ML18078A508
| ML18078A508 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/06/1978 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 7812180260 | |
| Download: ML18078A508 (5) | |
Text
Distribution NRC PDR _,.-
DEC 0 6 1978 Loe a 1 PDR LWR #3 File R. Boyd D. Vassallo F-. Wi 11 i ams
- o. Parr D I t *1 50-311 A. Dromerick QC <e r 0.
M. Rush brook R. Mattson Mr. R. L. Mittl, General Manager D. Ross Licensing ~nd Environment J. Knight Engineering and Construction DepartmerR:* Tedesco Public Service Electric and Gas ComparJ3r* -DeYoung 80 Park Place Newark, New Jersey 07101
Dear Mr.* Mittl:
V. Moore R. Vollmer M. Ernst R. Denise ELD IE "(3)
(w/extra copies)
BCC:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMAfION ~OR THE REVIEW OF THE SALEM UMIT 2 FINAL SAFETY.ANALYSIS REPORT ( FSAR)
As a result of our continuing revie11J of -tne Salem FSAR, we find that we need additional information to complete our eva1 uation.
The specific information required is listed in the Enclosure.
In order to maintain our review schedule, this addit1onal information is required promptly.
Please contact us if you desire any discussions or clarification of the enclosed request. *
Enclosure:
'Request for Additional Information cc w/enclo&µne:*.
See next page 7 8 1 2 1 8 o 2 COo
.s i*ncere 1 y, OriginaJ Signed bJ:
Olan Parr-
- ..J Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management v
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me FORM 31a (9*76> NRCM 0240
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u~s. GOVERNMENT PRINTIN.. G OFFICE: 1978 - 265 - 769
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. l Mr. R. cc: *Richard Fryling, Jr., Esq.
Assistant General Counsel Public Service Electric & Gas Company 80 Park Place\\
Newark 9 New Jersey 07100 Mark Wetterhahn, Esq.
Conner, Moore & Cober 1747 Pennsylvania Avenue, N.W.
Suite l 050 W~shington, D.C.
20006 Mr. Leif J. Norrholm U. s. Nuclear Regulatory Corrmission Region I
. Drawer I Hancocks Bridge, New Jersey 08038
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' j REQUEST.FOR ADDITION_AL INFORMATION SALEM NUCLEAR GENERATING STATION UNIT 2 DOCKET NO. 50-311 7.00 Instrumentation and Control 7.41 Based on your ~esponse in a letter from R. L. Mittl to 0. D. Parr dated October ~0, 1978, we have determined that additional information is needed to complete our evaluation of environmental qualification of safety-related Class lE equipment_.
The follow*ing are the specific Hems on which additional information is required from you.
(1)
The MSLB accident environmental envelop inside the containment should be provided to verify the adequacy of the qua 1 i fi ca ti on of those Class lE equipment required to mitigate this event.
(2)
In your response you stated that Barton Model 763 and 764 trans-
. mitters were found acceptable on the North Anna plant.
We orally informed you that the review of thses transmitters is being done as part of our review of the Westinghouse reverification program, and that thi~ review has not been completed, and that NRC gave only conditional approval for the use of these Barton transmitters on the North Anna plant for an interim period only.
Provide the information necessary to demonstrate that the Barton transmitters are acceptable for use for an interim period at Salem Unit 2.
(3)
The qualification data for the Rosemount transmitter (Model 1153A) was provided in a Rosemount report (No. 3788) which was first submitted on the AN0-2 docket and referenced by you.
We have found the following two~problems in this test report.
(a)
The temperature profile for the saturated steam test:shows a rise time of about 3 minutes from room temperature to the maximum temperature.
However, the typical rise time at Salem plant under LOCA is about 10.to 20 seconds~ Therefore, demon-strate how the test results ih Rosemont report No.
~788 apply to Salem Unit 2.
(b)
The test setup and the actual field installation are not the same.
The installation interface was not tested.
The AN0-2 appli~ant provided additional test data to resolve these concerns.
We require that you provide additional information (as was furnished on AN0-2 docket) to resolve the above stated concern.
(4)
We require that you identify the model numbers of ASCO solenoid valves installed inside the containment at the Salem Unit 2 plant.
One ASCO report (CP-C9539) has been submitted to NRC on the North Anna docket.
We request that you verify and confirm that the valves
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installed at Salem Unit 2 plant are covered by that report.
Otherwise, provide additional information on the qualification of the solenoid valves.
(5)
We requir~ that you submit the NAMCO report covering limit switches that was
~eferenced in the FSAR.
It is our position that limt switches for containment isolation valve position indication should be qualified to the most severe containment environment.
We require that you identify and justify the use of those limit switches that will not meet this qualification requirement.
(6)
We require that you su~mit for q~r review an environmental qualifi-cation test plan and test resulgs for instrument panels located inside the containment for transmitters and solenoids enclosure.
(7~ For seismic qualification of safety related equipme~t, we require that you provide additional information on qualification reports that describe the test procedures and test results, and the
. manufacturer's model number, and type for each piece of equipment listed in the FSAR tab 1 e Q7. 18-1. (see Qi. 40) *..
(8)
Most plant areas that contain safety related equipment depend on the continuous operation of environmental control systems to maintain the environment in those areas within the range for which the safety related equipment installed in those areas is qualified.
. It appears that there are no requirements for maintaining these environmental co~trol systems in operation while the plant is shutdown or in hot standby conditions.
(Technical Specifications on*ly require that the control room emergency air conditioning system shall be operable).
During periods when these environmental control
.systems are shutdown the safety related equipment could be exposed to environmental conditions for which it has not been qualified.
Therefore, the safety related equipment should be qualified to the extreme environmental conditions that could occur when the environmental control equipment is shutdown or these environmental control systems should operate continuously to maintain the environmental conditions within the qualification limits of the safety related equipment.
Since you have not demonstrated that the safety related equipment installed at the Salem Unit 2 plant was qualified to the extreme environmental conditions that could occur when the environmental control equipment is shutdown, we require that an environmental monitoring system should be provided.
This environmental monitoring system should, at a minimum, m~et the following requirements:
The conrol room should receive an ~larm when the temperature range has been exceeded.
This alarm should be provided by instrumentation which should be:
(a) of high quality,
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.. (b) periodically tested to verify its functional capabilHy by plant technical specification requirements, and (c) energized from continuous power sources.
The oberator should have a method of maintaining a continuous record of the temperature during the time that the environmental conditions exceed the normal limits.
We also require that you commit to provide an abnormal occ0rrence report to the NRC when the temperature exceeds the value for which the equipment was qualified.
I~ addition, if the qualification temperature is exceeded we require that you provide the results of an analysis to demonstratG thDt the excess temperature has not degraded the involved Class lE equipment below an acceptable level for continued plant operation.
State your int0nt to meet our requirements regarding this matter.