ML18051A542

Requests Extension of One Operating Cycle Beyond Present Commitment of 1985 Refueling Outage to Make Mods Per SEP Topic XV-2, Spectrum of Steam Piping Failures Inside & Outside Containment (Pwr).

ML18051A542
Person / Time
Site:	Palisades
Issue date:	08/15/1983
From:	TONER K A CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	CRUTCHFIELD D Office of Nuclear Reactor Regulation
Shared Package
ML18051A543	List: ML18051A542 ML18051A544 ML18051A545 ML18051A546 ML18051A547 ML18051A549 ML18051A550 ML18051A551 ML18051A552
References
TASK-15-02, TASK-15-2, TASK-RR NUDOCS 8308230375
Download: ML18051A542 (4)

Text

( **' consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 August 15, 1983 Dennis M Crutchfield, Chief Operating Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -SEP TOPIC XV-2 "SPECTRUM OF STEAM PIPING FAILURES INSIDE AND OUTSIDE CONTAINMENT (PWR)" -REQUEST FOR TIME EXTENSION TO RESOLVE CONCERN OF TWO STEAM GENERATOR BLOWDOWNS INSIDE CONTAINMENT During a review of SEP Topic "Spectrum of Steam Piping Failures Inside and Outside Containment (PWR)," the NRC Staff became concerned that removal of core decay heat would become unreliable in the event of a main steam line break (MSLB) inside containment and a concurrent failure to close of the main steam isolation valve (MSIV) in the intact main steam (MS) line. As mented in NUREG-0820 "Integrated Plant Safety Assessment, Palisades Plant" dated October 1982, the NRC indicated that such an event would result in unreliable decay heat removal due to the blowdown of both steam generators.

In response to the Staff's concern, Consumers Power Company committed to performing appropriate modifications to make the MSIV/MS configuration failure proof with respect to the blowdown event. The commitment, which is also documented in NUREG-0820, presently requires that the modifications be completed.

by the end of the 1985 refueling outage. The purposes of this submittal are to: 1) request a time extension of one operating cycle beyond the present commitment in which to make the modifications and 2) provide the NRC with a basis for such a request. Consumers Power Company is presently on schedule in its efforts to resolve the NRC concern via MSIV replacement by the end of the 1985 outage. We have completed a study which shows the feasibility of replacing the two existing MSIVs with new valves capable of closing under conditions of flow in either direction thereby eliminating the single-failure potential.

In addition, we have begun preparing valve procurement specifications which will be completed and forwarded to prospective manufacturers on or about September 1, 1983. 8308230375 830815 PDR ADOCIA. 05000255 P PDR OC0883-0010A-NL02 DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983 2 Recently, however, we have completed a preliminary probabilistic risk ment (PRA) and cost/benefit (C/B) analysis which reveals the need to: a) further evaluate the safety significance of this event given the reliability of existing systems to prevent inadequate core cooling during and after the event and b) should plant modification prove necessary, determine the most cost-effective modification which resolves the concern. The preliminary PRA and C/B analysis (Enclosure

1) shows that the_§requency of a significant release resulting from this event is 9.8 x 10 occurrences/year and that the present cgurse of action (ie, MSIV replacement) results in a C/B ratio of $6.1 x 10 /manrem; an expenditure considerably in excess of the NRC safety goal guideline of $1000/manrem.

Consumers Power Company met with the Staff in Bethesda on July 26, 1983 to present the results of the preliminary PRA and C/B analysis and to request that the NRC review the results and grant Consumers Power Company a time extension of one operating cycle beyond our current commitment for any sary plant modification.

This time extension, if approved, would result in: 1) Consumers Power Company finalizing its PRA and C/B analysis to determine more accurately the safety significance of this event as well as the most co'st-effective modification (if modification is proven necessary) and ting such analysis by September 1, 1984 and 2) completing any required modifications by the end of the 1986 refueling outage. During the July 26, 1983 meeting, the Staff indicated that it would consider our request and would attempt to pass judgment on the request by Septem-ber 1, 1983. However, the Staff requested that Consumers Power Company provide in this submittal certain evaluation regarding plant response during and after the event. The NRC indicated that such evaluation would assist the Staff in its consideration of the request. Specifically, the Staff requested that we provide the following:

1) an evaluation of the adequacy of existing operating procedures to guide operator response for this event and 2) an evaluation as to whether adequate heat removal through a dried-out steam generator is possible given the presence of a heat transfer barrier lished by the steam that is created by the incoming auxiliary feedwater as it comes into contact with the high temperature steam generator internals.

Enclosures 2 and 3 provide our response to the requests.

Enclosure 2 cates that the immediate actions prescribed in our MSLB procedures are proper for the two steam generator blowdown event. Enclosure 3 (item 3) indicates that "steam blanketing" is not likely to be a problem given the design of the steam generator, the effectiveness of the internal separators and dryers and the low velocities of the steam which is developed by boiling of the incoming auxiliary feedwater.

OC0883-0010A-NL02

-* DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983

• 3 Additional evaluations were requested by the Staff during an August 2, 1983 telephone conference call. These requests are itemized below. It should be noted that Enclosure 3 also responds in part to requests number 1 and 2a. Consumers Power Company will provide a detailed response to each NRC request as part of our final PRA and C/B analysis to be submitted by September 1, 1984. Additional NRC Requests 1. Evaluate the thermal-hydraulic response of the steam generator secondary side during and after the two steam generator blowdown event. 2a. Determine the number of cooldown cycles that would cause the steam generator vessel, tubes or tube sheet to fail. 2b. Determine the number of cooldown cycles that would occur during-and after the event. 3. Should it be determined that tube failure will occur, evaluate the impact on containment failure and include in the evaluation a description of the model utilized to analyze the consequences.

4. Determine the likelihood of a MSLB outside of containment and depending on the probability of such an event: a) evaluate the means by which long term cooling (LTC) would be accomplished taking into account that the spilled coolant would not be filling the sump to provide a LTC supply of water and b) provide a description of the model utilized to analyze the consequences.

5. Evaluate the effect of various MSLB sizes on the plant response.

6. Evaluate the means by which the operator would prevent excessive cooldown that could pull a void on the primary system; especially if there exists a LOCA through the steam generators.

In conclusion, this submittal represents Consumers Power Company's formal request to change its scheduled date for completing plant modifications to make the MSIV/MS configuration single-failure proof to prior to startup from the 1986 refueling outage. It is the opinion of Consumers Power Company, based on the evaluations to date of the event, that the health and safety of the public will not be jeopardized by this delay. OC0883-0010A-NL02 l' DMCrutchfield, Chief Palisades Plant SEP TOPIC XV-2 August 15, 1983 4 Consumers Power Company also requests that the NRC pass judgment on the request for time extension and notify us of the decision by September 1, 1983 so that our efforts to procure replacement valves and meet our present ment dates for installation are not constrained.

Should our request for time extension be approved, we will submit the final PRA and C/B analysis by September 1, 1984 and will complete any required modification during the 1986 refueling outage. Should our request be denied, we will proceed with our efforts to replace the existing MSIVs on a schedule consistent with our current commitment.

Kerry A Toner Senior Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector

-Palisades Enclosures OC0883-0010A-NL02