ML18100B108
| ML18100B108 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/25/1994 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18100B109 | List: |
| References | |
| LCR-94-11, NLR-N94049, NUDOCS 9406030124 | |
| Download: ML18100B108 (7) | |
Text
Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations MAY 2 5 1994 NLR-N94049*
LCR 94-11 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT RADIATION MONITORING INSTRUMENTATION SALEM GENERATING STATIONS UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric & Gas Company (PSE&G) hereby transmits a request. for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station Units Nos. 1 and 2 respectively.
In accordance with 10CFR50.9l(b) (1) requirements, a copy of this request has been sent to the State of New Jersey.
The proposed amendment modifies Tables associated with Technical Specifications 3/4.3.3.1 Radiation Monitoring Instrumentation, 3/4.3.3.8 Radioactive Liquid Effluent Monitoring Instrumentation, and 3/4.3.3.9 Radioactive Gaseous Effluent Monitoring Instrumentation.
The proposed change relocates the Salem specific radiation monitor numbers from the table to a cross reference in the Bases.
No required radiation monitoring functions are being changed.
The proposed change is administrative to allow radiation monitor numbering to be changes without prior NRC approval.
Salem is in the process of upgrading the Radiation Monitoring System.
This upgrade will involve a replacement on many of the existing radiation monitors.
The proposed change to the Technical Specifications will support this* effort. includes a description, justification, and significant hazards analysis for the proposed changes. contains the Technical Specification pages revised with pen and ink changes.
~he revised Bases pages have been included for your information.
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Document Control Desk NLR-N94049 LCR 94-11 2
MAY 2 5 1994 PSE&G is requesting a 60 day implementation period after amendment approval.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
C Mr. J. c. Stone Licensing Project Manager Mr. c. Marschall Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Manager IV New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
Ref:
NLR-N94049 STATE OF NEW JERSEY
)
COUNTY OF SALEM
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SS.
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J. J. Hagan, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
subscribed and swo~~rJ° before
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ary PubftiC:Jl.Jew Jersey My commission expires on me 1994 KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Comm1ssron Expires April 21, 1998
ATTACHMENT 1 NLR-N94049 LCR 94-11 RADIATION MONITORING INSTRUMENTATION I.
Description of Change A.
For specification 3/4.3.3.1 change Tables 3.3-6 and 4.3-3 to delete the following Salem specific radiation monitor numbers from the instrument description.
Functional Unit la
- delete R5/R9 Functional Unit lb
- delete R44 Functional Unit 2al - delete Rl2a Functional Unit 2a2 - delete Rlla Functional Unit 2bl - delete R45B Functional Unit 2b2 - delete R45C Functional Unit 2b3 - delete R46 Functional Unit 2b4 - delete Rl5 B.
For specification 3/4.3.3.1, on Table 3.3-6 change the footnote designated by "#" to read:
- The plant vent noble gas monitor may also function in thi~
capacity when the purge/pressure-vacuum relief isolation valves are open.
- c.
For specification 3/4.3.3.8, change Tables 3.3-12 and 4.3-12 to delete the following Salem specific radiation monitor numbers from the instrument description. Unit 2 numbers are in parentheses.
Functional Unit la
- delete l-R18 (2-R18)
Functional Unit lb
- delete 1-Rl9 A, B, c, and D)
(2-Rl9 A. B. c. and D)
Functional Unit 2a
- delete l-Rl3 A, B, c, D, and E (2-Rl3 A, B, and C)
Functional Unit 2b Not applicable to Unit 1 For Unit 2 delete R37 D.
For specification 3/4.3.3.9, change Tables 3.3-13 and 4.3-13 to delete the following Salem specific radiation monitor numbers from the instrument description. Unit 2 numbers are in parentheses.
Functional Unit la
- delete l-R41C (2-R41C)
Functional Unit 2a
- delete 1-R41C or l-R12A (2-R41C or 2-Rl2A)
Functional Unit 3a
- delete l-Rl6 or 1-R41C (2-Rl6 or 2-R41C)
- '1-1....
NLR-N94049
- 2 LCR 94-11 E.
Modify the Bases for specifications 3/4.3.3.1, 3/4.3.3.8 and 3/4.3.3.9 to include the cross reference between radiation monitor function and Salem specific numbers II. Justification Current Salem Technical Specifications include a functional description of the radiation monitor as well as a Salem specific radiation monitor designator.
When monitors are replaced or upgraded, the designator is changed to ensure proper configuration control of documentation associated with the radiation monitor.
The incorporation of the Salem specific radiation monitor numbers into the Bases will ensure that this information is still maintained and available to the necessary personnel.
However, by relocating the radiation monitor numbers to the Bases, the numbers may be changed without submittal of a License Change Request.
Bases are controlled in accordance with the 10CFR50.59.
This would eliminate an unnecessary regulatory burden.
The change associated with the note on Table 3.3-6 is editorial to provide a more accurate description of the radiation monitor referenced.
The new description is consistent with the radiation monitor description on the table.
III. In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not:
- 1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
The proposed change to relocate the Salem specific radiation monitor numbers to the Bases is administrative.
There are no modifications or changes in operating conditions associated with the proposed changes.
Providing a more accurate description of a referenced radiation monitor in the note is editorial.
The proposed changes do not affect the probability of occurrence or the consequences of accidents identified in the UFSAR.
No accident precursors are being generated by the proposed changes.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of a previously analyzed accident.
NLR-N94049
- 3 LCR 94-11
- 2.
Create the possibility of a new or different kind of accident.
The proposed changes to relocate the Salem specific radiation monitor numbers to the Bases are administrative.
The change to the note on Table 3.3-6 is editorial to provide a more accurate description of the required radiation monitor.
There are no modifications or changes in operating conditions associated with the proposed changes.
Therefore, the proposed changes will not increase the possibility of a new or different kind of accident from any accident previously identified.
- 3.
Involve a significant reduction in a margin of safety.
The Technical Specification operability requirements for the radiation monitors are not being changed.
Relocating the Salem specific radiation monitor numbers to the Bases will not change any requirements for the radiation monitors.
The change to the note on Table 3.3-6 is editorial to provide a more accurate description of the required radiation monitor.
Therefore, the changes to the surveillance frequencies do not involve a significant reduction in any margin of safety.
IV.
Based upon the preceding information, PSE&G has concluded that the proposed changes meet the requirements of 10CFR50.92(c) and does not involve a significant hazards consideration.
ATTACHMENT 2 MARKED UP PAGES
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