ML20154B488

Summary of 860123 Meeting W/Util in Bethesda,Md to Discuss Channel Checks for Operability of Lo & lo-lo Reactor Water Level Instrumentation Channels.List of Meeting Attendees & Affected Tech Spec Instruments Encl

ML20154B488
Person / Time
Site:	Oyster Creek
Issue date:	02/24/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8603040319
Download: ML20154B488 (8)

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UNITED STATES NUCLEAR REGULATORY COMMISSION h

WASHINGTON, D. C. 20555

.o February 24, 1986 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY:

Oyster Creek Nuclear Generating Station

SUBJECT:

JANUARY 23, 1986, MEETING WITH GPU NUCLEAR CORPORATION (GPUN) TO DISCUSS THE CHANNEL CHECKS FOR OPERABILITY OF THE LOW AND LOW-LOW REACTOR WATER LEVEL INSTRUMENTATION CHANNELS On Thursday, January 23, 1986, a meeting was held at NRC, Bethesda, Maryland, with GPU Nuclear (GPUN), the licensee, to discuss the channel checks for operability of the low and low-low reactor water level instrumentation trip switches, the staff's Safety Evaluation, Reactor Water Level Instrumentation Channel Check, dated November 30, 1985, and the licensee's response to the Safety Evaluation which is due before the commer. cement of the Cycle 11 Refueling (Cycle 11R) outage. The Cycle 11R outage is scheduled to begin in April 1986. Attachment 1 is the list of individuals that attended the meeting. is the material handed out by the licensee in the meeting for its presentation. The following is a sumary of the significant items discussed and the actions, if any, taken or proposed.

On November 30, 1985, the staff issued Amendment No. 95 to the Provisional Operating License for Oyster Creek. This amendment authorized the revision of the daily channel check for the low and low-low reactor water level instrumentation channels. This amendment was a one-time-only change which was effective only from November 8, 1985, to the restart from the Cycle 11R outage. The Safety Evaluation (SE) attached to the amendment requested before the commencement of the Cycle 11R outage (1) a justification of the existing reactor water level instrumentation channels addressing the staff concerns about the revisions to the channel checks for operability of the channels or (2) a statement that a daily channel check of the chant.els will be installed in the Cycle 11R outage.

If this amendrent is not changed by a future application, this amendment will revert to the previous requirement of a daily channel check for the channels at the restart from the Cycle 11R outage.

In the SE, the staff also requested the licensee to (1) report promptly any loss of operability of the low and low-low reactor water level instrument-ation channels and (2) provide an additional. level of administrative control to the existing procedures on returning the channels to service which will.

show the switches in the channels communicate with the reactor vessel.

It is these switches which, at the low-low or low reactor water level setpoints, actuate to initiate engineered safety features functions. This is discussed in the SE. The additional administrative control, accepted by the staff, 8603040319 860224 DR ADDCK 05000219 PDR J

. was to (1) open the isolation valve between the switch and the upper part of the reactor vessel (reference leg) which results in an indication in the control room of the reactor water level being less than low and low-low water level setpoints and (2) open the isolation valve between the switch and the lower part of the reactor vessel (measurement leg) which clears the above indication. This will be referred to as the communication test er C-test.

The agenda for this meeting was decided to be (1) the discussion of the switch that the licensee declared inoperable on January 21,1986,and(2) the discussion of the licensee's proposal for installing a daily channel check for the switches in the low and low-low reactor water level instrumentation channels.

On Friday, January 17, 1986, normal surveillance was conducted on the low reactor water level instrumentation channel switches. The setpoint for three of these switches was found to be outside the acceptance criteria. The switches were recalibrated, verified to be in comunication with the reactor vessel using the C-test described above and returned to service. Two of these three switches were again surveilled on Monday, January 21, 1986, and the drift in the setpoints were found to be insignificant, however, one switch would not reset during the C-test. The licensee declared this switch inoperable and decided to replace the switch.

The licensee stated that the C-test may have contributed to the failure of the switch to reset. The switch manufacturer had stated to the licensee that the C-test would cause a shift in the setpoint in the conservative direction but this would be temporary and the setpoint would return to its calibrated value. The licensee, however, has also decided to modify the C-test. On only the switch that was replaced, two additional valves, as shown in the figure on the next page, were added so that the pressure in the switch can be measured by a pressure gauge which is attached to either of the new valves.

By properly opening and closing the isolation valves, the pressure measured by the gauge would indicate that the switch was in proper comunication with the reactor vessel. The new method was explained to the staff by the licensee and accepted by the staff.

The licensee does not believe the problem with the one swit..; above is generic to the remaining seven switches. The licensee is now planning to install the new valves on the remaining switches as surveillance is required on these switches by the Technical Specifications and return all the switches to service using the modified C-test as described above.

The licensee stated that the switch manufacturer will be at the station site to inspect the inoperable switch to help determine the mode of failure. The results of this inspection will be shared with NRC and may change its position on not doing the surveillance immediately on the remaining seven switches. The licensee stated that it is not planning to proposed a change to the Technical Specification to make the valve modifications to the remaining switches.

VALVE PIPING

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1I SWITCH jfD(SALVES INSTALLED e

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s SIMPLIFIED SCHEMATIC 0F THE LOW AND LOW-LOW REACTOR WATER LEVEL INSTRUMENTATION CHANNEL SWITCHES t

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9 For the second part of the meeting, the licensee handed out a chart which is i.

The September 1985, December 1985 and September 1986 dates in the chart reflect 1) before.the low and low-low reactor water level instrument-ation was modified, 2) after the modifications were completed in the Cycle 10M outage and 3) after the new modifications to be discussed here are completed i

in the Cycle 11R outage. The staff issued its evaluation of the modification i

of the low and low-low reactor water level instrumentation in-the SE attached i

to Amendment No. 91 dated November 19, 1985.

The chart also contains references to the low-low-low reactor water level, high drywell pressure and main steam high flow instrumentation. These instrumentation were not involved in Amendment Nos. 91 and 95.

The licensee discussed the modifications which will provide a channel check for the low and low-low reactor water level instrumentation:

low - install Rosemount transmitters for the four existing RE-05 switches low-low - install permanent differential pressure gauges across the four switches.

These modifications will require rearranging the instrument racks. The licensee stated it is considering doing the modilications with the fuel out of the reactor vessel.

The staff requested the surveillance done to verify communication with the reactor vessel for the low-low-low reactor water level instrumentation channels before a channel is returned to service. The staff asked if there j

were instrumentation that could backup'the high drywell pressure and main steam high flow instrumentation both of which the licensee may proposed to I

delete the daily channel check? The staff stated that in accordance with 10 CFR 50.59 any modification which will result in a. change to the Technical Specifications must be submitted to. the staff for its review and approval.

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The staff stated that the licensee does not need to propose a change to Technical Specifications to return the channel check for the low and low-low l

reactor water level instrumentation channels to daily. - The channel check for this instrumentation in Amendment No. 95 will automatically revert to a daily channel check at the restart from the Cycle 11R outage. The staff also stated that doing these modifications to these instrumentation without fuel in the reactor vessel should not be an unreviewed safety question.

At the end of the meeting, the licensee and the staff discussed the licensee's i

proposed change to the Technical Specifications in its letter dated October 11,.

i 1985, for the reactor vessel isolation when the low-low reactor water level i

instrumentation is inoperable in the reactor shutdown mode. The licensee i

stated that it has decided to submit a new proposed change for reactor vessel isolation by April 30, 1986. The other change submitted-in the October 11, 1985, letter resulted in Amendment No. 95 dated November 30, 1985.

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. In summary, the following was agreed to in the meeting:

1.

The licensee will provide the surveillance that verifies comunication with the reactor vessel for the low-low-low reactor water level instrumentation channels before a channel is returned to service.

2.

If there is backup instrumentation for the high drywell pressure and main steam high flow instrumentation, deleting the channel check is acceptable to the staff.

3.

The licensee will infom the NRR Project Manager of the results of the manufacture's inspection of the inoperable switch.

The staff stated that the modifications discussed in the meeting for the low and low-low reactor water level instrumentation in the Cycle 11R outage should be done while the fuel is out of the reactor vessel.

hh k & h., Project Manager idack F. Donohew, BWR Project Directorate #1 Division of BWR Licensing Attachments:

1.

List of Attendees 2.

Licensee's handout cc:

R. Bernero R. Houston G. Lainas W. Hodges L. Phillips M. Scrinivasan DISTRIBUTION Docket EJordan NRC PDR BGrimes Local PDR JPartlow

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PD#1 Reading JDonohew 0 ELD CJamerson OC File JZwolinski ACRS(10)

DBL DBL:PD#1 JD5 jg JZwolinski 86 t /p /86 7

Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station cc:

G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W.

Post Office Box 445 Washington, D.C.

20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.

New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager 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 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 D. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office box 388 Forked River, New Jersey 08731

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ATTACHMENT 1 i

j MEETING WITH GPU NUCLEAR CORPORATION (GPUN)

January 23, 1986 4

r NAME ORGANIZATION J. Donohew NRC/NRR/ DBL l

M. Laggart GPUN d

A. Agarwal GPUN-i T. Hoatson GPUN J. Rogers GPUN 1

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R. Stevens NRC/NRR/ DBL i

G. Holahan NRC/NRR/ORAS l

R. Scholl, Jr.

NRC/NRR/0 RAS W. Hodges NRC/NRR/ DBL 1

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E AFFECTED TECHNICAL SPECIFICATION INSTRUMENTS 3

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1 1

l SEPTEMBER 1985 l

DECEMBER 1985 l

SEPTEMBER 1986 l

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Daily l

Daily l

l Daily l

l Inst. Channel l

Type i Dian. Ck.

l Type I

Chan. Ck.

I Type l

Chan. Ck. 1 I

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l l La Rx Water Level l

Yarway l

1/d l

SOR l RE21A (1) l Rosemount/ Fox l

1/d l'

Indicating I

Non-Ind RE21G XMTR/ Analog Trip l

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1 l Lc-Lo Rx Water Level l

Yarway 1/d l

SOR RE21A (1)

SOR 1/d l

l Indicating Non-Ind RE218-W/Ind. Gauges l

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l Ls-Lo-Lo Rx. Water l

Barton l

N/A l

Barton l N/A' SOR (2) l N/A l

-l Level i

Indicating ll Indicating Non-Indicating l

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1 1

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,1 Hi DW Press (Core l Barton l

1/d l

Barton 1/d l SOR l

N/A (3) l ll Cos11ng)

Indicating Indicating Non-Indicating l

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Main Steam Hi Flow I

Barton i

1/d l

Barton l

1/d l SOR (4) l N/A (3) l l

Indicating l

l Indicating l

l Non-Indicating I

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.(1)

Ttchnical Specification Change Request'#141.

-(2)

One Barton Lo-Lo-Lo indicator per header to remain.

(3)

Will require Technical Specification change.

(4)

One Barton' flow indicator per header to remain.

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