ML20106E362

Forwards Addl Info Supporting 841002 Proposed Change to Tech Specs Re Main Steam Line High Radiation Trip Level Setpoint for Hydrogen Addition Test,Per 841016 Telcon

ML20106E362
Person / Time
Site:	FitzPatrick
Issue date:	10/22/1984
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
JPN-84-70, NUDOCS 8410290185
Download: ML20106E362 (5)

Text

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& Authority October 22, 1984 JPN-84-70 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Regarding Main Steam Line High Radiation Monitor Trip Level Setpoint.

Reference:

1. NYPA letter, J.P. Bayne to D.B. Vassallo (NRC), dated October 2, 1984 (JPN-84-6 2) regarding same subject.

Dear Sir:

In Reference 1, the Authority submitted a proposed change to the FitzPatrick Technical Specifications regarding the Main Steam Line High Radiation Trip Level Setpoint for the hydrogen addition test.

In a conference call on October 16, 1984 between the NRC staff and the Authority personnel, the staff requested additional information. This additional information is enclosed as an Attachment to this letter.

8410290185 841022 ,

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-October 22, 1984

'JPN-84-70

.Page 2 If you have any questions, please contact Mr. J.A. Gray, Jr.

of my staff.

Very truly yours, e +

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/- Bay irst Execut e Vice President Chief Operations Officer enc.

cc:. Office of the Resident Inspector-U.S. Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Mr. J.D. Dunkleberger Division of Policy Analysis and Planning

'New York State Energy Office Agency Building 2, Empire State Plaza Albany, New York 12223

, ATTACHMENT TO JPN 70 Propo ed change to James A. FitzPatrick Technical Specifications for the Main Steam Line Radiation Monitor Setpoint The Authority and the NRC staff members held a telephone conversation on October 16, 1984. The proposed change to the FitzPatrick Technical Specifications for the Main Steam Line Radiation Monitor Setpoint was discussed. In response to NRC staff requests, the following additional information is provided.

A. Test Schedule / Purpose

1. Pre-Implementation Test - Current plans are to perform a 2-3 day pre-implementation test in late November 1984 to develop information on:

a. Hydrogen and oxygen concentration relationships in the primary coolant

b. Changes (if an$ to plant chemistry and electrochemical potential of the primary coolant through on-line monitoring

c. Off-gas system performance

d. Steam line, in-plant and site boundary radiation surveys and shielding requirements to support a permanent program

e. Adequacy of injection points

f. Performance of the hydrogen addition system for controlling oxygen levels in the primary coolant

g. Adequacy of sampling equipment and procedures

h. Feasibility of a permanent hydrogen addition system The pre-implementation test involves injecting hydrogen in the feedwater from 0 to approximately 60 SCFM in pre-defined increments, with a stoichiometric amount of oxygen added upstream of the recombiner to aid in proper off-gas recombination. During this stage various chemical and operating parameters (02, H2, ECP) are monitored to define the IGSCC free (immune) regime for JAF.

2. Constant Extension Rate Test (CERT) / Materials Verification - The CERT will be performed from early to mid-December 1984 for 14 days, bringing the total test duration to 17 days. The CERT will be conducted to:

a. Insure that the immune regime has been attained by a materials confirmation of a CERT test with highly sensitized 304 SS.

b. Attain steady state readings for electrochemical potential which, along with reactor coolant oxygen and conductivity, are the key indicators for the above regime.

.,- This portion of the tent involvan-operating the

.- . plant at steady state power and full hydrogen f ' injection (as defined by the pre-implementation test) - for 350 operating hours, as recommended by GE and EPRI.

LNote: The test schedule is. highly dependent upon timely review and approval of the technical specification change.

B. Design All of>the test equipment is designed and operated by LGeneral Electric and is proprietary. .This includes the hydrogen and oxygen injection / flow control, chemical

-monitoring, ECP and the test autoclave for the CERT.

-The equipment will be located in areas of the plant consistent with the ALARA program.

.C.. Radiological /ALARA Considerations A preliminary engineering evaluation on the use of

. hydrogen water chemistry (H2 WQ at JAF was. conducted in May 1984. One of the areas addressed was the impact of H2 WC-on in-plant and site boundary radiation levels. Some of the areas expected.to have significant increases.in radiation levels are the south side of the turbine floor, heater bays, steam tunnel, condenser bay and turbine-building roof. Based on the test results from Dresden 2 (

Reference:

GE Report NEDC-23856-7, October 1982) which is the only plant currently using H2 WC, the radiation level throughout the Steam System is expected to increase appraximately by a factor of 6.. In addition to normal radiation and ALARA

. practices / procedures utilized during the test, an ALARA review will be conducted in conjunction with the study mentioned above. Controlled access and administrative controls will be used to limit exposure during the test.- While recognizing that in-plant and site boundary doses will invariably increase with increasing hydrogen flow, no significant safety hazards are expected.

A complete set of in-plant surveys will be taken at various hydrogen flow rates (i.e. , radiation levels) in addition to normal survey points. Additionally, area radiation monitors will be logged at specific increments of hydrogen addition. Site boundary surveys will be conducted with Reuter Stokes high pressure ionization chambers which are appropriate for measuring

'N16 gamma. Gamma isotopic surveys will be conducted in

' the environm(:nt during the CERT test by an outside

. contractor. Surveys will be compared with normal operating data before/af ter the test.

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- . . _ . _ _ w__..- _._._ _.____ _._.,_._._ _ _ _

-~ D. Significent Hezerde Conaldsrations

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The capability to monitor for fuel failures will be r.aintained via (1) main steam line radiation monitors which will still be functional for isolation and Reactor Protection System (RPS) signals, (2) increased frequency of radiation surveying, (3) daily primary reactor coolant isotopic analysis, (4) continued operability of the SJAE off-gas radiation monitor (it should be noted that items 1 and 4 are required by Technical Specifications) .

During the entire test, the expected gas consumptions are 700,000 SCF H2 and 350,000 SCF O 2. Two standard size (115,000 cu f t.) tube trailers will be used for hydrogen (with no more than two on site at one time) , connected by a dual manifold and electrically grounded. The oxygen will be supplied cryogenically (liquid with an approximate 3000 gallon tank.

Administrative controls will be enforced to ensure access to these areas are controlled. The total quantities of hydrogen and oxygen on-site at any one time, will remain the same for the proposed 17 day test as they would be for a 3 day test. Furthermore, hydrogen and oxygen supplies will be located in areas consistent with fire protection requirements.

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