile Island Unit Number 2, Dated October 22, 1976 1.
Long-term post-accident monitoring instrumentation (Section 18.7.1);81-294
Mmenic B. Vassallo 3
2.
Instrument line failures (Section 18.7.2); and 3.
Battery-supplied direct curren* power system (Section 18.8.1).
hihbw Robert L. Tedesco, Assistant Director for Plant Systems Division of Systems Safety cc:
S. Hanauer R. Heineman R. Boyd W. Mcdonald H. Silver T. Ippolito F. Rosa M. Srinivasan C. Miller J. Watt J. Glynn F. Ashe e
81 29b