ML20246A308

Discusses ASME Code Relief Request for Diesel Generator Starting Air Check Valves.Reason for Relief Request Listed

ML20246A308
Person / Time
Site:	Brunswick
Issue date:	06/29/1989
From:	Le N Office of Nuclear Reactor Regulation
To:	Eury L CAROLINA POWER & LIGHT CO.
References
TAC-71090, TAC-71091, NUDOCS 8907060232
Download: ML20246A308 (3)

Text

,

i a pM t109 k UNITED STATES i

F'- 3 NUCLEAR REGULATORY COMMISSION Nf E WASHWGTON, D. C. 20555 k.....[ June 29, 1989 1

Docket Nos. 50-325 and 50-324 Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 27602 Dea'r Mr. Eury:

SUBJECT:

ASME CODE RELIEF REQUEST FOR DIESEL GENERATOR STARTING AIR CHECK VALVES - BRUNSWICK STEAM ELECTRIC PLAN 1, UNITS 1 AND 2, (TACNOS.71090AND71091)

On November 24, 1987, pursuant to 10 CFR 50.55a(g)(4), you submitted a revised In-Service Testing (IST) Program which included relief request number VR-26 1or the diesel generator starting air check valves, and program remark number V-08 which included both the diesel generator starting air check valves and the diesel generator starting air (jet assist) valves. The reason for your relief requests is as follow:

"The testing of these valves must be in conformance with ASME Section XI, subsection IWV 3520 code requirements. This subsection requires confirmation that each check valve disk is on its seat, by visual observation, by electrical signal initiated by a position indicating device, by observation of appropriate

, pressure indications in the system, or by other positive means. Literal

)

compliance with these requirements is impractical for the subject valves because tnere are no external or remote means to verify valve position during system operation, ncr is there an external means to manually cycle the valves."

On November 2,1988, you submitted a letter stating that you have completed a j review of periodic test procedures for these check valves and have determined  :

that relict request number VR-26 and program remark number V-03 need to be amended. You also submitted amended VR-26 and program remark V-08, and new .

relief request VR-31 with the letter.

The primary purpose of the revision to VR-26 and the new relief request VR-31 is that the diesel, of which these valves are a part, must be shut down and inspected at least every 18 months in accordance with Technical Specification 4.8.1.1.2.d.1. Plant procedures are being revised to take credit for disassen61y of these valves during these shutdowns. This represents a more conservative approach than identified in the previous program submittal in that 100% of the subject valves will be examined every 18 months versus the sampling required by the previous program.

~

O 8907060232 890629 PDR ADOCK 05000324 P PNU (01CO 16

D=

. f [r. Lynn W. Eury -2 June 29, 1989 The change in V-08 will allow the sample disassembly valves to be examined over a 2 year interval versus the current requirement of each refueling outage. This will provide more flexibility to the plant in that some of the valve disassembles may be performed during system outages versus exclusively during unit refueling outages as currently required by program note V-08.

In accordance with the requirements of 10 CFR 50.55(a)g, the staff has performed a review of your requests and has determined that certain ASME Code require-ments are' impractical, and therefore; has found that your proposed alternate testing method for meeting the Code and the current Grunswick TS, by disassembling and manually cycling these valves every 38 months, to be acceptable. Therefore, relief requests VR-26 ar.d VR-31 are granted. The proposed change to the Program Remark V-08 is granted on an interim basis until a more detailed evaluation of your proposal and the review of your IST program are evaluated. The staff has determined,pursuantto10CFR50.55(g)(6)(1),thatgrantir;c/reliefis authorized by law, will not endanger life or property or the oamon defense and security and is otherwise in the public interest. In making th s determination, the staff has given due consideration to the burden that could result if those requirements were imposed on the facility.

Sincerely, Original Signed By:

Ngoc B. Le, Project Manager Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc: See next page l DISTRIBUTION Docket' File NRC & Local PDRs PDII-I Reading <

SVarga Glainas t EAdensam PAnderson NLe OGC (for info. only)

EJordan B. Grimes ACRS (10)

LBMarsh HShaw

• SEE PREVIOUS CONCURRENCES I

[BSEP ASME CODE RELIEF LTR]

• LA:PDII-I *PM:PDII-1 *EMEB *0GC D:PDII-1 1 PAnderson p(e:gd [garsh __

pdensan

'd

~

0; ..'

Mr. !.. W. Eury Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. Russell B. Starkey, Jr. Mr. H. A. Cole

! Project Manager Special Deputy Attorney General Brunswick Nuclear Project State of North Carolina P. D. Box 10429 P. O. Box 629 Southport, North Carolina 28461 Raleigh, North Carolina 27602 Mr. R. E. Jones, General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director P. O. Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 P. O. Box 29520 Raleigh, North Carolina 27626-0520 Ms. Grace Beasley Board of Commissioners P. O. Box 249 Bolivia, North Carolina 28422 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 P. O. Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 l Atlanta, Georgia 30323 l Hr. Dayne H. Brown, Chief Radiatior. Protection Branch l Division of Facility Services N. C. Department of Human Resources 701 Barbour Drive

.Raleigh, North Carolina 27f03-2008 Mr. J. L Harna!,s l- Plant General Manager i Prunswick Steam Electric Plant P. O. Box 10429 Southport, North Carolina 28461 l

I I

_- _ - - - _ - -