ML18054A411

Forwards Corrected Tech Spec Pages 3-6 & 3-8 & Change to Ref 5 on Page 4 of Request for Change Section of Application to Amend License DPR-20 Re Low Temp Overpressure Protection

ML18054A411
Person / Time
Site:	Palisades
Issue date:	11/01/1988
From:	Smedley R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18054A412	List: ML18054A411 ML18054A414
References
NUDOCS 8811080317
Download: ML18054A411 (4)

Text

• consumers Power POWERINli MICHlliAN'S PROliRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 November 1, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

TECHNICAL SPECIFICATIONS CHANGE REQUEST - LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) - ADDITIONAL INFORMATION Consumers Power Company letter dated April 12, 1988 requested a Technical Specification Change for LTOP. With reference to that letter, this letter transmits two corrected proposed page changes (pages 3-6 and 3-8) and changes Reference 5 on page 4 of the Request for Change section.

Proposed page 3-6 change is necessary because the addition of verbiage to page 3-4 caused an overflow onto pages 3-5 and 3-6. A changed page 3-5 was included in our April 12, 1988 letter, a changed page 3-6 was inadvertently omitted.

The change to Reference 5 on page 4 of the Request for Change is necessary because further review of Reference 5, EA-RBJ-RWS, "Palisades Reactor Pressure Vessel Temperature Limits Determination", resulted in the analysis being conducted again. The resulting pressure/temperature limits from the re-analysis remain the same as transmitted in our April 12, 1988 letter, but the re-analysis incorporates additional written information for clarity and is re-identified as EA-ESSR 88727-C/S-Ol. Hence, Reference 5 on page 4 of the Request for Change should read:

5. EA-ESSR 88727-C/S-01 "Palisades Plant Primary Coolant System Pressure Temperature Limits Per Appendix G of the ASME Boiler and Pressure Vessel Code" Revision O.

OC1088-0182-NL02

Nuclear Regulatory Commission Patisades Nuclear Plant

• TSCR - LTOP - Additional Info.

• 2 Draft Reference to the pressure/temperature analysis was omitted from Page 3-8.

Therefore, a new proposed page 3-8 with EA-ESSR 8827-C/S-01 added as Reference 17 is being provided.

~~

Richard W Smedley ~ ~

Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC1088-0182-NL02

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 CORRECTED PAGE CHANGES FOR INCLUSION IN THE APRIL 12, 1988 LTOP TECHNICAL SPECIFICATION PROPOSAL November 1, 1988 3 Pages OC1088-0182-:NL02

The proposed changes in Sections 4.1.lc, 4.6.lb and in the basis for Section 4.6 align the Surveillance Requirements with the proposed 4

Limiting Conditions for Operation.

Therefore, through a combination of PORV setpoints, equipment operability requirements, and restrictions on the primary/secondary temperature relationship when initiating forced circulation in the PCS, the proposed Technical Specifications prevent the pressure limits of the 10CFR50 Appendix G curves from being exceeded.

References

1. EA-PAL-85-101 "Calculation of PCS Pressure Increase From Adding I 133 gpm (3 charging pumps) Before the PORVs Open," November 4, 1987. I I

2. EA-PAL-LTOP-880119 "Calculation of Required PORV Capacity to maintain I the PCS Below Appendix G", January 20, 1988. I I

3. EA-PAL-LTOP-880120 Rev A - "PORV Flow Capacity at Expected LTOP /

Conditions" February 15, 1988. I I

4. EA-~AL-LTOP-880121 - "Calculation of Time for Operator to Act for I HPSI and Bubble" January 20, 1988. I I

5. EA-ESSR 88727-C/S-01 "Palisades Plant Primary Coolant System Pressure I Temperature Limits Per Appendix G of the ASME Boiler and Pressure /

Vessel Code" Revision 0. I III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this change request involve no significant hazards, and, accordingly, a no significant hazards determination per 10CFR50.92(c) is justified. The following evaluation supports that finding.

Evaluation

1. Involve a significant increase in the probability or consequences an accident previously evaluated LTOP prevents the PCS pressure from exceeding 10CFR50. Appendix G pressure/temperature limits. Three recognized conditions could cause those limits to be exceeded. Two involve mass additions i.e.,

an inadvertent HPSI pump start and/or a charging/letdown imbalance.

The third involves an energy addition - i.e., the initiation of forced PCS circulation when the steam generator temperature is greater than the PCS temperature.

This proposed Technical Specification change prevents those conditions from causing Appendix G limits to be exceeded by:

OC1088-0182-NL02