ML20031D336
| ML20031D336 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/02/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TAC-43600, TAC-43601, NUDOCS 8110130261 | |
| Download: ML20031D336 (4) | |
Text
i Wisconsin Electnc eomcowa 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 October 2,1981 9
f* ' P s b Mr. Ilarold R. Denton, Director U) D
/
Office of Nuclear Reactor Regulation I
U. S. NUCLEAR REGULATORY COMMISSION s-007 9 1981. -11, Washington, D.C.
20555
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Dear Mr. Denton:
DOCKET NOS. 50-266 AND 50-301
/tm[
FIRE PROTECTION MODIFICATIONS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 This letter is to provide the current status of fire protection items for the Point Beach Nuclear Plant.
Our March 18, 1981 letter pursuant to 10 CFR Part 50.12(a) re-quested extension of certain of the schedule dates in Paragraph (c) of the fire protection regulations in 10 CPR Part 50.48. In particular we requested:
1.
That the date in Puagraph (c)(5) for submitting plans and schedules for meeting the provisions of Paragraph (c)(2), (c)(3), and (c)(4) with respect to the requirements of Section III.G of Appendix R to Part 50 be extended from March 19, 1981 to September 30, 1981, and with respect to the requirements of Section III.O of Appendix R to Part 50 be extended to June 30, 1981.
2.
That the date in Paragraph (c)(5) for submitting design descriptions of modifications needed to satisfy Section III.G.3 of Appendix R be extended from March 19, 1981 to December 31, 1981.
3.
That the implementation date in Paragraph (c)(2) for installation of modiGcations that do not require prior NRC approval or plant shutdown be extended from nine months after February 17, 1981 to nine months after September 30, 1981 for modifications required by Section III.G, and to nine months after June 30, 1981 for modifica-tions required by Section III.O.
4.
That the implementation date in Paragraph (c)(3) for the installation of modifications that do not require prior NRC approval but require plant snutdown be extended from before startup after the earliest of the specified events commencing 180 days or more after February 17, 1981 to before startup after the earliest of the specified events commencing 180 days or more after September 30, 1981 for modifications required by Section III.G, and to before startup after the earliest of the specified events commencing 180 days or more after June 30, 1981 for modifications required by Section III.O.
8110130261 011002 p) h PDR ADOCK 05000266 F PDR
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Mr. Harold R. Denton October 2,1981 Our letter also provided the basis for the listed schedule extension requests.
Although the requested extensinn dates appeared to be reasonable at the time of our request, our subsequent efforts to satisfy these dates have proven them to be optimistic and u.1 achievable.
Our basis addressed the problem of coordinating the design and implementation of fire protection features with the many other tasks required by the Commission.
The availa-bility of cognizant personnel to perform fire protection tasks in addition to the other necessary safety-related tasks was also e recognized problem. We did not anticipate the significant impact of the large work force necessary to implement the many required modifications in an operating nuclear power plant.
Engineering and implementation are proceeding within the limits of our personnel availability and at a work pace which can be accommodated safely at the plant. The following itemized information is provided:
Reassessment of Plant Design Features for Meeting the Requirements of Sections III.G, III.J, and III.O of Appendix R.
Our March 18 letter described the reassessment in accordance with Section III.G as a five step evaluation which we expected to complete by September 30, 1981.
To date, all necessary shutdown equipment and cables have been identified.
We are currently in the process of evaluating och plant area for the purpose of developing suitable plans to comply with Section III.G.
We believe that this work can be completed by December 31, 1981 and that plans and schedules for implementation can be submitted by January 31, 1982.
All modificatica work necessary to meet the requirements of Section III.G is not being delayed until completion of the reassessment.
A specification for automatic suppression systems in the cable spreading, switchgear, and auxiliary feedwater pump rooms will ba issued shortly.
Contractor selection is expected by October 31, 1981 and implementation will proceed when system camponents have been procured.
We have developed an equipment barrier design and fabrication details are presently being prepared. We will proceed to implement these barriers as the reassessment evaluation indicates tneir necessity. We will also proceed with implementation of additional fire suppression systems in the auxiliary building if our plant area evaluation indicates their necessity.
Our March 18 letter stated that a plant inspection was required to determine the plans necessary to comply with section III.O.
The inspection was performed as scheduled.
However, the development of plans and schedules could not be completed by June 30, 1981.
A design has been developed for reactor coolant pump,il mllection including the high pressure lift pump and piping.
The design is presently undergoing final plant staff review.
We presently an to have one pump collection system fabricated following plant approval.
The assembly will require plant fit-un and perhaps modification before all reactor coolant pump oil collection syste s can be fabricated.
