ML20064H250
| ML20064H250 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/09/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064H244 | List: |
| References | |
| NUDOCS 9403170218 | |
| Download: ML20064H250 (4) | |
Text
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UNITED STATES g(g
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NUCLEAR REGULATORY COMMISSION g
W ASHINGTON D.C. 20555-0001 SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 207 TO FACILITY OPERATING LICENSE N0. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORKa JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333
1.0 INTRODUCTION
By "JPN-93-050, Forwards Application for Amend to License DPR-59,proposing Elimination of MSIV Closure Function & Scram Function of [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Radiation Monitor|letter dated July 15, 1993]], the Power Authority of the State of New York (PASNY, the licensee) submitted a request for changes to the James A.
FitzPatrick Nuclear Power Plant Technical Specifications. The requested changes would eliminate the reactor scram and Main Steam Isolation Valve (MSIV) closure requirements associated with the Main Steam Line Radiation Monitors (MSLRM). The licensee has experienced spurious trips of the MSLRM channels on numerous occasions in the past.
Failure of one of the MSLRM was a contributing factor to an automatic reactor scram on May 25, 1993.
The licensee states that elimination of the trip functions will reduce scram frequency, maintain availability of condenser heat sink, eliminate the potential for trips due to hydrogen water chemistry, and increase operator control over radioactive releases. The licensee's proposed change is based on the May 1987 Boiling-Water Reactor (BWR) Owners Group Licensing Topical Report NED0-31400, " Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Line Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," and the Standard Review Plan (SRP) 15.4.9, Revision 2, July 1981.
As stated in NED0-31400, and indicated in FitzPatrick Final Safety Analysis Report (FSAR), the automatic reactor shutdown on the MSLRM trip is not given credit in the analysis of any design basis event for BWRs. The FSAR assumes that only in a control rod drop accident (CRDA) do MSIVs close on the MSLRM trip. However, the SRP 15.4.9 recommends that the radioactive source term is assumed to already have been transferred to the condenser and turbine prior to MSIV closure. The SRP 15.4.9 also states that the plant site and dose mitigating engineered safety features are acceptable with respect to the radiological consequences of a postulated CRDA if the calculated whole-body and thyroid doses at the exclusion area boundaries are within 25 percent of the exposure guideline values of 10 CFR Part 100.
In NED0-31400, a reevaluation of the role of the MSLRM in the CRDA analysis was performed, confirming that removal of the MSLRM scram / isolation features would not compromise CRDA consequences.
The topical report also evaluated the 940317o218 940309 PDR ADOCK 0500 8
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J i i potential effect on occupational exposure in the event of a sudden release of radioactivity from the fuel and concluded that the elimination of the scram / isolation features would have no adverse effect.
2.0 EVALUATION In a May 15, 1991, Safety Evaluation (SE), the NRC staff accepted the referencing of NED0-31400 for the elimination of the MSIV closure function and scram function of the MSLRM, as long as the following three conditions were met:
1.
The applicant demonstrates that the assumption with regard to input values, including power per assembly, Chi /Q, and decay times, that were made in the generic analysis, l'ound those for the plant.
2.
The applicant includes sufficient evidence, implemented or proposed operating procedures or equivalent commitments, to provide reasonable assurance that increased significant levels of radioactivity in the main steam lines will be controlled expeditiously to limit both occupational doses and environmental releases.
3.
The applicant standardizes the MSLRM and offgas radiation monitor alarm setpoint to 1.5 times the nominal "N background dose rate at the monitor locations and commit to promptly sample the reactor coolant to determine possible contamination levels in the reactor coolant and the need for additional corrective action, if the MSLRM or offgas radiation monitors or both exceed their alarm setpoints.
In response to Condition 1, the licensee stated that the assumptions made in the generic analysis bound those for FitzPatrick.
The NRC staff has reviewed the licensee's assurnptions for the values such as Cht/Q and power level per assembly and has concluded that the generic analysis assumptions bound those presented in the FitzPatrick analysis.
