ML18101A593: Difference between revisions

From kanterella
Jump to navigation Jump to search
Created page by program invented by StriderTol
Created page by program invented by StriderTol
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:*  
{{#Wiki_filter:~ps~G              **
** Public $ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 151995 LR-N95046 LCR 94-30 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Public $ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 151995 LR-N95046 LCR 94-30 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
ADDITIONAL INFORMATION  
ADDITIONAL INFORMATION - POSITION INDICATION SYSTEMS - OPERATING SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 By letter dated August 1.9, 1994, Public Service Electric & Gas (PSE&G) requested a Technical Specification amendment for Salem Unit Nos. 1 and 2, to add a new action statement to Technical Specifications 3.1.3.2.1, Position Indication Systems -
-POSITION INDICATION SYSTEMS -OPERATING SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 By letter dated August 1.9, 1994, Public Service Electric & Gas (PSE&G) requested a Technical Specification amendment for Salem Unit Nos. 1 and 2, to add a new action statement to Technical Specifications 3.1.3.2.1, Position Indication Systems -Operating for both Salem Units. Based on the review of the amendment request, the NRC staff requested additional information regarding the following two paragraphs of our original submittal. "The proposed change is consistent with NUREG 1431 Vol.1 (Standard Technical Specifications Westinghouse Plants) issued November, 1992.
Operating for both Salem Units. Based on the review of the amendment request, the NRC staff requested additional information regarding the following two paragraphs of our original submittal.
* Since the LCO is only applicable in Modes 1 and 2, :the proposed new action only requires to place the unit;in HOT STANDBY (Mode 3), which is the first operational mode in which the LCO is no longer applicable". "The proposed change is also more conservative than NUREG 1431, which allows for either continued (reduced) power operation with.one or more rod position indication inoperable or up to 4 hours to determine the rod(s) position".
        "The proposed change is consistent with NUREG 1431 Vol.1 (Standard Technical Specifications Westinghouse Plants) issued November, 1992.
Upon further discussion between PSE&G and NRC personnel, it was determined that the*proposed change is consistent with NUREG 1431. Specifically, NUREG 1431 Condition D requires the unit to be placed in Mode 3 (HOT STANDBY), when the Limiting Condition for Operation (LCO) can not be met. This is consistent with PSE&G's request which adds a new (similar) action under the proposed LCO. .fOJ\ I D 95-2168 REV. 6/94
* Since the LCO is only applicable in Modes 1 and 2, :the proposed new action only requires to place the unit;in HOT STANDBY (Mode 3), which is the first operational mode in which the LCO is no longer applicable".
* *** ,.)ii Document'Control Desk LR-N95046
        "The proposed change is also more conservative than NUREG 1431, which allows for either continued (reduced) power operation with.one or more rod position indication inoperable or up to 4 hours to determine the rod(s) position".
* MAR 151995 2 The second paragraph stating that the request is more conservative than the NUREG needs to be deleted. The statement was based on interpreting NUREG 1431 Conditions A and B as two distinctly separateirequirements.
Upon further discussion between PSE&G and NRC personnel, it was determined that the*proposed change is consistent with NUREG 1431. Specifically, NUREG 1431 Condition D requires the unit to be placed in Mode 3 (HOT STANDBY), when the Limiting Condition for Operation (LCO) can not be met. This is consistent with PSE&G's request which adds a new (similar) action under the proposed LCO.
However, after further discussions with our NRC project manager and technical reviewer, it was determined ttiat Conditions A and B can not be read and applied separately.
                                                                                            .fOJ\       I   D 95-2168 REV. 6/94
Condition B must be looked at and applied in conjunction with A, and not as a separate requirement.
 
