ML18102A197

Application for Amends to Licenses DPR-70 & DPR-75,adding Design Parameters for MSLB

ML18102A197
Person / Time
Site:	Salem
Issue date:	06/18/1996
From:	STORZ L F Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18102A198	List: ML18102A197 ML18102A199
References
LCR-S96-06, LCR-S96-6, LR-N96126, NUDOCS 9606250316
Download: ML18102A197 (8)

Text

Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President

-Nuclear Operations JUN 1 8 1996 LR-N96126 LCR S96-06 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT DESIGN TEMPERATURE SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:

In accordance with 10CFR50.90, Public Service Electric & Gas (PSE&G) Company hereby requests a revision to the Technical Specifications (TS) for the Salem Generating Station Unit Nos. 1 and 2. In accordance with 10CFR50.91 (b) (1), a copy of this submittal has been sent to the State of New Jersey. The proposed TS changes contained herein represent changes to Specification 5.2.2 "Design Pressure and Temperature." These changes will add the design parameters for Main Steam Line Break (MSLB) . PSE&G requests these changes to provide clarification since the MSLB analysis results in a higher containment air temperature than the current value in Specification 5.2.2. This submittal satisfies a commitment made in Supplement 1 of Licensee Event Report 272/95-016-01, (ref LR-N96080) . The proposed changes have been evaluated in accordance with 10CFR50.91(a)

(1), using the criteria in 10CFR50.92(c) and PSE&G has concluded that this request involves no significant hazards considerations.

The basis for the requested change is provided in Attachment

1. A 10CFR50.92 evaluation with a determination of no significant hazards consideration is provided in Attachment

2. The marked up Technical Specification pages affected by the proposed changes are provided in Attachment

3. --96062503i6-96061-a PDR ADOCK 05000272 P PDR 11.\. Printed on Recycled Paper f\UD\ I l

• Document Control Desk LR-N96126 JUN 181996 In Supplement 1 of LER 95-016, PSE&G committed to implementing this License Change Request prior to entry into Mode 4. In order to support the current startup schedule for Unit 2, PSE&G requests approval of the amendment no later than July 29, 1996. PSE&G is requesting a 3 day implementation period after amendment approval.

Should you have any questions regarding this request, we will be pleased to discuss them with you. Affidavit Attachments (3) Sincerely, C Mr. T. T. Martin, Administrator

-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24) USNRC Senior Resident Inspector

-Salem Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625

• STATE OF NEW JERSEY COUNTY OF SALEM SS. REF: LR-N96126 LCR S96-06 L. F. Storz, being duly sworn according to law deposes and says: I am Senior President

-Nuclear Operations of Public Service Electric and Gas Company, and as suGh, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief. Subscribed and Sw before me this / f*f'/\. -+--¥.£..><-L..=__,,_=-

' 1996 My Commission expires on KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission Expires April 21, 1998

• DoGument Control Desk LR-N96126 LCR S96-06 Attachment 1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS (TS) CONTAINMENT DESIGN TEMPERATURE BASIS FOR REQUESTED CHANGE REQUESTED CHANGE AND PURPOSE The proposed change will add the design temperature for Main Steam Line Break (MSLB) which is higher than the value currently specified in the Technical Specifications (TS) . PSE&G requests these changes because the MSLB analysis documented a resulting containment air temperature of 35l.3°F. The current value for containment air temperature in Specification

5.2.2 reflects

the Design Basis Loss of Coolant Accident (LOCA) value of 271°F. In order to reflect both LOCA and MSLB, the governing value for MSLB temperature is being added to TS 5.2.2. The containment concrete structural loading for MSLB temperatures and pressures is enveloped by the Design Basis LOCA temperature and pressures already in the TS. The pressure retaining capability of the liner is governed by the loads generated in the MSLB, and should be identified as such in the TS. However, since there is no impact on the liner pressure integrity during the MSLB this change is not considered safety significant.

BACKGROUND On July 20, 1995, a discrepancy was identified between the peak containment temperature in the licensing basis MSLB and the maximum containment air temperature specified in TS 5.2.2. One of the corrective actions identified in the supplement to the resulting Licensee Event Report (LER) 272/95-016 was to process a License Change Request (LCR) to correct the discrepancy.

The proposed change will satisfy the specified corrective action. JUSTIFICATION OF REQUESTED CHANGES The ability of the containment structure to withstand postulated accidents has been part of the NRC's original design criteria and analysis for Salem since the time of its licensing.

The original Salem Final Safety Analysis Report (FSAR), Section 14.3.4 discussed the containment integrity evaluation.

The text specifically identified the Loss of Coolant Accident (LOCA) to provide bounding conditions for containment design (consistent Page 1 of 3 Document Control 1sk Attachment 1 LR-N96126 LCR S96-06 with Design Criteria 50). It concluded that the integrity of the containment is sufficiently protected if the LOCA peak containment pressure remained below design pressure.

It also concluded that there would be no yielding of the containment liner plate at the design pressure of 47 psig. Temperature was not mentioned in the evaluation and no results from the MSLB were identified in this analysis.

