ML19343C482

Advises Re Implementation of Fire Protection Mods Not Previously Accepted by Nrc.Evaluation of Emergency Lighting Sys Will Be Completed by 811117.Oil Collection Sys Mods for Reactor Coolant Pump Are Scheduled After 810816

ML19343C482
Person / Time
Site:	Prairie Island
Issue date:	03/19/1981
From:	Mayer L NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
References
TAC-11094, TAC-11095, NUDOCS 8103240354
Download: ML19343C482 (3)

Text

.

a MSP NORTHERN STATE 5 POWER COMPANY mis u sa s ou e. m o u s s eora so oi

_Lly ceM/'\\

March 19,1981 W

pr(

c3 I

/

u V

Director of Nuclear Reactor Regulation IU/ 2 3198] A h]%/.

U S Nuclear Regulatory Commission u.s. mea nmren cc** ' 5*

J/

Washington, DC 20555 Prairie Island Nuclear Genertting Plant

/I..

Docket No. 50-282 License No. DPR-42 Y[-

50-306 DPR-60 Plans and Schedules for Meeting the Provisions of Paragraphs 50.48(c)(2), (c)(3), and (c)(5) of 10 CFR Part 50; Fire Protection Modifications Paragraph 50.48 (c) (5) of 10 CFR Part 50 requires that p ans and schedules 1

for meeting the provisions of paragraphs c(2), c(3), and c(4) be submitted within 30 days of the ef fective date of the new Section 50.48.

We interpret this requirement to include all proposed fire protection modifications not previously accepted by the Staff, as well as modifications needed to meet the requirements of Sections III.G, III.J, and III.0 of the new Appendix R to 10 CFR Part 50.

Modifications not previously accepted by the Staff are those items identified in Enclosure (2) of a letter from Darrell G Eisenhut dated November 24, 1980.

We are currently reassessing all relevant areas of the plant to determine the status of compliance with Section III.G.2 of Appendix R, as described in Generic Letter 81-12, from Darrell G Eisenhut dated February 20, 1981.

This reassessment has not yet been completed. An extension of the time limit specified in paragraph 50.48(c)(5) for submitting plans and schedules related to modifications required by Section III.G has been requested in a Request for Exemption dated March 13, 1981. The purpose of this letter is to provide our plans and schedule for meeting all other requirements of Section 50.48 and Appendix R applicable to Prairie Island.

Fire Protection Safety Evaluation Report Items Not Accepted by NRC Staff Two open items are identified in Enclosure (2) of Mr Eisenhut's November 24, 1980 letter:

3.1.12 Alternate Shutdown Capability 3.2.1 Safe Shutdown Analysis Items 3.1.12 and 3.2.1 are related to fire protection of safe shutdown capability. The regulation requires that Section III.G of Appendix R must be satisfied irrespective of the status of safe chutdown related open items in the Fire Protection Safety Evaluation Be7 vt.

Safe shutdown equipment and circuits, including " associated circuits", must be reassessed for compliance with the new standards in Section III.G.

8103240s54

~

NORTHERN CTATE3 POWER COMPANY Director of NRR March 19,1981 Page Our Exemption Request dated March 13, 1981 contained our proposed schedule for addressing the requirements of Appendix R,Section III.G.

Our reassessment of the safe shutdown capability of the Prairie Island plant for conformance to Section III.G has not progressed to the point where meaningful information related to plans and schedule for compliance can be submitted for NRC Staff review at this time.

Appendix R,Section III.J, Emergency Lighting Section III.J of Appendix R requires emergency li.ghting units with at least an 8-hour battery power supply be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes.

The existing Prairie Island emergency lighting system satisfies this requirement for most areas of the plant.

Emergency lighting throughout the plant (except the control room and special ventilation zone airlocks) is normally fed from the associated unit's 120/208-volt minimum interruptible bus with automatic transfer to one of the station batteries upon failure of the ac supply.

Lighting in the control room is supplied from both 480-volt ac safeguards buses with strategically placed two-hour standby battery powered units.

Two-hour battery powered lighting units are placed in each auxiliary building special ventilation zone airlock.

The existing system will be evaluated and modifications made to provide each area needed for operation of safe shutdown equipment, including access and egress routes, with de lighting. For each light, the de source will either be the station battery and its associated battery charger (which can supply essential lighting indefinitely) or another eight-hour battery source.

The auxiliary building special ventilation zone airlocks are small (four to ten feet in length and four feet wide).

They do not constitute an..ccess or egress route within the meaning of Section III.J.

Evaluation of the existing emergency lighting system and needed modifica-tions which can be completed dur ang plant operation will be completed by November 17, 1981. Modifications which require a plant shutdown will be completed during the first extended outage of the af fected unit following August 16, 1981 in accordance with 10 CFR Part 50, Section 50.48(c)(3).

Appendix R,Section III.0, Oil Collection System for Reactor Coolant Pump Section III.0 of Appendix R requires that reactor coolant pumps be equipped with an oil collection system if the containment is not inerted during normal operation. The oil collection system must be designed, engineered, and installed to remain operable in the event of a loss of coolant accident or design basis earthquake.

e

e NORTHERN CTATED POWER COMPANY e

Director of NRR March 19, 1981 Page Oil splash protection was installed on reactor coolant pumps at Prairie Island in 1978 and 1979. The original design of this modifica-tion is now being reviewed by our architect-er.gineer for compliance with the requirements of Section III.O.

It appears that the existing installation, with minor modifications, will satisfy the new requirements.

Any modifications determined necessary by our architect-engineer will be scheduled for completion during the first extended outage of the affected unit following August 16, 1981 in accordance with 10 CFR Part 50, Section 50.48(c)(3).

.Please contact us if you require further information related to our plan and schedule for completing this work.

L 0 Mayer, PE

(

hanager of Nuclear Support Services f

LOM/DMM/jh ec lJ G Keppler G Charnoff NRC Resident Inspector m

____,1