ML20135D650

Provides Clarification to 961025 Request for Improvement to TS Section 3.1.3.5,control Rod Scram Accumulators

ML20135D650
Person / Time
Site:	Hope Creek
Issue date:	12/04/1996
From:	Dawn Powell Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20135D652	List: ML20135D650 ML20135D685
References
RTR-NUREG-1433 LCR-H96-08, LCR-H96-8, LR-N96384, NUDOCS 9612100076
Download: ML20135D650 (6)

Text

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(ll> IP'!sil?D(Ji Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DEC 041996 LR-N96384 LCR H96-08 United States Nuclear Regulatory Commission l

Document Control Desk Washington, DC 20555 STATEMENT OF CIARIFICATION TO INITIAL REQUEST OF OCTOBER 25, 1996 FOR IMPROVEMENT TO TECHNICAL SPECIFICATION SECTION i 3.1.3.5, CONTROL ROD SCRAM ACCUMULATORS HOPE CF.EEK GENERATING STATION FACILITY OPERATING LICENSES NPF-57 DOCKET No. 50-354 Gent)" 'n: I As ch ;ussed on November 26, 1996 between J. Keenan, PSE&G Licensing, and D. Jaffe, NRC Hop 2 Creek Project Manager, PSE&G provides the following clarification of Attachment 1, page 5 of 7 of our submittal dated October 25, 1996 (LR-N96203). Please delete the words "ecram accumulators" and change " rod" to " rods" in paragraph 3 as shown in attachment A to this letter. This change provides consistency with  ;

Technical Specification pages as provided and shown in '

Attachnent B and is consistent with improved Standard Technical Specifications, NUREG-1433, Revision 1. 'te . l revised page with the deletion is provided as Attachment C. l l

This clarification only modifies the background section of ,

the correspondence. Accordingly, the significant hazards  !

analysis and Technical Specification pages are unaltered by this clarification. Further, there is no change to the technical content of this correspondence. The 10 CFR 50.92 and the revised Technical Specification pages, which remain in there original form, were considered and reviewed as originally proposed and are in agreement with the improved Standard Technical Specifications.

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1 9612100076 961204 0 PDR ADOCK 05000354 /

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' Document Control Desk LR-N96384 l

1 Should you have any questions regarding this change, we will l be pleased to discuss them with you. l l

l Sincerely, ii

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kN k' wh David R. Powell Manager - Nuclear Licensing J

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i Attachments (3)

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C Mr. H. Miller, Administrator - Region I l U. S. Nuclear Regulatory Commission .

475 Allendale Road l King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 l Rockville, MD 20852 Mr. R. Summers (X24)

USNRC Senior Resident Inspector - Hope Creek Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 l

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l Document Control Desk LR-M96206 ,

Attachment 1 LCR H96-08

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With the reactor pressure < 900 psig, the function of the accumulators in providing the scram force becomes much more  ;

important since the scram function could become degraded during a '

depressurization event or at low reactor pressures. Therefore, immediately upon discovery of charging water pressure < 940 psig, -

concurrent with one or more inoperable control rod scram accumulators, and reactor pressure < 900 psig, all control rods associated with inoperable accumulators must be verified to be l fully inserted. The associated control rods must also be l l declared inoperable within one hour. As stated in the improved i Technical Specification allowed completion time of one hour is reasonable considering the low probability of a DBA or transient .

occurring during the time that the accumulator is inoperable.  ;

l l The proposed changes also state that the reactor mode switch must  !

be immediately placed in the shutdown position if either required  ;

action and associated completion time associated with loss of the ,

CRD charging pump cannot be met. This ensures that all insertable control rods are inserted and that the reactor is in a condition that does not require the active function (i.e. scram) ,

of the control rods. This required action is modified by a note .

stating that the action is not applicable provided all control rods associated with the inoperable scram accumulators are fully inserted, since the safety function of the control rod (s) has l been performed.

l The proposed Technical Specifications will also be revised to state that, during OPCON 5 with an accumulator associated with a withdrawn control rod inoperable, the control rod is required to >

be inserted.

"In OPERATIONAL CONDITION 5*:

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1) With one or more control rod;ccr;: ;;;umulat;;; R DELCTE l inoperable, upon discovery immediately initiate action to i fully insert inoperable withdrawn control rods."

Once the control rod is fully inserted, the accumulator is no longer required to be operable (as indicated in a footnote in the l- current Technical Specifications) and the entry conditions for l the required actions are no longer applicable, thus no additional l actions are required (this is consistent with LCO 3.0.2).

Therefore, the action to disarm the associated directional control valves is proposed for deletion.

Multiple control rods withdrawn with the vessel head removed (OPCON 5) while fuel remains in its cell is only accomplished in accordance with Technical Specification section 3.10.3. In the event multiple withdrawn control rods have inoperable accumulators and no CRD pump operating, the actions of LCO 3.10.7

will direct the immediate scram. Actions for single or multiple withdrawn control rods with inoperable accumulators, and CRD pump i

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