In response to Condition 2, the licensee's submittal indicated that they have procedures in place which provide reasonable assurance that the plant is capable of responding to increased radiation levels as detected by the offgas monitor; the Annunciator Response Procedures (ARPs) and an Abnormal Operating Procedure (A0P) currently control the plant response.
The licensee states that procedures are in place which ensure that actions are taken to limit occupational doses and environmental releases. The licensee has stated that the Fitzpatrick Operating License permits bypassing of the Offgas Treatment System during plant startup.
NED0-31400 states that this condition is acceptable provided the offgas radiation monitors are being utilized to automatically isolate the offgas process line. The Steam Jet Air Ejector isolation feature conforms with the NED0-31400 criteria, and precludes a direct release to the environment.
In the event the offgas system is isolated, the offgas dose is equivalent to the FSAR design basis scenario
(with MSIV isolation) since in this case the activity is assumed to be transferred to the main condenser, followed by a ground level release.
The NRC conditions stipulated in the safety evaluation for the offgas radiation monitor will be implemented as described for Condition 3.
The existing procedures will be revised to remain consistent with the commitments and requirements of the requested change.
The NRC staff has reviewed the licensee's commitment and has determined it is acceptable and responsive to Condition 2, which was required to be addressed per Topical Report NED0-31400.
In response to Condition 3, the licensee has stated that concurrent with the modification of the MSLRM trip, the alarm setpoints on the MSLRH and offgas radiation monitor will be adjusted to less than or equal to 1.5 times the normal full power N-16 background dose rate.
This does account for the 2
increased N-16 carryover due to hydrogen water chemistry. The licensee has also stated that prior to modification of the MSLRM trip, the plant procedures will be revised to require prompt sampling of the reactor coolant to determine the need for corrective actions, if the MSLRM or offgas radiation monitors, or both, exceed their alarm setpoints.
In review of the licensee's commitment, the staff has determined that the
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Condition 3 has been satisfied.
3.0
SUMMARY
The NRC staff has reviewed the licensee's submittal and safety analysis and concludes that there are no adverse safety implications associated with removal of the MSLRM scram and MSIV closure function since the licensee has provided reasonable assurance that the offsite radiation exposure levels are within the guidelines of 10 CFR Part 100 and SRP 15.4.9.
Therefore, the NRC staff finds that TS changes proposed by the licensee are acceptable.
4.0 STATE CONSULTATI0E 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.
5.0 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. 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 Commission has previously issued a proposed finding that the
o amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR 41513). 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 i
the amendment.
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6.0 CONCLUSION
i The Commission 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 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
R. Frahm 1
R. Emch Date: March 9, 1994 a
4 I
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f Docket No. 50-333 March 9, 1994 Mr. William A. Josiger, Acting Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Josiger:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC N0. M86978)
The Commission has issued the enclosed Amendment No.207 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 "JPN-93-050, Forwards Application for Amend to License DPR-59,proposing Elimination of MSIV Closure Function & Scram Function of [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Radiation Monitor|letter dated July 15, 1993]].
l The amendment revises the TSs to eliminate the reactor scram and Main Steam Line Isolation Valve closure requirements associated with the Main Steam Line Radiation Monitors. The changes are consistent with Licensing Topical Report NED0-31400, " Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," dated May 1987.
This license amendment is effective as of the date of its issuance to be l
l implemented prior to startup following the next FitzPatrick refueling outage.
Please notify the NRC, in writing, within 30 days of implementing this l
amendment.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance l
will be included in the Commission's next regular biweekly Federal Reaister i
notice.
Sincerely, Original signed by:
Brian C. McCabe, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 207 to DPR-59 2.
Safety Evaluation cc w/ enclosures:
See next page Distribution:
See attached sheet
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OFFICIAL RECORD COPY FILENAME: FIT 86978.AMD
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