ML18054A411
| 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: |
| 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.
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 2
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
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 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 4
- 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