ML20216J563

Forwards Insp Rept 50-289/87-09 on 870306-0424 & Notice of Violation

ML20216J563
Person / Time
Site:	Three Mile Island
Issue date:	06/23/1987
From:	Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Hukill H GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20216J568	List: ML20216J563 ML20216J571 ML20216J581
References
NUDOCS 8707060185
Download: ML20216J563 (4)

See also: IR 05000289/1987009

Text

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~JUN 281987

Docket No. 50-289

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GPU Nuclear Corporation

ATTN: Mr. H. D. Hukill

Vice President and Director, TMI-I

P. O. Box'480  !

Middletown, Pennsylvania 17057

]

Gentlemen:

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Subject: Inspection Report No. 50-289/87-09

During- the period from March 6, to April 24, 1987, members of NRC Region. I

staff conducted routine safety. inspections at your facility; and, in particu-

lar, they closely followed on a 24-hour basis your transition' from cold shut-

down to power operations. We documented the results of that inspection in' the-

enclosed report. At the conclusion of the inspection period, Mr. R. Conte of

my staff summarized the . inspection findings with you and other members 'of your

staff.

We believe your efforts to make personnel and equipment ready for operation to

be noteworthy. A number of initiatives on-your part contributed to that read-

iness. However, we see some significant lessons learned in the technical sup-

port area in view of the relatively high number of design or .. installation

deficiencies identified by you and/or our inspectors. This was particularly.

noted for the safety grade modifications dealing with ' condensate storage ' tank

and steam generator level indication, alarm, and control- functions. Our

inspectors will review your corrective actions in a future inspection. Over-

all, the transition from. cold shutdown to power operation went' . relatively

smoothly.

Also, during the inspection, you did not report, under 10 CFR 50.72 or 10 CFR

50.73, actuations of the safety grade emergency feedwater system (EFW),

including the Heat Sink Protection System (HSPS), because the = system is not

listed as' an engineered safety feature (ESF) in.your Final Safety Analysis

Report (FSAR) or Technical Specifications (TS). Based on' June _5 and 8, 1987,

discussions between you and Mr. A. Blough of NRC Region I, we now understand

.

that you agree that EFW/HSPS actuations are typical of the type of events

intended to be reported under 10 CFR 50.72 and 10 CFR 50.73. Accordingly,.you-

have agreed to: (1) consider future actuations of EFW/HSPS as "ESF actuations"

for- reporting purposes --

-implementation of this commitment will .be

proceduralized through revisions to ~ appropriate station procedures; . and (2)

conduct a review to determine if actuations of any other systems not' listed as.

ESFs in your FSAR'should be reported in accordance with the. intent;of 10 CFR .

50.72 and -10 CFR 50.73 -- you will advise. the NRC resident inspectors of the ,

results of~this review. If your understanding differs ,from the above, please 1

contact this office immediately. NRC Region I does not expect! Licensee Event

Reports (i.e. ,10CFR50.73 reports) for past EFW/HSPS actuations.

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GPU Nuclear Corporation 2

This inspection also identified two apparent violations of regulatory require-

ments. One was the failure to account for thermal expansion in the design of

the pressurizer platform; this created the potential for interference with the

pressurizer spray line. The other was the failure to adequately survey prior

to recent intakes of radioactive material during an event at the letdown pre-

filter room in the early part of March 1987. With respect to the latter appar-

ent violation, we noted your positive short-term corrective actions to identify

fundamental design deficiencies in the letdown prefilter room. In responding,

you should follow the instructions in Appendix A. Your response to this viola-

tion should also include a discussion of your long-range plans to eliminate

radiological concerns associated with the overall makeup filter transfer and

disposal operation as discussed in paragraph 7.5 of the inspection report.

Also, this letter acknowledges receipt of your letters, dated May 2, 1986,

September 17, 1986, and March 13, 1987, in response to two violations of NRC

requirements in the fire protection area. Our inspector also verified your

corrective actions and measures to prevent recurrence as detailed in the

attached inspection report.

Thank you for your cooperation in these matters.

Sincerely,

(pigireal Signed Itys'

Samuel J. Collins, Deputy Director

Division of Reactor Projects

Enclosures:

1. Appendix A, Notice of Violation

2. NRC Region I Inspection Report No. 50-289/87-09

cc w/encis:

G. Broughton, Operations and Maintenance Director, TMI-1

C. W. Smyth, TMI-1 Licensing Manager

R. J. McGoey, Manager, PWR Licensing

E. L. Blake, Jr.

TMI-1 OTSG Hearing Service List

Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

Commonwealth of Pennsylvania

0FFICIAL RECORD COPY IR TMI-1 87-09 - 0002.0.0

06/19/87

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GPU Nuclear Corporation 3

'JllN 9 91997  !

bec w/encis:

Region 1 Docket Room (with concurrences)

J. Goldberg, OELD:HQ

Management Assistant, DRMA (w/o encis)

Operations Branch, DRS Files

Engineering Branch, DRS Files .

EP&RP Branch, DRSS Files l

S. Collins, RI l

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R. Blough, RI

W. Travers, NRR

G. Edison, PM, NRR <

F. Hebdon, NRR

K. Abraham, RI

R. Conte, SRI, TMI-1

W. Baunack, RI

L. Briggs, RI

D. Coe, RI

D. Johnson, RI

A. Krasopoulos, RI

K. Murphy, RI

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B. Norris, RI

S. Peleschak, RI

S. Pullani, RI

P. Wen, RI

F. Young, RI, TMI-1

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0FFICIAL RECORD COPY IR TMI-1 87-09 - 0003.0.0

06/19/87

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GPU Nuclear Corporation 4

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