ML20246D544

Forwards Request for Addl Info Re Evaluation of post- Defueling Monitored Storage SAR

ML20246D544
Person / Time
Site:	Three Mile Island
Issue date:	08/22/1989
From:	Masnik M Office of Nuclear Reactor Regulation
To:	Roche M GENERAL PUBLIC UTILITIES CORP.
References
TAC-69115, NUDOCS 8908280179
Download: ML20246D544 (4)

Text

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, 4 l . August 22, 1989 t

Docket No'. 50-320 1 l

Mr. M. B. Roche DISTRIBUTION Vice President and Director - THI-2 (Docket: File; MMasnik GPU Nuclear Corporation NRC & Local PDRs OGC P.O. Box 480 Plant File EJordan I Middletown, PA 17057 SVarga BGrimes BBoger ACRS(10) ]

Dear Mr. Roche:

SNorris l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR EVALUATION OF PDMS SAFETY ANALYSIS REPORT (TAC 69115) 4

Reference:

Letter with attached safety assessment, 4410-88-L-0068/0378P I from F.R. Standerfer to NRC dated August 16, 1988 re " Post l Defueling Monitored Storage Proposed License Amendment and i Safety Analysis Report" 6

By letter dated August 16,1988 (reference above) you submitted your Safety Analysis Report (SAR) for long term storage of the TMI-2 facility. Based on our continuing review of your SAR and after the recent visit to TMI-2, we have determined that additional information or further clarification is required.

We request that you respond to the enclosed questions.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents, therefore, OMB clearance is not required under P.L.96-511.

Sincerely,

/s/

Michael T. Masnik, Senior Prcfuct Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page k Oh o o p1 h\

[PDMS SAFETY ANALYSIS REPORT) \\

LA -4 / PM: -4 @D:PDI-4 SN rs MMasnik:cb tolz 8//A/89 8/'1A/89 8/p/89

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.- Mr. M.- B. Roche Three Mile Island Nuclear Station 1 BPU Nuclear Corporation - Unit No. 2 cc:

. Frank Lynch, Editorial Regicna1 Administrator, Region I The Patriot

'U.S. Nuclear Regulatory Commission 812 Market Street 475 Allendale Road Harr1sburg, PA 17105-King of Prussia, PA 19406

. Dr. Judith H. Johnsrud Robert- B. Borsun.

' Environmental Coalition on Nuclear Power Babcock & Wilcox 433 Orlando Avenue Nuclear. Power Division State College, PA- 16801- Suite 525 }

1700 Rockville Pike Rockville, MD 20852 Ernest L. Blake, Jr., Esquire Marvin I. Lewis Shaw, Pittman, Potts, and Trowbridge 7801 Roosevelt Blvd. #62

-2300 N Street, N.W. Philadelphia, PA 19152 Washington, DC 20037 Secretary Jane Lee U.S. Nuclear Regulatory Commission 183 Valley Road Washington, DC 20555 Etters, PA 17319 Sally S. Klein, Chairperson Walter W. Cohen, Consumer Dauphin County Board of Commissioners Advocate Dauphin County Courthouse Department of Justice Front' and Market Streets Strawberry Souare, 14th Floor Harrisburg, PA 17101 Harrisburg, PA 17127 Thomas M. Gerusky, Director Mr. Edwin Kinter Bureau of Radiation Protection Executive Vice President Department of Environmental Resources GPU Nuclear Corporation P. 0. Box 2063 100 Interpace Parkway Harrisburg, PA 17120 Parsippany, NJ 07054 Ad Crable U.S. Environmental Prot. Agency Lancaster New Era Region III Office 8 West King Street Attn: EIS Coordinator Lancaster, PA 17601 Curtis Building (Sixth Floor) l 6th and Walnut Streets l . Philadelphia, PA 19106 U.S. Department of Energy P. O. Box 88 l Middletown, PA 17057 David J. McGoff Francis I. Young Office of LWR Safety and Technology SeniorResidentInspector(TMI-1)

NE-23 U.S.N.R.C.

U.S. Department of Energy Post Office Box 311 Washington, DC 20545 Middletown, Pennsylvania 17057 u____--__ __--

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' ADD 1110NAL QUESTIONS CONCERNING TMI-2 PDMS' SAFE 7Y ANALYSIS. REPORT

i. Provide calculations and evaluations of radiation levels from reactor vessel. (shine and backscatter) to the containment.

:2. Provide an evaluation of radiolytic generation of hydrogen and nitric acid in reactor vessel and its potential impact.

'3.. Provide additional information on the integrity and surveillance of welded and bolted flanges on containment penetrations.

'4 Provide additional detailed information on methodology for the determination of release rates and effluent concentrations for containment and AFHB gaseous effluents during passive mode conditions.

5. Provide additional information on pest control for the AFHB during.

PDMS.

6. Provide the basis that will assure containment isolation for penetrations which currently use check valves as a single closure for the containment boundary.

7 Provide flowpath, methodology for inplace DOP testing, and clarification of si:e and location of HEPA filter in atmospheric breather for containment.

B. Provide estimates of the total activity remaining in the Auxiliary Building, the Fuel Handling Building, and in each of the seven (7) other contaminated facilities at TMI-2.

'9. Will the HPR 219A or HPR-239 effluent monitor be used during PDMS for monitoring the station vent?

.10. Provide the PDMS dispos 2 tion of the oil reservoir in the Unit 2

Turbine Building.

13. Describe the air flow pathways between the Auxiliary Building and' the Fuel Handling Building during PDMS.

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