ML20071J169

Provides Info Identifying Electrical Equipment Important to Safety within Scope of 10CFR50.49(g) Already Qualified. Schedules for Qualification of post-accident Instrumentation Encl

ML20071J169
Person / Time
Site:	Three Mile Island
Issue date:	05/20/1983
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.E.1.2, TASK-2.F.1, TASK-2.F.2, TASK-TM 5211-83-157, NUDOCS 8305260094
Download: ML20071J169 (3)

Text

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GPU Nuclear Corporation U Nuclear =fme S 8: 48o Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:

May 20, 1983 5211-83-157 Office of Nuclear Reactor Regulation Attn: Harold A. Denton, Director U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Environmental Qualification of Electrical Equipment (10 CFR 50.49)

In accordance with 10 CFR 50.49(g) and NRC letter dated March 30, 1983, GPUN is supplying the following information to identify the electrical equipment important to safety within the scope of Section 50.49(g) that is already qualified, and to submit schedules for environmental qualification or replacement of the remaining equipment that is important to safety as defined in 10 CFR 50.49(b).

(1) Safety Related Electrical Equipment 1

GPUN letter dated August 28, 1981 (L1L 238) in response to IEB 79-01B lists I all the safety related electrical equipment which is required to be and which is already qualified. The additional information we submitted in our letters dated May 3, 1982 (5211-82-101) and May 16, 1983 (5211-83-076) (NUREG 0737 items), support our conclusions that the components listed are qualified in accordance with DOR Cuidelines dated November, 1979.

Your letter dated December 10, 1982, contained TMI-l TER which indicated some apparent equipment qualification discrepancies. In our letter dated March 21, 1983 (5211-83-054) we requested a meeting to resolve these apparent discrepancies. We would like to reiterate that request at this time. In the event any valid discrepancies result from this meeting, we will resolve .

o$$ them on a schedule consistent with the requirements of 10 CFR 50.49(g). l So og (2) Non Safety Related Electrical Equipment on

,0 GPUN letter dated July 21, 1982 (5211-83-170) in response to IE Notice 79-22, od OS and PID dated December 14, 1981 Section P concerning interaction of safety and non-safety systems indicate that failure of non-safety systems during

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@ the design basis accidents will not result in an adverse effect on safety g equipment.

no GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

a b. r b

Mr. Harold A. Denton 5211-83-157 (3) Certain Post Accident Monitoring Equipment (R.G.1.97 Rev. 2)

Enclosed is a list of post accident monitoring instrumentation that is already environmentally qualified. CPUN letter dated April- 15, 1982 concerning emergency response facilities discusses CPUN efforts through the B&W Owners to respond -to Reg. Guide 1.97 guidelines. This effort is currently scheduled for completion mid Cycle 5. When this effort is complete, we will qualify or replace the remaining post accident monitor-ing equipment on a schedule consistent with requirements of 10 CFR 50.49(g).

Since rely ,'

v H. D. li kill Director, TMI-l llDil:LWH:vj f Enclosure cc: J. Allen J. Stolz J. Van Vliet b

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L _ _ _ .

O TMI-l Post Accident Instrumentation (Environmentally Qualified)

Regulatory Guide 1.97, Rev. 2 IT_EM CAT. TYPE ENVIRONMENTAL QUALIFICATION RCS Ilot Leg H2O Temp 1 B NUREG 0737 Item II.F.1 RCS Cold Leg H2 O Temp 1 B NUREG 0737 Item II.F.1 RCS Pressure 1 C NUREG 0737 Item II.F.2 sheets 12 and 13*

Core Exit Temp (Incore T/C) 1 B NUREG 0737 II.F.2 sheet 1 thru 11*

Saturation Monitor 1 B NUREG 0737 II.F.2 sheets 12 and 13*

R.B. Sump level 2 B NUREG 0737 Item II.F. sheets 15 thru 18*

R.B. Pressure 1 B NUREG 0737 II.F.1 RB H2 Concentration

• 1 C NUREG 0737 Item II.F.1 sheets 1 thru 12*

DU Exchanger Outlet Temp 2 D NUREG 0737 Item II.F.2 '

DH Removal Flow /LPI Flow 2 D NUREG 0737 Item II.F.2 .

PORV/ Safety Valve Position 2 0 NUREG 0737 Item II.D.3 sheets 1 thru 9*

Pressurizer Level 1 D NUREG 0737 Item II.D.3 S/G Level 1 D NUREG 0737 Item II.F.2 S/G Pressure 2 D NUREG 0737 Item II.F.1 EFW Flow 1 D NUREG 0737 Item II.E.1.2 sheets 1 thur 6*

MUT Level 2 D NUREG 0737 Item II.F.1 R.B. High Range Radiation 1 E NUREG 0737 Item II.F.1 sheets 13 and 14*

• See GPUN Letter dated May 20, 1983, (83-128 )

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