ML20211D032
| ML20211D032 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/16/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211D015 | List: |
| References | |
| NUDOCS 8610220083 | |
| Download: ML20211D032 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION
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WASHING TON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 6 TO FACILITY OPERATING LICENSE NO.' NPF-38 LOUISIANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated August 1,1985, as supplemented by letter dated October 8, 1986, Louisiana Power and Light Company (the licensee), requested changes to the Technical Specifications (Appendix A to Facility Operating License No.
NPF-38) for the Waterford Steam Electric Station, Unit 3.
The proposed changes would:
(1) correct three typographical errors in Table 3.8-1,
" Containment Penetration sonductor Overcurrent Protective Devices"; (2) change Technical Specification 3/4.9.7, " Crane Travel-Fuel Handling Building" so that use of the spent fuel handling machine is not required for movement of new fuel outside the spent fuel pool; and (3) revise Technical Specification 3/4.7.2, " Steam Generator Pressure / Temperature Limits".
2.0 DISCUSSION The changes to the technical specifications requested by the licensee are in three areas as described below.
Containment Penetration Conductor Overcurrent Protection Devices The proposed charge revises the Appendix A Technical Specifications by correcting three typographical errors in Table 3.8-1, " Containment Penetration Conductor Overcurrent Protective Devices" of Technical Specification 3/4.8.4, " