ML19345H139
| ML19345H139 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Calvert Cliffs, Palisades, Saint Lucie, Maine Yankee, Fort Calhoun  |
| Issue date: | 09/12/1978 |
| From: | Conner E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19345H132 | List: |
| References | |
| NUDOCS 8105010030 | |
| Download: ML19345H139 (5) | |
Text
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ENCLC'U;E 1
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' :e UNITED STATE:
NUCLEAR REGULATORY CC'.17.11cSICf4
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WASHINGTON, D. C. 20$55 g
Septenter 12, 1978
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Dockets !!os.: 50-255, 50-285, 50-309, 50-317, 50-318, 50-335 and 50-336 BALTIt:0RE GAS & ELECTRIC C0!iPAriY (BG8E), C0!!SUMERS POWER LICENSEES:
COMPANY (CP), FLORIDA POWER & LIGHT C0t'PA!;Y (FP&L), !!AI!!E YAt:KEE AT0!:IC PO'<.'ER COMPANY (fiYAP), NORTHEAST tlUCLEAR ENERGY C0itPANY (N!!ECO), AtiD OMAHA PUBLIC POWER DISTRICT (OPPD)
CALVERT CLIFFS UNITS NOS.1/2, FORT CALHOUN, Wi!NE YANKEE,
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FACILITIES: MILLSTONE UNIT NO. 2, PALISADES AND ST. LUCIE UNIT NO. 1.
ilINUTES OF MEETING HELD ON AUGUST 2,1978 WITH THE ABOVE
SUBJECT:
LICENSEES TO DISCUSS THE REACTOR PROTECTION SYSTEM (RPS CHANNEL INOPERABILITY.
A meeting was held on August 2,1978 with the above licensees and representatives of Combustion Engineering (CE) to discuss the length I
l of tima a single failed RPS channel should be bypassed before requiring it to be tripped. Attachment 1 is a list of attendees.
remarks (M. Conner) and a history of the inoperable i
The NRC made opening (J. Burdoin).
In a similar meeting on March 16, 1976, RPS channel suhi.'et
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we determined that the RPS had been reviewed and approved for a two-out-In a followup letter to each facility, we requested of-four logic only.
that each license propose Technical Specifications (TS) to include aHe failed RPS to be placed in'the tripped condition within one hour.
also stated that we would undertake a detailed review of the particular RPS that could result in a two-out-of-three trip logic requirement.
NNECO (A. Roby) pointed out that they wil'1 be the lead spokesmen on this subject. His important comments were:
1.
The NRC approved the RPS design at the operating license stage.
i There is no change in the requirements of the revised IEEE applicable 2.
standards.
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3.
They don't believe this to be a safety ccret r..
4.
NNECO believes that events following an inadvertent reactor shutdown,because of operating with one RPS channel tripped, might be a greater problem than one channel bypassed.
5.
The licensees do not agree with this requirement.
6.
They believe this should be a generic issue for all facilities.
We next had a general discussion of the agenda items (Attachment 2).
We asked FP&L and BG&E if the TS authorizing 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to repair an inoperable RPS channel had affected their operating efficiency. FP&L (G. Shamblin) stated that St. Lucie has not experienced any RPS failure that has resulted in outage time. BG&E (R. Olson) said he had not checked into such records for the Calvert Cliffs units. MYAP (J. Garrity) said it must result in a definite value impact. The NRC ('). Tondi) discussed agenda items 1 and 2 pointing out that the RPS's at Calvert Cliffs and St. Lucie do not have adequate separation to justify a two-out-of-three systein. He also stated that he saw no evidence that the o'her CE designed facilitios would meet this criteria. The staff (J.
foin) presented notes on the RPS channel separation inspection of Calvm Cliffs (Attachment 3).
After a utility caucus, the licensees requested:
.l. That we continue the plant RPS inspections to determine if a two-out-of-three logic was justified; and 2.
That we considar this a long term generic issue for all facilites.
The staff (D. Tondi) said we would schedule the visits to begin within I
one month. Since the containments should be accessible for the RPS I
inspection, we discussed visiting Maine Yankee first. The staff (M. Conner) comitted to schedule the visits and notify each licensee of such scheduling.
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E.L. Conner, Project Manager Operating Reactors Branch #4 Division of Operating Reactors l
Attachments:
l.
List of Attendees 2.
Agenda 3.
RPS Channel Separation at Calvert Cliffs
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ATTACH!! Erit 1 f
MEETING HELD 0:18/2/73 HITH i
D. Sente11 M. Conner D. Tondi R. Bockhorst D. Thatcher BG3E J. ItGough D. Brinkman
'J. Burdoin R. Olson S. Breon R. Silver FP&L G. Shamblin CP, D. Hoffman F. Butler-MYAP J. Garrity G. Dowd P. Yandow N. Pillsbury OPPD B. Hickle S. Khan G. Peterson e
NNECO R. Kacich E. Farrell H. Haynes J. Clark A. Roby 9
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ATTACHTICT!T 2_
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RPS CHAT:f:EL It nPERABil.!TY
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MEETING AGE l:Ds_
AUGUST 2. 1978
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SUBJECT:
REACTOR PROTECTIO:1 SYSTEM (RPS) CHA!U!EL I!!0PEPACILITY l.
Single failure criteria as it applies to two penetration areas and as it applies to energizing RPS channels frca redundant vital buses, for 2-out-of-3 system.
Separation / single failure in CE RPS cabinets as it applies to 2.
terminal blocks, logic units and co=.on uireways in bottom of cabinets.
3.
Separation of Conduit routing for RPS.
4.
Separation of cable tray routing for RPS.
System reviewed as a 2-out-of-4 system and not reviewed as a 5.
2-out-of-3 system.
Millstones RPS is functionally identical to Calvert Cliffs.
6.
- 7.,0perating experience as it applies to frequency and duration of j
RPS channel outage.
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ATTACHMENT 3 RPS - CHAMMEL SEPARATION CALVERT CLIFFS 1.
Separation of Sensors 2.
Sensing Lines & Transmitters in Containment are Vulnerable to Pipe Whip, Jet Impingement and Other High Energy Events Conduit for Circuits from Transmitters in Containment Ditto 3.
Item 2 above 4.
Circuitry Termination at RPS Panel 5.
Separation at Penetrations 6.
Separation in Cable Spreading Areas Split in Logic Matrix to Eliminate Consequences of a Hot Short on 7.
Scram Actuate Relays (K)....K )
4 8.
Sensor Channels:
a) Pressurizer b) RWST Level c) Steam Generator Level & Pressure d) Ex-core Neutron Detectors j
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