ML18038A456

Forwards Addl Info Supporting Application to Use Alternative to 10CFR50.55a Requirements.W/Two Oversize Drawings

ML18038A456
Person / Time
Site:	Nine Mile Point
Issue date:	03/23/1989
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8903280311
Download: ML18038A456 (8)

Text

"'ccp~~TED 3]RIBUTI0N DEM0NS~TloY SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8903280311 DOC.DATE: 89/03/23 NOTARIZED: NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION TERRY,C.D. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION

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Document Control Branch (Document Control Desk)

SUBJECT:

Forwards addi info supporting application to use alternative to 10CFR50.55a requirements.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: OR Submittal: Inservice Inspection/Test ng/Relief from ASME Code NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 LA 1 0 PD1-1 PD 5 . 5 SLOSSON,M 1 1 INTERNAL: ACRS 6 6 AEOD/DSP/TPAB ARM/DAF/LFMB 1 0 NRR/DEST/MEB 9H NRR/DEST/MTB 9H 1 1 NUDOCS-ABSTRACT OGC/HDS1 1 0 FILE 0 RES/DSIR/EIB 1 1 EXTERNAL: EG &G BROWN, B 1 1 EG&G ROCKHOLD i H 1 1 LPDR 1 1 NL 007 HEMMING 1 1 NRC PDR 1 1 NSIC 1 1 NOIR 'ZO ALL "RIDS" RECIPIEtGS'IEASE HELP US TO REDUCE WASTE.'XNZACZ 'lHE DOCUMENI'OhURDL DESK, ROOM P1-37 (EZZ. 20079) TO ELOCUTE YOUR NAME FRY DISTRIKTZIQN LISTS FOR DOCUMEMZS YOU DGNiT NEEDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24

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V NIAGA A 0 MQHAWK NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 March 23, 1989 NHP1L 0375 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C-.. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Gentlemen:

Attached please find additional information supporting our application to use an alternative to the requirements of 10 CFR 50.55a (NMP1L 0350 dated January 18, 1989). This additional. information is provided in response to comments from the Nuclear Regulatory Commission's staff.

Very truly yours, NIAGARA MOHANK POHER CORPORATION C. D. Terry Vice President Nuclear Engineering and Licensing KBT/pns 6800G Attachment xc: Regional Administrator, Region I Hr. R. A. Capra, Director Hs. H. H. Slosson, Project Manager Hr. N. A. Cook, Resident Inspector Records Management 89032803ii 890323 PDR ADOCK 05000220 P PDC

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NIAGARA MOHANK PONER CORPORATION, NINE MILE POINT UNIT 1 DOCKET NO. 50-220 DPR-63 After welded repairs or replacements, a reactor system hydrostatic test is normally performed at a test pressure 1.08 times the nominal operating pressure (1035 psig). The Code specified minimum test temperature corresponding to this test pressure is 200'F (reference Table INB-5222-1).

The minimum temperature for pressurization required by Technical Specification 3.2.2.c is more restrictive (220'F), and therefore, is the governing requirements The Technical Specification test temperature is based on stress intensity factors according to Appendix G of ASME Section III. Changing the test temperature does not affect the validity of the pressure test provided the temperature is below saturation; Furthermore, the test temperature is an important parameter for fracture toughness considerations. The reactor is designed for a limited number of hydrostatic pressure tests over the 40-year life of the vessel. The performance of this test has a major impact on the outage schedule. Relief valves have to be gagged to prevent inadvertent operation. After the test, the gags have to be removed. Thus, for minor repairs or replacements, such as replacement of the drain valves, an alternative to the hydrostatic test, a system leakage test is proposed.

The ASME Section XI system l.eakage test is performed at nominal operating pressure (1035 psig) and at the minimum temperature required by Technical Specification 3.2.2.c (200'F), reference paragraph INB-5230(a). Performing this test at a higher pressure would be a burden similar to the hydrostatic pressure test. The relief valves would have to be gagged to prevent inadvertent operation. Consequently, there would be no advantage of an elevated pressure system leakage test over performing the ASME Section XI hydrostatic test. An ASME Section XI system leakage test is performed during startup after every refueling outage.

In response to the Nuclear Regulatory Commission staff's requests, we have included the attached boundary diagram, F-42234-C, and the piping elevation showing the configuration of the reactor vessel drain line and the location of the new welds for the replaced valves.

6800G

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