ML20212M857
| ML20212M857 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/22/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| References | |
| IEB-86-002, IEB-86-2, NUDOCS 8608270309 | |
| Download: ML20212M857 (4) | |
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2 UNITED STATES
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NUCLilAR REGULATORY COMMISSION 1
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.j WASHINGTON. D. C. 20555
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August 22, 1986 Docket No.: 50-219 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forired River,riew Jersey 08731'
Dear Mr. Fiedlar:
SUBJECT:
AMENDMENT NO. 95 S.1FETY EVALUATION AND STATIC-0-RING DIFFERENTIAL PRESSURE SWITCHES This is in response to your letters dated May 27 and July 30, 1986, on the reactor protection system switch replacement.
In the May 27, 1986, letter, you stated that (1) the Static-0-Rino (SOR) differential pressure switches in the reactor water level (RWL) low function will be replaced by an analog trip system, (?) this analog trio system will have level indication to provide a daily channel check for this function, (3) differential pressure gauges will be installed across the SOR switches in the RWL low-low function to provide a d311y check for this function, and (4) the remainder of tne project discussed in the meeting of January 23, 1986, with the staff to replace existing differential pressure and pressure switches with SOR switches has been deferred.
Items (2) and (3) were in response to the staff's Safety Evaluatien (SE) dated November 30, 1985, for Amendment No. 95 and Items (1) and (4), to the erratic behavior of S0P suitches at Oyster Creek in the RWL low function in the last 4 months of Operating Cycle 10.
InAmendmentsNo.91and95,dhtedNovember19and30,1985, respectively, we approved the replacement.of the Yarway RE02s and RE05s by the SOR switches in the RWL low and low-low functions.
In Amendment No. 95, we requested GPU Nuclear (the licensee) to (1) establish an additional level cf administrative control to the existing procedure on returning the SOR switches to service which would show the switches communicated with the reactor vessel, (2) report promptly to the staff any loss 'of operability of the RWL instrumentation and (3) provide, prior to the resta'rt from the Cycle 11 Refueling (Cycle 11R) outage, visual indications for'a daily channel check for the SOR switcher or provide a justification for not needing this daily channel check, address $ng the staff's concerns in the SE. The additional administrative control provided by the licensee was acceptable and is discussed in the meetino summary dated February 24, 1986. The loss of operability in Operating Cycle 10 for the RWL instrumentation was reported promptly to the staff and is discussed in the
't meeting sumaries dated February ?4 r.nd March 14, 1986. This loss of operability was the erratic behavior of the SOR Ewftches in the RWL low function mentioned above. The differential pressure om ges and remote indicction for the analog trip system er.d the SOR switches in the RWL low and low-low functions, respec-tively, are to provide the channel check for these function'; as we reque'ited.
Therefore, ycu have met the requirements in our SE for Amendment No. 95.
8608270309 860922 PDR ADOCK 05000219 P
2 In your letter dated May 27, 1986, you stated that two of the transmitters for the analog trip system will be paralleled with differential pressure gauges, two transmitters for this system will have remote indication in the control room and the SOR switches will have differential pressure gauges installed across each switch. The gauges and the remote indications are to provide the means for a daily channel check for the analog trip system and the SOR switches. Because Amendment No. 95 was a one-time-caly change which was effective only from November 8, 1985, to the restart from the Cycle 11R outage, the requirements for this equipment on restart from the current Cycle 11P outage will be the original requirement prior to Amendment No. 95; that is, a daily channel check.
Therefore, the licensee will be installing the differential pressure gauges and the remote indication to provide the means for the required daily channel check at the restart from the current Cycle 11R outage.
A charnel check is defined in the Technical Specifications as a qualitative determination of acceptable operability by observation of channel behavior during operation. The channels being discut. sed here are the RWL low and low-low functions. The means provided for a channel check should indicate the behavior of the sensor for the channel. The remote indication for two trans-mitters in the analog trip systcm do this and are, therefore, acceptable for providing a channel check. The differential pressure gauges for the SOR switches will indicate the differential pressure across the SOR switch membrane and, because there is no sensor within the switch itself that coJ1d provide some measure of channel behavior, these differential pressure gauges are also acceptable for providing a channel check. The use of SOR switches for the RWL low-low function in view of the erratic behavior of SOR differential pressure switches will be discussed separately below. The dif-ferential pressure gauges for two transmitters in the analog trip system provide indication of the reactor pressure at the sensor for the chanr.el but do not indicate the behavior of the sensor for the channel.
The channel check for the Yarway RWL instrumentation which were replaced in the Cycle 10M i
outage by the SOR switches provided an indication o# the behavior of the sensor for the channel. Therefore, these differential pressure gauges are not accept-able for providing a channel check for these channels of the analog trip system without further justification. You should provide justification that these gauges will indicate the behavior of the sensor for these channels or provide the same indication to be installed for the other two transmitters. Acceptable means for a channel check must be provided before the restart from the Cycle 11R outage.
The erratic behavior of SOR differential pressure switches is the subject of the IE Eulletin No. 86-02 on SOR Model 102 and 103 switches, dated July 18, 1986. We have reviewed your July 30, 1986, response to item 1 of the Bulletin. We note that this response supercedes your May 27, 1986, letter in that you have now committed to replace the SOR switches in the RWL low-low function by an analog trip system in the Cycle 11R outage. An appropriate channel check must also be provided for this system before the restart from the current Cycle 11R outage.
. August 22, 1986 3ecause there are SOR Model 103 switches in the safety-related core spray system and drywell suppression system, you may need to submit reports to meet items 3, 4, 5 and 6 of the Bulletin. These reports, if needed, are required prior to the next critical operation of Oyster Creek to be in compliance with the Bulletin. The next critical operation for Oyster Creek would be the restart from the current Cycle 11R outage. These reports, if needed, should be submitted as soon as practical before the restart from this outage.
The reporting and/or recordkeepirg requirements contained in this letter affect fewer than ten respondents; therefore, OMB Clearance is not required under P.L.96-511.
Sincerely,
(, Jack N. Donohew, Jr., Project Manager i BWR Project Directorate #1 Division of BWR Licensing cc: See next page DISTRIBlITION Docket File NRC PDR local PDR BWD1 Reading R. Fernero OGC-B(For info only)
E..icrdan B tirimes J. Partlow J. Zwolinski J. Donohew C. Jamerson M. Srinivasan ACRS (10)
G. Lainas G. Holahan OC file N. Thcmpson
- NOTE: PREVIOUSLY CONCURRED j
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_____:._..____...:p NAME :CJamerson * :(1 onohew:en :JZwolinski
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DATE :7/10/86
- 8/22/86
- b/n?/86 OFFICIAL RECORD COPY i
Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generatino Station Generating Station cc:
Mr. Ernest L. Blake, Jr.
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Strett, N.W.
Post Office Rox 445 Washington, D.C.
20036 Forked River, New Jersey 08731 J.B. Liberman, Esauire Comissioner Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 301 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineerina U.S. Nuclear Regulatory Comission Department of Environmental Quality 631 Park Avenue 380 Scotch Road King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 RWR Licerising Manaaer i
GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 11?
Trenton, New Jersey 08625 Mayor Lacey Township i
818 West Lacey Road Forked River, New Jersey 08731 Licensing Manaaer Oyster Creek Nuclear Generating Station Mail Stop:
Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731 1