ML20070M964
| ML20070M964 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/25/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070M959 | List: |
| References | |
| NUDOCS 9405040216 | |
| Download: ML20070M964 (4) | |
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t UNITED STATES E
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WASHINGTON, D.C. 205E0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT 0fLREGULATION RELATED TO AMENDMENT NO. 211 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT 5
DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated January 31, 1994, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. FitzPatrick*
Nuclear Power Plant Technical Specifications (TSs).
Specifically, the licensee requested changes to Appendix B of the TSs, the Radiological Effluent TSs.
The requested changes would revise Appendix B TS 3.5 and the associated Bases, to establish a threshold level below which there will be no requirement to perform grab samples and isotopic analyses of steam jet-air ejector when entering an SJAE limiting condition for operation (LCO). effluen SJAE) the requested changes would revise TSs to clarify instructions and makeIn addition, editorial corrections which are administrative in nature.
2.0 EVALUATION 2.1 SJAE Grab Samoles and Isotopic Analysis The licensee has proposed to revise Appendix B TS 3.5 and the associated Bases to establish a threshold level below which there will be no requirement to perform grab samples and isotopic analyses of SJAE effluent.
when the process radiation monitor indicates an increased releas greater than 50 percent after correction for changes in thermal power level.
detected, ensuring that the 10 CFR Part 20 limits are not exceeded.T
- However, when release rates are small, the installed detectors are not sufficiently sensitive to effectively monitor the effluent. To monitor the effluent at lower release rates, the licensee performs grab samples three times a week.
This task results in additional radiation exposure to workers.
The proposed change would add a threshold detection level of 5,000 pci/sec, below which no additional grab samples and isotopic analysis would be required.
The change would eliminate the need to perform grab samples three times a week while at lower release rates, thus minimizing radiation exposure to workers, 9405040236 940425 PDR ADOCK 05000333 P
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The threshold level (5000 pci/sec) is 1 percent of the SJAE monitoring trip level setting and less than 10 percent of the SJAE instrument alarm value.
This threshold value is sufficiently low so that significant fuel pin defects i
would still be identified prior to exceeding the 500,000 pci/sec trip setting, i
and long before the 10 CFR Part 20 limits are exceeded. Therefore, the change would not significantly reduce the margin of safety currently provided by the existing TSs.
4 Based on the fact that adequate monitoring of SJAE effluent monitoring I
capability is maintained, there would be no decrease in the margin of safety currently required by the existing technical specifications, and the change would help to minimize worker radiation exposure, the NRC staff finds the proposed change to be acceptable.
2.2 Revision of Main Condenser SJAE LCO The licensee has proposed to revise Appendix B TS Table 3.10-1 to change the required actions when a SJAE LC0 is entered. TS Table 3.10-1 currently 3
1 requires the release rate to be brought below the trip level (500,000 pci/sec) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, of exceeding the trip level, or be in hot standby within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The proposed change would remove the requirement to be in hot standby but would require, instead, isolation of all main steam lines or the i
SJAE.
l The proposed change would provide a level of control equivalent to i
Section 3.7.6 of NUREG-1433, " Standard Technical Specifications (STSs) for General Electric Boiling Water Reactors (BWR/4)." The STSs require the release rate to be brought below the trip level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, of exceeding the trip level, or 1) isolate all main steam lines within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
or 2) isolate SJAE within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or 3) be in hot standby within
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the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.' The proposed change is more limiting than the STSs because it does not provide the option of shutting down in lieu of isolating the main steam lines or the SJAE.
4 Bringing the reactor to a shutdown condition does not prevent the release of i
radioactive gases since the main steam isolation valves, main steam line drains, and the SJAE may still operate allowing the release of gases to the environment.
i Based on the fact that the proposed change provides a level of control equivalent to the STSs, the NRC staff finds the change to be acceptable.
j 2.3 Administrative Chanaes The licensee proposed to revise Appendix B TSs to clarify instructions and make editorial corrections which are administrative in nature. The staff has reviewed these proposed changes and determined that they are acceptable since j
they do not involve any substantive changes to requirements.
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3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no coments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (59 FR 10014). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant.to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
i The Comission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in-compliance with the Comission's regulations, and (3) the issuance of the anendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
G. Replogle Date:
April 25, 1994
F Aprti 25, 1994 Docket No. 50-333 Mr. William J. Cahill, Jr., Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Cahill:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M88677)
The Commission has issued the enclosed Amendment No. 211 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated January 31, 1994.
The amendment revises Appendix B of the TSs, the Radiological Effluent TSs.
Specifically, the amendment revises Appendix B TS 3.5, and the associated Bases, to establish a threshold level below which there will be no requirement to perform grab samples and isotopic analyses of steam jet-air ejector (SJAE) effluent, and revises Appendix 8 TS Table 3.10-1 to change the actions required when entering a SJAE limiting condition for operation. Additionally, the amendment revises the TSs to clarify instructions and make editorial corrections which are administrative in nature.
A copy of the related Safety Evaluation is enclosed.
'A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, Original signed by Brian C. McCabe, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.211 to DPR-59 2.
Safety Evaluation cc w/ enclosures:
See next page
- See previous concurrence Distributign:
See attached sheet LA:PDI-1 PE:PDI-1
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