ML20127H583
| ML20127H583 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/07/1978 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9211180550 | |
| Download: ML20127H583 (4) | |
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NSP NORTHERN 5TATES POWER COMPANY uswNracou s. MINNE SCTA 95409 July 7, 1978 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 HONTICELID NUCLEAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Status of Fire Protection Actions Ref (a):
Letter dated December 10,19 76 f rom L 0 Mayer, NSP, to Victor Stello, USNRC, " Comparison of Existing Fire Protection Provisions to the Guidelines Contained in Standard Review Plan 9 5.1" Ref (b):
Imiter dated July 5,19 77 from L 0 Mayer, NSP, to Victor Stello, USNRC, " Completion of Fire Protection Review" References (a) and (b) identified outstanding actions that were required to be completed to conform to the recommendations of Standard Review Plan 9.$.1.
Reference (b) stated that most of these actions would be completed prior to July 1,1978.
The purpose of this letter is to notify the Commission of certain actions which will not be completed by July 1,1978 or which require further discussion.
Item No.
16 The turbine building barrier installation has not been fully completed. It is estimated that this project will be completed by July 15, 1978.
23 Installation of MG Set Room floor drains has not been completed. This item was not completed due to additional engineering analysis of the wall penetrations and due to high radiation levels in the vicinity of the drain piping locations.
This project will be completed prior to startup
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after the Fall 1978 refueling outage.
In the interim, if a I-fire should occur in this area, the access doors can be opened to provide adequate drainage.
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NORTHERN STATES POWER COMPANY u N N z A pou s. min N e sotA e s 4 oi July 7, 1978 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Comedssion Washington, DC 20555 FDNTICELID NUCLEAR GENERATING PIR;T Docket No. 50-263 License No. DPR-22 Status of Pire Protection Actions Ref (a):
Letter dated December 10, 19 76 f r om L 0 Maye r,
NSP, to Victor Stello, USNRC, " Comparison of Existing Fire Prot ection Provisions to the Guidelines Contained in Standard Review Plan 9 5.1" Ref (b):
Imtter dated July 5,1977 f rom L 0 Mayer, NSP, to Victor Stello, USNhC, " Completion of Pire Protection Review" References (a) and (b) identified outstanding actions that were required to be completed to conform to the recommendations of Standard Review Plan 9.5.1.
Ref erence (b) stated that mos t of these actions would be completed prior to July 1,1978. The purpose of this letter is to notify the Commission of certain actions which will not be completed by July 1,1978 or which require further discussion.
Item No.
16 The turbine building barrier installation has not been fully conpleted.
It is es timated that this project vill be completed by July 15, 1978.
23 Installation of MG Set Room floor drains has not been completed. This item was not completed due to additional engineering analysis of the wall penetrations and due to high radiation levels in the vicinity of the drain piping locations. This project will be completed prior to startup after the Fall 1978 refueling outage.
In the interim, if a fire should occur in this area, the access doors can be opened to provide adequate drainage.
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i NORTL MN CTATES POWER COM, ANY Director of NRR Page 2 July 7, 1978 29 Replacement of the doors addressed in this item has not been completed. These doors are being replaced in conjunc-tion with required security modifications. Other actions associated with this item have been completed.
31 Extension of the turbine lube oil reservoir deluge system has not been completed. The design has been completed and is presently being reviewed by qualified fire protection pe rso nn el. This modification will be completed prior to startup following the Fall 1978 refueling outage.
37 Investigation of emergency relief venting for fire exposure of above ground tanks has been completed. This investiga-tion revealed that the diesel fire pump day tank, the diesel generator day tanks, and the heating boiler day tank require modification to meet the venting criteria.
These modifications will be completed prior to startup following the Fall 1978 refueling outage.
60 Investigation of all plant areas with respect to smoke and heat venting has been completed.
The torus room does not meet the criteria outlined in Standard Review Plan 9 5.1.
Transient scaffolding is stored in this area.
Iloweve r, it is treated with a fire retardant material. The spacial arrangement of the stored scaffolding precludes the involve-ment of all the combustibles present.
It is felt that the smoke and heat produced f rom a fire in this area would not prevent access for fire fighting purposes.
99 Control room audibic and visual alarm end annunciation for the cooling tower fire detection systen has not been completed. This modification was planned in conjunction with other cooling tower modifications which have since been postponed. This modification will be completed prior to startup following the Fall 1978 refueling outage.
Presently, other alarms would be received in the control room in the event the cooling tower fire detection system is activa ted.
121 Installation of the torus hose stations has not been completed. Tie-in of these hose stations will require isolation of the fire protection water supply to the reactor building. This modification will be completed during the Fall 1978 refueling outage.
148 The Control Room ventilation modification has not been completed.
It is expected that this modification will be l
completed prior to July 15, 1976.
NoMTF MN GTATED POWER COM. dNY e
Director of NRR Page 3 July 7, 1978 84 The emergency procedures are presently being revised. The list of special fire fighting equipment will be included when the revisions are issued.
Issuance of the new revis-ion vill be completed by October 1,1978.
Completion of the above listed modifications was delayed due to involveme nt of the plant Engineering Staf f in incorporating AS!IE Boiler and Pressure Vessel Code,Section XI testing requirements into the plant surveillance program.
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have any questions concerning the status of these items, pl.se contact us.
Yours ve ry truly, L 0 Mayer, PE Manage r of Nuclear Support Services IDM/MHC/deh cc:
J G Keppler G Charnoff i
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