ML18078B213
| ML18078B213 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/26/1979 |
| From: | Zech G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904200291 | |
| Download: ML18078B213 (6) | |
Text
MARCH 2 6 19/Bi Docket No. 50-272 LICENSEE:
Public Service Electric and Gas Company (PSE&G)
FACILITY:
Salem, Unit No. 1 lJov<V ~
BJ-;) 7,;J:
SUBJECT:
sur~Ml\\R-Y OF MEETING HELD ON FEBRUARY 5, 1979 TO DISCUSS PROPOSED TECHNICAL SPECIFICATION CHANGES FOR SALEM UNIT NO. l
- On February 5, 1979, we met with representatives of Public Service Electric and Gas Company (PSE&G) to discuss proposed Technical Specifi-cation changes for Salem Unit No. l regarding moderator temperature co.efficient and rod position indication requirements A list of attendees is enclosed.
Significant discussions are summarized below.
Moderator Temperature Coefficient The licensee provided the basis for its June 29, 1978 Tech Spec. change proposal for Section 3.1.l.4 involving the moderator temperature coeffkient (MTC) limiting condition for operation for Sale.'1i Unit No. l.
We indicated that the Action Statements for those situations when t:1e MTC may be positive, should specifically include the requirement to establish and maintain the reactor coolant system boron concentration within limits sufficient to restore.the MTC to an acceptable value.
Also, to clarify the intent of the ACTION statements, we proposed to indicate that operation in MODES i-and 2 may proceed with a positive MTC provided the ACTION statements are heing observed.
The licensee agreed to consider these changes to their original proposal.
Rod Position Indication
~c,,J; COP The licensee indicated that the center control rod (205), rod.position indicator channel at Salem Unit No. l had a degraded signal and there-.
_fore had been declared "inoperabl e 11 and that ACTION statements of.
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Section 3.1.3.2 were being observed to allow aontinued reactor operat_ion.
In the event of a reactor scram, however, reactor startup would not be 790~20()~9/
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DATE~ '"'"""""""""............,............,..........,..........,..., '""""""'"""'""'...............................................,
MIC FORM 318 (9-76) NRCM 0240
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I Of'FICll Meeting Summary for
- Public Service Electric & Gas possible because of Tech Spec section 3.0.4 which does not allow entry into an OPERATIONAL MODE while under an ACTION statement.
The licensee therefore requested, in its letter of January 22, 1979, that relief from section 3.0.4 be granted to allow a reactor startup following a scram at least until March 31, 1979 at which time Salem Unit No. l is expected to commence a refueling outage and the cause of the degraded signal to that control rod indicator channel could be corrected and the channel returned to within specifications.
The basis for this request is contajned in the January 22, 1979 letter.
We advised the licensee that because of manpower limitations we could not. justify a review of the 1_icensee's request for a Tech Spec change that may not be needed.
We did indicate, however, that.should a scram occur, we would expedite our review to determine the acceptability of the licensee's request. *To assist us in this possible review, the licensee agreed to provide additional information in the form of in~core flux maps that have been taken at Salem Unit No. l as required by the ACTION statements.
Enclosure:
Attendance List Original Signed By Gary G. Zech, Project Manager Operating Reactors Branch #1 Division of Operating*Reactors
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Nae J:IOBM 318 (9-76) NRCM 024G
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Meeting Surrunary for
- Public Service Electric & Gas Docket File NRC PDR Local PDR ORBl Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut B. Grimes D. Davis D. Ziemann P. Check G. Lainas A. Schwencer R. Reid T. Ippolito V. Noonan J. McGough Project Manager OELD OI&E(3)
ACRS (16)
C. Parrish NRC Participants TERA J. R. Buchanan Licensee March 26, 1979
Docket No. 50-272 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 26, 1979
- LICENSEE:
Public Service Electric and Gas Company {PSE&G)
FACILITY:
Salem, Unit No. 1
SUBJECT:
SUMMARY
OF MEETING HELD ON FEBRUARY 5, 1979 TO DISCUSS PROPOSED TECHNICAL-SPECIFICATION CHANGES FOR SALEM UNIT NO. 1 On February 5, 1979, we met with representatives of Public Service Electric and Gas Company {P~E&G) to discuss proposed Technical Specifi-cation changes for Salem Unit No. 1 regarding moderator temperature coefficient and rod position indication requirements A list of attendees is enclosed.
Significant discussions are summarized below.
Moderator Temperature Coefficient The licensee provided the basis for its June 29, 1978 Tech Spec change proposal for Section 3.1.1.4 involving the moderator temperature coeffictent {_MTC} limiting condition for operation for Salem Unit No. 1.
We indicated that the Action Statements for those situations when the MTC may be positive, should specifically include the requirement to establish and maintain the reactor coolant system boron concentration within limits sufficient to restore the MTC to an acceptable value.
Al so, to clarify the intent of the ACTION statement.s, we proposed to indicate that operation in MODES 1 and 2 may procee~ with a positive MTC provided the ACTION statements are being observed./ The licensee agreed t6 consider these changes to their original proposal.
Rod Position Indication The licensee indicated that the center control rod {2D5), rod position indicator channel at Salem Unit No. 1 had a degraded signal and there-fore had been declared "inoperable" and that ACTION statements of Section 3.1.3.2 were being observed to allow continued reactor operation.
In the event of a reactor scram, however, reactor startup would not be
- r
'\\
Meeting Summary for Public $ervtce Electric & Gas
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March 26, 1979 possible because of Tech Spec Section 3,0.4 which does not allow entry i'nto an OPERATIONAL MODE while under an ACTION statement.
The 1 icensee therefore requested, in its letter of January 22, 1979, that reltef from Section 3.0.4 be granted to allow a reactor startup following a scram at least until March 31, 1979 at which time Salem Unit No. l is expected to commence a refueling outage and the cause of the degraded signal to that control rod indicator channel could be corrected and the channel returned to within specifications.
The basis for this request is contained in the January 22, 1979 letter.
We advised the licensee that because of manpower limitations we could not justify a revi'ew of the l icensee>s request for a Tech Spec change that may not be needed,. We did indicate, however, that should a scram occur, we would expedite our review to determine the acceptability of the Hcensee's request, To assist us in this possible review, the licensee agreed to provid~ additional tnformation in the form of in-core flux maps that have been taken at Salem Unit No. l as required by the ACTION statements.
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Enclosure:
Attendance List Gary G. Zech, Project Manager Operating Reactors Branch #1 Division of Operating Reactors
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- ENCLOSURE l.
NRC STAFF MEETING WITH PUBLIC SERVICE ELECTRIC & GAS CO. (PSE&G)
February 5, 1979 NRC
~G. Zech P. Wagner H. Richings M: Dunenfeld D. C. Kirkpatrick J. Rosen th a 1 J. T. Beard List of Attendees PSE&G E. Rosenfeld J. Nichols