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Sei;vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 1 *, I Nuclear Business Unit JUN 1 7 .1998 LR-N980227 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
* P~blic Sei;vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 1   *,   I Nuclear Business Unit JUN 1 7 .1998 LR- N980227 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
TECHNICAL SPECIFICATION BASES CHANGES SALEM GENERA TING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 Public Service Electric and Gas Company (PSE&G) is providing revised Technical Specification (TS) Bases pages for several Unit 1 and Unit 2 Technical Specifications.
TECHNICAL SPECIFICATION BASES CHANGES SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 Public Service Electric and Gas Company (PSE&G) is providing revised Technical Specification (TS) Bases pages for several Unit 1 and Unit 2 Technical Specifications.
These include: (1) 3/4.1.3 "Movable Control Assemblies." (page B 3/4 1-5 Unit 1 only); (2) 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank", both dealing with containment sump pH (Unit 1 pages 8 3/4 1-4 and 8 3/4 5-3, and Unit 2 pages B 3/4 1-4 and B 3/4 5-3); and (3) 3/4.9.1 "Boron Concentration" (Unit 1 page B 3/4 9-1 and Unit 2 page B 3/4 9-1). The revised Bases pages were reviewed through the 1 OCFR50.59 process by the Station Operations Review Committee and approved by the General Manager -Salem Operations.
These include: (1) 3/4.1.3 "Movable Control Assemblies." (page B 3/4 1-5 Unit 1 only);
The Bases for Technical Specification 3/4.1.3 (B3/4.1.3):
(2) 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank", both dealing with containment sump pH (Unit 1 pages 8 3/4 1-4 and 8 3/4 5-3, and Unit 2 pages B 3/4 1-4 and B 3/4 5-3); and (3) 3/4.9.1 "Boron Concentration" (Unit 1 page B 3/4 9-1 and Unit 2 page B 3/4 9-1). The revised Bases pages were reviewed through the 10CFR50.59 process by the Station Operations Review Committee and approved by the General Manager - Salem Operations.
(1) ensure acceptable power distribution limits are maintained (2) ensure the minimum shutdown margin is maintained, and (3) limit the potential effects of rod misalignment on accident analysis.
The Bases for Technical Specification 3/4.1.3 (B3/4.1.3): (1) ensure acceptable power distribution limits are maintained (2) ensure the minimum shutdown margin is maintained, and (3) limit the potential effects of rod misalignment on associ~ted accident analysis. Incorporating the P-250 as an alternate method of determining rod position has been determined to be acceptable, based in part on: (1) the Technical Specification* Limiting Condition for Operation not describing any specific instrument to determine rod position, (2) the power supplies for both, the control console indication and the P-250 being supplied with reliable battery backed power supplies, and (3) the accuracy of the P-250 being equal or better than the control console indication.
Incorporating the P-250 as an alternate method of determining rod position has been determined to be acceptable, based in part on: (1) the Technical Specification*
The Bases for Technical Specifications 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank" were revised to provide operational flexibility (i.e. by reducing the amount of sodium hydroxide or other pH controller required to adjust post-LOCA containment sump pH, particularly for a small break LOCA) and to make the Bases for the Technical Specifications consistent with the UFSAR.
Limiting Condition for Operation not describing any specific instrument to determine rod position, (2) the power supplies for both, the control console indication and the P-250 being supplied with reliable battery backed power supplies, and (3) the accuracy of the P-250 being equal or better than the control console indication.
The Bases for Technical Specification 3/4.9.1 were revised to provide a clarifying statement to indicate that when satisfying LCO 3.9. t, "Boron Concentration," sampling
The Bases for Technical Specifications 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank" were revised to provide operational flexibility (i.e. by reducing the amount of sodium hydroxide or other pH controller required to adjust LOCA containment sump pH, particularly for a small break LOCA) and to make the Bases for the Technical Specifications consistent with the UFSAR. The Bases for Technical Specification 3/4.9.1 were revised to provide a clarifying statement to indicate that when satisfying LCO 3.9. t, "Boron Concentration," sampling  
                      ---~--  - - - - -------- -- ~---
--------------9806230180 980617 PDR ADOCK 05000272 P PDR The power is in your hands. 95-2168 REV. 6/94 De:>cument Control Desk
9806230180 980617 PDR ADOCK 05000272 P                         PDR The power is in your hands.
* LR-N980227 2 J. 7 1998 and analysis of the refueling canal is required regardless of the amount of water in the refyelinf?,
95-2168 REV. 6/94
PSE&G previously committed to revise this Bases section as a corrective action in response to an NRC Violation (LR-N96331 Response to Notice of Violation Inspection Report 50-272/96-12 and 50-311/96-12, dated October 23, 1996) and in LER 311/96-011-00 (LR-N96320) dated October 18, 1996. This action was originally committed to be completed by March 31, 1997. It was completed on April 29, 1998. The commitment was extended internally to PSE&G, however the need to provide timely notification of the schedule change to the NRC was not recognized.
 
