ML20094A082

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Suppls Response to NRC Re Violations Noted in IE Insp Rept 50-289/84-03.Forwards Update to List of Outstanding Items & Technical Data Rept 563, TMI-1,Post- Accident RMA-5 Grab Sampling & MAP-5 Filter Removal..
ML20094A082
Person / Time
Site: Crane Constellation icon.png
Issue date: 07/03/1984
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20094A069 List:
References
5211-84-2157, NUDOCS 8408030107
Download: ML20094A082 (3)


Text

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e GPU Nucles.' Corporation NUCIMr Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386

'4 Writer's Direct Dial Number:

July 3, 1984 5211-84-2357 i

3, Dr, Thomas E. Murley Region I, Regional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Inspection Report 84-03 (Post Accident Sampling and Monitoring)

Our letter of March 8,1984 provided the list of actions GPUN is pursuing in regard to post accident sampling along with commitment dates targeted for completion of each item.

Responses to certain of those items were shown to require additional submittals.

This letter transmits GPUN's response to several outstanding items and indicates those items which have been corupleted since our last submittal of June.6. 1984.

c s

s is an update to our list of outstanding items.

(TDR-563) provides the response to one of these items as indicated in.

Those items for which responses have been provided are not included in this submittal.

Sincerely, H. D. Hbkill Director, TMI-1 HDH/MRK/mle Attachments i

I I

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GPU Nuclear Corporation is a subsidiary of the General Pubile Utilities Corporation 8408030107 840730 PDR ADOCK 05000289 0

PDR y

5211-84-2157 POST ACCIDENT S# FLING #0 MNIT(RING (IR 84-03)

OlfTST#0ING ITEMS (N(ITE 2)

IR GRN Tageted Its Original Actim Cmpletion No.

Inspection Report Itan No.

Rmaining GPlN Action Date 84-0 M 1 HCS S4 FLING 1.a Provide the capability to obtain an RCS 1.a.3 Caplete nodification of post accident sapling (Note 5) saple mder all accident conditions and systen to tie in decay heat saple lines with the nodes of operation.

shielded mactor coolant saple line in the nuclear sapling roan.

84-03-02 CAS 2.a tbdify CAS to pennit sapling after 2.a.5 Cmplete nodification of Contairnent Atnosphem 06-01-84 contairnent isolation. Provide tapera-Sanpling Systen as described in GRN response ture and pmssure indications at the gas to iten 2.a.2 dich was provided to fit on suple banb. Dewlop procedures to Pty 11,19G4 (5211-84-2105).

quantify the saple including taperature and pressure corrections.

8 M 3-04 SHIELDING 4.1 Reviseshieldingstudy(RCSsapling) 4.1.e Provide tarporary shielding for the saple sink drain (Note 3) to include the following contributors:

line and mvise procedure to verify shielding is in a - Sink drain trap and drain Ifne.

place prior to initiation of RCS saple flow.

b - thdiluted coolant in the sink.

c - Scattemd radiation.

d - thshielded auxiliary lines.

e - Residual contamination during o* = = m t sa ple atts pts.

f - Airtome radioactivity originating frun sink.

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5211-84-2157 Attachrent I r

Page 2

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POST ACCIENT SMFLItG AND MNITCRING (IR 84-03)

C WISl#0 LNG ITD6 (PUTE 2)

IR GPLN Targeted Its Original Action Cmpletion s

No.

Inspection ibport Itsn No.

Rsmining CPlH kt'en Date s

84-03-07 SMPLING #0 ANALYSIS OF PLAKI EFFUINTS (PMP-5) 7.a Develop procedums for collection of 7.a.1 Investigate the collection, hendling, and analysis Cmplete repmsentative plant effluent sanples of high dose rate sanples as described in 7.a. nake (Note 1) including provisions for handling and the necessary pmcedural modifications, and perfonn analyzing high dose rate sanples.

tine and notion studies for the resultant process.

2 7.a.2 Pmvfde dose calculations based on the tint.and motico' See Attachrent 2 studies for the process dich msults frd7.a.1.

^

~Qs Other PASS Ca mitments 9.a Cmplete installation of seismic rack for bottled (Note 4) air to serve as backtp air for eductor in the Contaiment Atmospnere Sanpling System.

NOTE 1 - This procedure is available at the site for inspection.

NOTE 2 - Item sich wre reported cmplete in pmvious transmittals have been deleted.

NOTE 3 - Cmpletion of this iten has been dela# amiting the results of an engineering evaluation to detennine if the mumuM 4

shielding would be pmhibited due to floor loading mstrictions. GPlM will continue to track this iten mtil resolved.

i NOTE 4 - Installation of the seismic rack for bottled air has been cmpleted except for receipt and installation of qualified t4ing connectors and bottles of the correct size. GPtm will continue to track this itan mtil cmplete.

NOTE 5 - This modification is scheduled to be installed during the eddy curmnt outage dich will begin 120 days after obtaining 50% power or 90 days after achieving 100% power.

0002u