ML17059B430

Forwards RAI Re Sys Leakage Hydrostatic Testing & Scram Time Testing TS Changes

ML17059B430
Person / Time
Site:	Nine Mile Point
Issue date:	02/10/1997
From:	Hood D NRC (Affiliation Not Assigned)
To:	Sylvia B NIAGARA MOHAWK POWER CORP.
References
TAC-M96907, NUDOCS 9702130228
Download: ML17059B430 (8)

Text

Mr. B. Ralph Sylvia Executive Vice Presid... Generation Business

.'r " Group and Chief Nuclear Officer Niagara Mohawk Power Corporation Nuclear Learning Center 450 Lake Road

Oswego, NY 13126 Februar

, 1997

SUBJECT:

RE(VEST FOR ADDITIONAL INFORMATION REGARDING SYSTEM

'EAKAGE/HYDROSTATIC TESTING AND SCRAM TIME TESTING TECHNICAL SPECIFICATION CHANGES, NINE MILE POINT NUCLEAR STATION UNIT NO.

1 (TAC NO. M96907)

Dear Mr. Sylvia:

The NRC staff is reviewing your submittal of September 26, 1996, regarding the proposed technical specification change to various surveillances performed during a refueling outage.

We find that additional information is necessary to complete our review.'our response to the enclosure is requested as soon as possible to support your current outage schedule.

If you have questions regarding the enclosure or are unable to meet the requested /response

date, please call me at (301) 415-3049, or e-mail me at dsh8nrc.gov.

Sincerely,

/s/

Darl S.

Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Request for Additional Information cc w/encl:

See next page DISTRIBUTION:

Docket File PUBLIC PDI-1 R/F SVarga JZwolinski SLittle DHood GGolub ACRS CCowgill, RI RPelton SBajwa OGC DOCUMENT NAME:

G:iNMPli96907.RAI To receive a copy of this document, indicate in the box:

"C" = Copy without attachment enclosure "E" = Co ith attachment enclosure "N" = No co OFFICE PH:PDI-1 E

LA:PDI-1 D:PDI-1 IIANE DHood/rsI SLIttI SBajwo DATE 02/ 0 /97 02/ j 0/97 D2/ r /97 Official Record Copy 9702l30228 9702l0 PDR ADQCK 05000220 P

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205.'i&0001 February 10, 1997 Hr. B. Ralph Sylvia Executive Yice President Generation Business Group and Chief Nuclear Officer Niagara Mohawk Power Corporation Nuclear Learning Center 450 Lake Road

Oswego, NY 13126

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SYSTEM

=

LEAKAGE/HYDROSTATIC TESTING AND SCRAM TIME TESTING TECHNICAL SPECIFICATION CHANGES, NINE MILE POINT NUCLEAR STATION UNIT NO.

1 (TAC NO. M96907)

Dear Mr. Sylvia:

The NRC staff is reviewing your submittal of September 26, 1996, regarding the proposed technical specification change to various surveillances performed during a refueling outage.

We find that additional information is necessary to complete our review.-

Your response to the enclosure is requested as soon as possible to support your current outage schedule.

If you have questions regarding the enclosure or are unable to meet the requested response

date, please call me at (301) 415-3049, or e-mail me at dsh8nrc.gov.

Sincerely, p,~~i~

Darl S.

Hood, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Request for Additional Information cc w/encl:

See next page

r

B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station Unit No.

1 CC:

Hr. Richard B. Abbott Vice President and General Manager Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. Martin J.

McCormick, Jr.

Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hs. Denise J. Wolniak Manager Licensing Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Mr. Kim A. Dahlberg General Manager Projects Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Mr. Norman L. Rademacher Plant Manager, Unit 1

Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 126

Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D.

Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza

Albany, NY 12223 Hr. F. William Valentino, President New York State

Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension

Albany, NY 12203-6399 Mark J. Wetterhahn, Esquire Winston

& Strawn 1400 L Street, NW Washington, DC 20005-3502 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, NY 13202 Supervisor Town of Scriba Route 8, Box 382

Oswego, NY 13126

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4 1

RE VEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION AMENDMENTS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT NO.

1 OPERATING LICENSE NUMBER DPR-63 DOCKET NO. 50-220 Pages

164, 165,

168, 170, and 174 add hot shutdown to the list of plant modes for. which the respective secondary containment LCO is required.

Is the addition of the hot shutdown condition a change to the plant design

bases, as the secondary containment LCO's (3.4. 1 through 3.4.4) will now be applicable during the hot shutdown mode7 This change appears to go beyond requiring the secondary containment LCO's for TS 3.7.2 only.

Do these changes represent a change to the plant design basesT

Also, comment on whether note (a) on page 246 may be similarly affected.

2.

3.

4.

5.

6.

7.

8.

Special Test Exception 3.7.2 provides a number of additional requirements involving LCOs in 3.4. 1, 3.4.2, 3.4.3, 3.4.4 and 3.4.5.

However, proposed TS 3.7.2 does not mention the individual action statements in 3.4. 1 through 3.4.5.

Confirm that if individual LCOs in 3.4.1 through 3.4.5 cannot be met, then the 3.7.2 action statement will be enforced, requiring the plant to immediately abort system leakage or hydrostatic testing and scram time testing activities and reduce the average reactor coolant temperature to g212F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

LCO 3.4.2.a, "Reactor Building Integrity - Isolation Valves" specifies ventilation system valves only.

Are there other valves that are used to ensure reactor building integrity which are not ventilation system valvesf If so, how are they covered during 3.7.2 operations?

LCO 3.4.4.a, "Emergency Ventilation System" is included under proposed LCO 3.7.2.

However, parts b,

c and d are not included.

Will these sections of LCO 3.4.4 also be in effect during operation under LCO 3.7.27 If not, justify.

LCO 3.4.5.a, "Control Room Air Treatment System" is included under proposed LCO 3.7.2.

However, parts b,

c and d are not included.

Will these sections of LCO 3.4.5 also be in effect during operation under LCO 3.7.27 If not, justify.

Confirm that all surveillance requirements for TS 3.4. 1'through 3.4.5 and for tables 3.6.2j and 3.6.21 will be in effect during TS 3.7.2

'operation.

From table 3.6.2j, will the High Radiation Refueling Platform LCO be applicable during 3.7.2 operation2 Which systems normally are used.for shutdown cooling7 Will any TS LCO's be bypassed due to isolation of shutdown cooling during the hydrostatic test?

Enclosure

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