All the other corrective actions stated in the violation response and the LER were completed by their commitment dates. These included revision of the procedures, which control associated plant activities.
De:>cument Control Desk
* LR-N980227                                 2 J. 7 1998 and analysis of the refueling canal is required regardless of the amount of water in the refyelinf?, ~anal. PSE&G previously committed to revise this Bases section as a corrective action in response to an NRC Violation (LR-N96331 Response to Notice of Violation Inspection Report 50-272/96-12 and 50-311/96-12, dated October 23, 1996) and in LER 311/96-011-00 (LR-N96320) dated October 18, 1996. This action was originally committed to be completed by March 31, 1997. It was completed on April 29, 1998. The commitment was extended internally to PSE&G, however the need to provide timely notification of the schedule change to the NRC was not recognized. All the other corrective actions stated in the violation response and the LER were completed by their commitment dates. These included revision of the procedures, which control associated plant activities.
The attachment to this letter contains the revised pages for Salem Unit Nos. 1 and 2 Technical Specification Bases. Please incorporate these changes into the Technical Specifications.
The attachment to this letter contains the revised pages for Salem Unit Nos. 1 and 2 Technical Specification Bases. Please incorporate these changes into the Technical Specifications.
Should there be any questions with regard to this submittal, please do not hesitate to contact us. Attachment Sincerely, D.R. Powell Director Licensing  
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
& Regulation/Fuels Document Control Desk
Sincerely, D.R. Powell Director Licensing & Regulation/Fuels Attachment
* LR-N980227 3 C Mr. H.J. Miller, Administrator-Region I lJ., S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. Scott Morris (X24) USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 e .. JUN 17'1998}}
 
Document Control Desk
* LR-N980227                             3 e        .
JUN 17'1998 C     Mr. H.J. Miller, Administrator- Region I lJ., S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. Scott Morris (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625}}

Latest revision as of 16:23, 7 November 2019

Forwards Revised TS Bases Pages for Sections 3/4.1.3, 3/4.1.2,3/4.5.5 & 3/4.9.1.Revised Bases Pages Were Reviewed Through 10CFR50.59 Process by Station Operations Review Committee & Approved by General Manager-Station Operations
ML18106A660
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/17/1998
From: Dawn Powell
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18106A662 List:
References
LR-N980227, NUDOCS 9806230180
Download: ML18106A660 (3)
v • d • e


Text

PS~G

  • P~blic Sei;vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 1 *, I Nuclear Business Unit JUN 1 7 .1998 LR- N980227 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

TECHNICAL SPECIFICATION BASES CHANGES SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 Public Service Electric and Gas Company (PSE&G) is providing revised Technical Specification (TS) Bases pages for several Unit 1 and Unit 2 Technical Specifications.

These include: (1) 3/4.1.3 "Movable Control Assemblies." (page B 3/4 1-5 Unit 1 only);

(2) 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank", both dealing with containment sump pH (Unit 1 pages 8 3/4 1-4 and 8 3/4 5-3, and Unit 2 pages B 3/4 1-4 and B 3/4 5-3); and (3) 3/4.9.1 "Boron Concentration" (Unit 1 page B 3/4 9-1 and Unit 2 page B 3/4 9-1). The revised Bases pages were reviewed through the 10CFR50.59 process by the Station Operations Review Committee and approved by the General Manager - Salem Operations.

The Bases for Technical Specification 3/4.1.3 (B3/4.1.3): (1) ensure acceptable power distribution limits are maintained (2) ensure the minimum shutdown margin is maintained, and (3) limit the potential effects of rod misalignment on associ~ted accident analysis. Incorporating the P-250 as an alternate method of determining rod position has been determined to be acceptable, based in part on: (1) the Technical Specification* Limiting Condition for Operation not describing any specific instrument to determine rod position, (2) the power supplies for both, the control console indication and the P-250 being supplied with reliable battery backed power supplies, and (3) the accuracy of the P-250 being equal or better than the control console indication.

The Bases for Technical Specifications 3/4.1.2 "Boration Systems" and 3/4.5.5 "Refueling Water Storage Tank" were revised to provide operational flexibility (i.e. by reducing the amount of sodium hydroxide or other pH controller required to adjust post-LOCA containment sump pH, particularly for a small break LOCA) and to make the Bases for the Technical Specifications consistent with the UFSAR.

The Bases for Technical Specification 3/4.9.1 were revised to provide a clarifying statement to indicate that when satisfying LCO 3.9. t, "Boron Concentration," sampling

---~-- - - - - -------- -- ~---

9806230180 980617 PDR ADOCK 05000272 P PDR The power is in your hands.

95-2168 REV. 6/94

De:>cument Control Desk

  • LR-N980227 2 J. 7 1998 and analysis of the refueling canal is required regardless of the amount of water in the refyelinf?, ~anal. PSE&G previously committed to revise this Bases section as a corrective action in response to an NRC Violation (LR-N96331 Response to Notice of Violation Inspection Report 50-272/96-12 and 50-311/96-12, dated October 23, 1996) and in LER 311/96-011-00 (LR-N96320) dated October 18, 1996. This action was originally committed to be completed by March 31, 1997. It was completed on April 29, 1998. The commitment was extended internally to PSE&G, however the need to provide timely notification of the schedule change to the NRC was not recognized. All the other corrective actions stated in the violation response and the LER were completed by their commitment dates. These included revision of the procedures, which control associated plant activities.

The attachment to this letter contains the revised pages for Salem Unit Nos. 1 and 2 Technical Specification Bases. Please incorporate these changes into the Technical Specifications.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

Sincerely, D.R. Powell Director Licensing & Regulation/Fuels Attachment

Document Control Desk

  • LR-N980227 3 e .

JUN 17'1998 C Mr. H.J. Miller, Administrator- Region I lJ., S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. Scott Morris (X24)

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

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