Because of the heavy work load during the approaching Unit 1 refueling outage including contain-ment fire detector installation, we are not confident that the Unit I rt. actor coolant pump oil collection systems can be installed during this outage. We
"Mr. Harold R. Denton October 2,1981 do believe that sufficient work can be accomplished to facilitate implementation of this modification within the period of our original request for a time extension.
We submitted plans and schedules for implementing modifications requireu by 10 CFR Part 50.48 (c) which were not specifically requi-ed to satisfy Sections III.G and III.O in a separate March 18, 1981 letter.
The following significant status changes are noted for modifications as identified in the Fire Protection Evaluatior. Report:
1.
Item 3.1.5 - Water Damage Protection This item covered the requirement for floor drains in the cable spreading room.
A closed head sprinkler system was initially considered to provide automatic fire suppression.
Modifications necessary to accommodate water protection would include the floor drains, MCC spray shields, and transformer dikes for PCB contain-ment.
The cable spreading room automatic fire suppression will be a gaseous suppression system.
Floor drains, spray shields, and transformer dikes will not be required.
Floor drains would in fact be detrimental as they would have to be provided with locked closed isolation valves to asoure containment of an adeauate concentratica of suppressant, as well as for PCB containment.
Manual water suppression capability is provided with the water source located outside of the cable spreading room.
Wate suppressant can only r
be introduced through an open entrance door which thereby also provides drainage capability.
Overall fire protection of the cable spreading room is more suitably provided without floor drains which, therefore, will not be installed.
2.
Item 3.1.9 - Fire Barriers All fire barrier penetration seal work except for the west all of the auxiliary feedwater pump room and approximately four floor penetrations is complete.
Approximately six weeks of work remains to be done. The auxiliary feedwater pump room seal work is inter-faced with masonry wall requirements and pest-TMI shielding require-ments.
It has not been possible to accomplish the necessary work prior to the approaching Unit i refueling.
The multitude of tasks which must be accomplished during a refueling outage, supervisory personnel availability, and the physical capacity limitations of the plant dictate that unnecessary contract personnel be excluded from the plant during the refueling outage.
Therefore, the remaining seal installation work has been postponed until the outage completion.
Seal inst !!ation work is expected to be completed by March 1,1982.
3.
Item 3.1.24 - Diesel Generator Air Intake This modification has been completed.
4.
Item 3.1.31 - Emergency Diesel Generators - Remote Panel This modification is being implemented by plant personnel because of the safety significance of the diesel generators. The installation
Mr. Harold R. Denton October 2,1981 s
of necessary equipment is essentially complete. However, electrical checkout and operating procedures have not been fully developed.
The plant personnel responsible for developing the necessary procedures will be fully occupied with Unit I refueling outage activities between October 9 and December 5,1981. Therefore, this modification cannot be completed by November 17, 1981. We expect to have this modification completed by January 31, 1982.
Your February 13, 1981 letter stated that the installation of fire detectors in Unit 1 containment was required during the fall 1981 refueling outage, in Unit 2 containment during the spring 1982 refueling outage, and in all plant areas which did not require an outage by October 21, 1981. Con-tractor availability and material delivery problems delayed initiation of this installation.
At the present time, fire detector installation is one of the manv modifications being implemented expeditiously at Point Beach Nuclear Plant.
Detectors will be installed in Unit 1 containment during the refueling outage which begins October 9,1981. Detectors will be installed in Unit 2 containment dwing the spring 1982 refueling outage.
The balance of plant fire detector installation cannot be completed by October 21, 1981 but will be completed prior to the Unit 2 containment installation. to your May 4,1981 letter lists the following unresolved fire protection issues for Point Beach Nuclear Plant:
1.
Item 3.1.14 - Cable Separation 2.
Item 3.1.17 - Hydrogen Hazard Fire Protection 3.
Item 3.2.1 - Safe Shutdown Capability 4.
Item 3.2.2 - Circulating Water Pumphouse Fire Protection 5.
Item 3.2.6 - Reactor Coolant Pump Lube Oil Collection Plans and schedules for Issues 1, 2, and 3 will be covered by the plans and schedules which we will develop at the completion of our plant reassessment to meet the requirements of Section III.G of Appendix R.
Our June 23,1981 letter committed to the installation of a fire barrier wall to provide separation of the service water pumps in accordance with Section _III.G to resolve Issue 4.
The fabrication details for this barrier are in the process of preparation.
We expect implementation of this modification to be completed l
by March 1,1982.
Our plans' and schedules for Issue 5 are stated in our status description of plans necessary to comply with Section III.O.
Please advise us if your have any questions or require any additional information at this time.
Very truly yours, C. W. Fay, Director l
Nuclear Power Department Copy to:
NRC Resident Inspector
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