ML20065A069

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Responds to 820820 Request to Revise Commitments & Justification for Incomplete NUREG-0737 Items Which Util Will Be Unable to Complete by Estimated Restart Date.Revised Date Is 830331 or Restart,Whichever Is Later
ML20065A069
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/07/1982
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 5211-82-209, NUDOCS 8209130123
Download: ML20065A069 (3)


Text

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gf P.O. Bcx 480 Middletown. Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:

September 7,1982 5211-82-209 Office of Nuclear Reactor Regulations Attn: John F. Stolz Operating Reactors Branch No. 4 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 Revision of Commitments for NUREG 0737 Items II.B.3, II.F.1.4, II.F.1.5, and II.F.1.6 Your letter dated August 20, 1982, requested that we submit revised commitments and justification for presently incomplete NUREC 0737 items which we will be unabic to complete prior to our estimated restart date. This letter is in partial response to your request.

Our revised commitment for the subject NUREG 0737 items is by restart (reactor critical) or no later than March 31, 1983, which ever is later. The current status and schedule for the subject items is discussed in the attached table.

As you will note we have retained some contingency in our commitment in order to account for unanticipated problems which may delay completion. These include items such as post installation equipment failures identified during testing which cannot be corrected by restart.

Sincerely, n

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lukill Director, TMI-l llDil:PRC :CWS : j rg Enclosures cc:

R. C. llaynes Qf R. Jacobs 8209130123 820907 PDR ADOCK 05000289 P

PDR clear is a part of the General Pubhc Utihties System

NUREC 0737 ITEM STATUS ITEM STATUS

  • COMMENTS II.B.3 - Post Accident The RCS sampling modifications are complete Dissolvalgas information is not directly used by the except for the equipment necessary to sample operator and can be inferred from other plant para-for dissolved gases. The dissolved gas meters as was done during the TMI-2 accident. The sampling modification is 75% complete.

extent of core damage and boron concentration are the Remaining major work consists of fabrica-important parameters and the modifications necessary tion of the sample cylinder, support in-to determine them are complete.

sta11ation, and tubing and shielding in-sta11ation. Estimated completion for the Although no procedures currently exist a sample of the remaining work is 12/1/82.

containment atmosphere could be obtained via the exist-ing containment monitoring system (RM-A2 Drawing C-Containment atmospheric sampling is 98% com-302-721).

Based on similar experience at TMI-2 during plete. The major remaining work consists of the accident we believe that radiation levels would be heat trace and minor tubing termination.

acceptable if this method were used.

Procedures Estimated completion for remaining work is necessary to accomplish this are not planned since 12/1/82.

they could be prepared on short notice; post accident, by personnel in the technical support center or at the near site or Parsippany Emergency Operations Facility if nececsary.

II.F.1.4 - High Range This modification is 98% complete. The major A control grade pressure monitor (0-100 psig)

Containment Pressure remaining work consists of tubing and elect-exists and can be used to monitor containment pressure Monitor rical terminations.

for all accidents within the design basis. All design sis accidents result in containment pressures less Estimated completion for the remaining work than 55 psig.

is 10/1/82.

II.F.1.5 - Containment This modification is 98% complete. The major A control grade containment water 1cvel instrument Water Level Monitor remaining work consists of electrical term-has been installed. This monitor can measure contain-inations and vendor repair of a defective ment flood level up to 10 ft. The maximum post reciever that was discovered during testing.

accident containment flood level is 5.66 ft. (5.68 ft.

after 30 days)

Estimated completion for the remaining work is 10/1/82.

  • Does not include post construction testing.

o NUREG 0737 ITEM STATUS CON'T

=

ITDI STATUS

  • COTfENT II.F.1.6 - Containment This modification is 98% complete. The major The capability exists to obtain a containment atmos-Hydrogen Monitor remaining work consists of butt splices, cir-pheric sample as discussed above under item II.B.3.

cuit breaker and switch installation. (Circuit This sample could be used to determine containment breakers have not yet been recieved.).

hydrogen concentration.

Estimated completion for the remaining work is 12/1/82.

  • Does not include post construction testing.

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