Therefore, PSE&G would like to withdraw this paragraph from the submittal.
  *** ,.)ii
The original determination of No Significant Hazards Consideration is not affected by this change. Please feel free to contact us if there are any additional questions.
* Document'Control Desk                 2
Sincerely, F. X.
* MAR 151995 LR-N95046 The second paragraph stating that the request is more conservative than the NUREG needs to be deleted. The statement was based on interpreting NUREG 1431 Conditions A and B as two distinctly separateirequirements. However, after further discussions with our NRC project manager and technical reviewer, it was determined ttiat Conditions A and B can not be read and applied separately. Condition B must be looked at and applied in conjunction with Co~dition A, and not as a separate requirement.
* Manager -Licensing  
Therefore, PSE&G would like to withdraw this paragraph from the submittal. The original determination of No Significant Hazards Consideration is not affected by this change.
& Regulations  
Please feel free to contact us if there are any additional questions.
*'* r*' '. c Mr. L. N. Olshan. Licensing Project Manager -Salem U.S. Nuclear Regulatory Commission White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr *. c. S. Marschall (S09) USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator  
Sincerely, P~~1 F. X. Thomson,~
-Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia,:
* Manager -
PA 19406 i I Mr. Kent Tosch, <:Manager, VI New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 ' Trenton, NJ 08625}}
Licensing & Regulations
                        *'*
r*'
                        '.
c     Mr. L. N. Olshan.
Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission On~ White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr *. c. S. Marschall (S09)
USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia,: PA 19406 i
I Mr. Kent Tosch, <:Manager, VI New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415           '
Trenton, NJ 08625}}

Revision as of 09:16, 21 October 2019

Responds to Request for Addl Info Re 940819 TS Amend Request to Add New Action Statement to TS 3.1.3.2.1, Position Indication Sys.
ML18101A593
Person / Time
Site: Salem  
Issue date: 03/15/1995
From: Thomson F
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LCR-94-30, LR-N95046, NUDOCS 9503240026
Download: ML18101A593 (2)


Text

~ps~G **

Public $ervice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 151995 LR-N95046 LCR 94-30 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

ADDITIONAL INFORMATION - POSITION INDICATION SYSTEMS - OPERATING SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 By letter dated August 1.9, 1994, Public Service Electric & Gas (PSE&G) requested a Technical Specification amendment for Salem Unit Nos. 1 and 2, to add a new action statement to Technical Specifications 3.1.3.2.1, Position Indication Systems -

Operating for both Salem Units. Based on the review of the amendment request, the NRC staff requested additional information regarding the following two paragraphs of our original submittal.

"The proposed change is consistent with NUREG 1431 Vol.1 (Standard Technical Specifications Westinghouse Plants) issued November, 1992.

  • Since the LCO is only applicable in Modes 1 and 2, :the proposed new action only requires to place the unit;in HOT STANDBY (Mode 3), which is the first operational mode in which the LCO is no longer applicable".

"The proposed change is also more conservative than NUREG 1431, which allows for either continued (reduced) power operation with.one or more rod position indication inoperable or up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to determine the rod(s) position".

Upon further discussion between PSE&G and NRC personnel, it was determined that the*proposed change is consistent with NUREG 1431. Specifically, NUREG 1431 Condition D requires the unit to be placed in Mode 3 (HOT STANDBY), when the Limiting Condition for Operation (LCO) can not be met. This is consistent with PSE&G's request which adds a new (similar) action under the proposed LCO.

.fOJ\ I D 95-2168 REV. 6/94

      • ,.)ii
  • Document'Control Desk 2
  • MAR 151995 LR-N95046 The second paragraph stating that the request is more conservative than the NUREG needs to be deleted. The statement was based on interpreting NUREG 1431 Conditions A and B as two distinctly separateirequirements. However, after further discussions with our NRC project manager and technical reviewer, it was determined ttiat Conditions A and B can not be read and applied separately. Condition B must be looked at and applied in conjunction with Co~dition A, and not as a separate requirement.

Therefore, PSE&G would like to withdraw this paragraph from the submittal. The original determination of No Significant Hazards Consideration is not affected by this change.

Please feel free to contact us if there are any additional questions.

Sincerely, P~~1 F. X. Thomson,~

  • Manager -

Licensing & Regulations

  • '*

r*'

'.

c Mr. L. N. Olshan.

Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission On~ White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr *. c. S. Marschall (S09)

USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia,: PA 19406 i

I Mr. Kent Tosch, <:Manager, VI New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 '

Trenton, NJ 08625