ML20217C123
| ML20217C123 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/11/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217C120 | List: |
| References | |
| NUDOCS 9710010204 | |
| Download: ML20217C123 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 306 # 4 001
.....,o SAFETY EVALUATION BY THE OFFICJ.0F NUCLEAR REACTOR REGULATION RELATED TO AMENDMuG A'.
t ro TO FACillTY OPERATING LIC E 20 NPF-49 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL, MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By letter dated June 19, 1997, the Northeast Nuclear Energy Company, et al.
(the licensee), submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 3 Technical Specifications (TS). TS 3/4.7.1.3 requires sufficient water to be available for the auxiliary feedwater (AFW) system to maintain the reactor coolant system at hot standby for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> before cooling down to hot shutdown in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The proposed amendment would increase the required volume of water when the demineralizer water storage tank (DWST) and condensate storage tank (CST) are being credited, make editorial changes, and expand the descriptions in Bases Sections 3/4.7.1.2 and 3/4.7.1.3.
2.0 EVALUATION Final Safety Analysis Report (FSAR) Section 10.4.9.1 states that the DWST is designed to provide sufficient water to allow (1) 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of hot standby condition of the plant; (2) an additional 6-hour cooldown period sufficient to reduce reactor coolant hot leg temperature to 350*F to allow residual heat removal system operation; and (3) in the event of a secondary system rupture, sufficient water to allow for 30 minutes of spillage before operator action to isolate the depressurized steam generator.
In its letter dated June 19, 1997, the licensee stated that the proposed change to TS Surveillance 4.7.1.3.2 will account for the additional unusable inventory when the combined DWST and CST inventory are being credited to provide the inventory for the AFW system. The requirement specified in TS Surveillance 4.7.1.3.2 for combined DWST and CST inventory is being increased by 50,000 gallons from 334,000 gallons to 384,000 gallons, to account for unusable CST volume due to tank discharge line location, other physical characteristics, and measurement uncertainty.
The licensee stated that the operability of the DWST with a 334,000-gallon minimun. or a combined DWST/ CST with a 384,000-gallon minimum measured water volume ensures that sufficient water is available to maintain the reactor coolant system at hot standby conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to 9710010204 97091g DR p
ADOCK 05000423 PDR
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.. the atmosphere, concurrent with a total loss-of-offsite power, and with an additional 6-hour cooldown period to reduce reactor coolant temr.rature to 350*F.
In the event of a feedline break, the licensee stated that the inventory requirements include an allowance for 30 minutes of spillage before operator action is credited to isolate flow to the line break.
The NRC staff has reviewed the proposed change to TS Surveillance 4.7.1.3.2 and finds it acce) table. The staff's determination is based on the fact that the TS sup) orts tie FSAR description and requirements and accounts for tank physical claracteristics and measurement uncertainties.
The staff has reviewed the editorial changes made to TS 3.7.1.3. TS 4.7.1.3.1, and TS 4.7.1.3.2 and finds them acceptable.
In addition, the staff has reviewed the changes to Bases Sections 3/4.7.1.2 and 3/4.7.1.3 and has no objection to the wording.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component located within the restricted a-ea 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.ffluents that may be released offsite, and that there is no signifir..it increase in individual or cumulative occupational radiation exposure. Th. Comission has previously issued a proposed finding that the amendment involves no significant hazards consider.ation, and there has been no public coment on such finding (62 FR 40853 dated July 30,1997). 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
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 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 Contributor: J. Andersen Date:
September 11, 1997
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