Supplement 4 to the Salem Safety Evaluation Report, Section 6.2.1 discussed the NRC's review of the containment functional design. In this section, a discussion of the MSLB stated that the limiting containment temperature response produced a peak calculated temperature of 350°F. Specifically, the staff stated: "The results of our analysis confirm the applicant's peak calculated temperature of 350 degrees Fahrenheit.

Furthermore, the containment atmosphere temperature will remain above 300 degrees Fahrenheit for approximately three minutes. Therefore, we have determined that a temperature profile which remains above 300 degrees Fahrenheit for three minutes and at 350 degrees Fahrenheit for at least one minute is acceptable for use in equipment qualification for the Salem Unit 2 plant." "Based on our review of the applicants' main steam line break analysis and on our confirmatory analysis, we find the applicants' analysis to be acceptable." The impact of an approximately one degree increase (350°F to 351.3°F) in the calculated maximum temperature during a MSLB is not considered to have a significant impact on equipment qualification.

The impact of the elevated temperature on the liner plate from the MSLB was not addressed.

Analyses results indicated that no yielding of the liner plate would occur during the MSLB scenario at the resulting pressure of 35 psig. However more recent calculations have concluded that a maximum temperature of 351.3°F concurrent with a pressure of 25 psig could exist following a MSLB. With the lower pressure and elevated temperature, some yielding of the liner plate is postulated to occur around the 120 foot elevation.

Although liner plate yielding is postulated to occur, the loading is transferred to the containment concrete structure and therefore, does not affect the containment's ability to limit leakage to values assumed in the Accident Analysis.

• Detailed structural analysis described in Supplement 1 of Licensee Event Report 272/95-016 shows that the Design Basis LOCA combination of pressure and temperature result in more severe loading for the containment concrete structure and, therefore, Page 2 of 3 Document Control 1sk Attachment 1 LR-N96126 LCR S96-06 bounds the temperature and pressure scenario associated with a MSLB accident.

The pressure retaining capability of the liner is governed by the loads generated in the MSLB. For either scenario, the structural integrity of the containment is maintained consistent with Criteria 51. Therefore the proposed change is not considered safety significant.

CONCLUSIONS The proposed change to add the calculated MSLB temperature to the containment design data in the TS will ensure consistency with the UFSAR. The containment concrete structural loading for MSLB temperatures and pressures is enveloped by the Design Basis LOCA temperature and pressures already in the TS. The pressure retaining capability of the liner is governed by the loads ' generated in the MSLB. However, since there is no impact on the liner integrity during the MSLB this change is not considered safety significant.

PSE&G requests these changes because the MSLB analysis documented a resulting containment air temperature in excess of the current value in Specification 5.2.2. This submittal satisfies a commitment made in Supplement 1 of LER 272/95-016.

Page 3 of 3 Document Control 1sk Attachment 2 LR-N96126 LCR S96-06 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT DESIGN TEMPERATURE 10CFR50.92 EVALUATION Public Service Electric & Gas (PSE&G} has concluded that the proposed changes to the Salem Generating Station Unit Nos. 1 and 2 Technical Specifications (TS} do not involve a significant hazards consideration.

In support of this determination, an' evaluation of each of the three standards set forth in 10CFR50.92 is provided below. REQUESTED CHANGE The proposed change will add the design temperature for Main Steam Line Break (MSLB} which is greater than the currently specified design value. PSE&G requests these changes because the MSLB analysis documented a resulting containment air temperature of 35l.3°F. The current value in Specification 5.2.2 is 271°F. BASIS 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The accidents considered for this change are the Loss of Coolant Accident (LOCA} and the Main Steam Line Break (MSLB}. The proposed change ensures the design limiting containment pressure and temperature data specified in the TS is consistent with the UFSAR. Since no physical changes to the containment are being made there will be no change in the probability of either accident occurring.

Detailed structural analysis presented in Supplement 1 of Licensee Event Report (LER} 272/95-016 shows that the Design Basis LOCA combination of pressure and temperature result in more severe loading for the containment concrete structure and, therefore, bounds the temperature and pressure scenario associated with a MSLB accident.

The pressure retaining capability of the liner is governed by the loads generated in the MSLB. Since containment leakage is maintained within the limits assumed in the Accident Analysis for either scenario there is no change in the consequences of either accident.

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• Document Control Desk Attachment 2 LR-N96126 LCR S96-06 Therefore the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

• 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The changes proposed affect the post-accident condition of the containment, and have no impact on the pre-accident condition.

Since there is no physical change proposed the containment and all systems in the containment will continue to perform as designed.

With no physical changes being proposed and no change to the pre-accident condition of the containment it can be concluded that there will be no change in the probability of a new or different accident being created. Therefore the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. The proposed change does not involve a significant reduction in a margin of safety. Although calculations indicate that some yielding of the liner plate could occur during a MSLB, loading is transferred to the containment concrete structure and leakage from the containment is maintained within the limits assumed in the Accident Analysis.

Since containment leakage is maintained within the limits assumed in the Accident Analysis the proposed change does not involve a significant change the margin of safety provided by the containment for the MSLB. CONCLUSION Based on the above, PSE&G has determined that the proposed changes do not involve a significant hazards consideration.

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