ML19257A509
| ML19257A509 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/31/1979 |
| From: | Andognini G BOSTON EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 79-281, NUDOCS 8001040531 | |
| Download: ML19257A509 (7) | |
Text
.
4 BOGTO N EDISON COMPANY aENEmA6 orriCEs soo sOvtsTON sT=EET GOSTON. M AssACHUSETTs 02199 G. CANL ANDOGNING BU PERENTENDENT NUCLEAN OPENATIONE OEPARTMENT December 31, 1979 BECo. Ltr. #79-281 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555 License No. DPR-35 Docket No. 50-293 Response to Lessons Learned Short Term Requirements
References:
(A) NRC Letter dated October 30, 1979, Discussion of Lessons Learned Short Term Requirements (B) BEco Letter dated November 21, 1979, Response to Discussion of Lessons Learned Short Term Requirements (C) BECo Letter dated October 19, 1979, Follow-up to Reviews Regarding the Three Mile Island Unit 2 Accident
Dear Sir:
Reference (A) requested that all operating nuclear power plants provide a detailed description and justification for each of their responses which were not in complete agreeement with your staff's requirements as clarified by that reference.
Boston Edison Company performed a preliminary review of those clarifications and responded in Reference (B).
Additionally, Reference (A) required Boston Edison Company to submit to the NRC by January 1, 1980, a detailed description and schedule for the following five NUREG-0578 rasitions:
(1) Position 2.1.1
- Emergency Power Availability to Provide g
Long Tem Source of Air for Air-Operated Relief Valves.
b (2) Posir.~on 2.1.2
- Relief and Safety Valve Testing
/!l (3) Position 2.1.5a - Dedicated H2 Control Penetrations (4) Position 2.1.8a - Post-Accident Sampling 1635 019 (5) Position 2.2.2b - On-Site Technical Support Center 8001040 f
f
80 TON EDISON COMPANY Mr. Harold R. Denton December 31, 1979 Page 2 Our responses to the above positions are included as an attachment to this letter. We believe that the positions delineated in this letter and those of Reference (B) satisfy the documentation of our commitments for Category A items as required by Reference (A).
For those Category A items which were deferred by Reference (C), our methods of implementation will be provided before the beginning of our next operating cycle.
Should you desire. additional information or clarification please feel free to contact us.
Very truly yours,
(
pJ J
Attachment 1685 020
Attachment to BECo. Ltr. #79-281 Position 2.1.1 Emergency Power to Provide a Long Term Source of Air for Air Operated Relief Valves Boston Edison has reviewed NRC's request for verification of emergency power availability to provide a long tera source of air for air op.erated relief valves. The review indicated the following:
- 1) The relief valves will lif t (without air availability) when the set point pressure is reached
- 2) Air is required for manual operation only
- 3) Relief val,es have accumulators which have sufficient capacity for a minimum oE twenty (20) pilot actuations.
- 4) The air supply to the relief valve is backed-up by a nitrogen supply for manual operation
- 5) Three (3) of the four (4) existing air compressors are connected to safety buses (diesel generators) and are automatically reenergized after initial load shedding upon loss of offsite power.
- 6) Receiver low air pressure isolates the non-essential air header Boston Edison believes the existing plant design is adequate to meet the NRC's Concerns.
6. -. _ _ _ _ _
Attachment to BECo. Ltr. #79-281 Position 2.1.2 Performance Testing of PWR and BWR Relief and Safety Valves Boston Edison Company endorses the position of the BWR Owners Group on Safety and Relief Valve Testing. General Electric Company is presently at work pre-paring a total program plan. The Owners Group has also held in-depth discussions with prospective contractors for the low pressure tests. A meeting is scheduled for early January to make the necessary decisions on this issue.
A schedule has l'een discussed by J. R. Bynum of the BWR Owners Group and D. M.
Verrelli of your staff. A presentation including the scope of testing, analysis to be performed, and a schedule for completion of the above will be forwarded by January 31, 1980.
We understand that the schedule discussed above is satisfactory to the NRC staff.
4 I
1685 022 _ _. - - _ _ _ _ _ _. _ _ _
Attachment to BECo. Ltr. #79-281 Position 2.1.5.a Dedicated Penetrations for External Recombiners or Post-Accident Purge System Spare connections on the torus vessel and new connections on the torus and drywell purge lines have been designated as dedicated connections for ex-ternal recombiners. The new connections on the torus and drywell purge lines are inboard of the existing purge isolation valves.
The installation of the dedicated penetrations will be completed before the beginning of the next operating cycle. The penetrations are redundant and will be installed in accordance with ASME III Class 2.
4
~-
~
1685 023 -. -
Attachment to BECo. Ltr. #79-281 Position 2.1.8.a Improved Post Accident Sampling Capability X conceptual design for equipment additions needed at Pilgrim 1 Nuclear Power Station to meet the Post Accident Sampling Requirements of NUREG-0578 was re-ceived in late December from General Electric Company. This design is et present being evaluated by Boston Edison Company and the BWR Owners Group.
The Genersl Electric Design recommends a three step sampling process. The samples are to be obtained at the Post Accident Sample Station adjacent to the Secondary Containment. GE believes the Sample Room needs controlled HVAC and should be properly shielded from the high dose rates expected following a LOCA. The samples are to be transported to a wet lab and prepared for counting. The final results are obtained in a counting area located and shielded from radiation sources which would ensure accurate counting.
Af ter Boston Edison, in conjunction with the BWR Owners Group, completes their design evaluation, the final design will be submitted to NRC for review.
1685 024 _
Attachment to BECo. Ltr. #79-281 J.
Position 2.2.7.b On-Site Technical Support Center (TSC)
A permanent On-site Technical Support Center separate from and in close proximity to the control room that has the capability to display and transmit plant status to those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident will The center shall be habitable for postulated accident conditions.
be installed.
Emergency plans shall be revised as necessary to incorporate the role and loca-tion of the technical support center.
The following general description of the On-site Technical Support Center (TSC) is provided.
1.
Space Work space will be provided for 17 people with capability to accommodate 8 additional people for peak manning periods.
2.
Structural Will meet uniform building code zone criteria for earthquake.
It a.
is not a seismic Cat. I structure.
b.
Local fire code requirements will be met.
The structure will provide radiation protection for continuous c.
habitability.
3.
Habitability HVAC will be sized for equipment and personnel.
a.
Air intake will be able to be shif ted from an open louver to a high b.
efficiency particulate (HEPA) and charcoal absorbent filtered inlet.
Air intake will be monitored for radiat ion similar to control room c.
monitoring requirements. Toxic gases tiill not be monitored.
d.
Po table water and toilet facilities will be directly connected to the normal plant systems, Standard office plus emergency lighting will be provided.
e.
Emergency power will be supplied in the event of a failure of the f.
plant normal supply, i685 025..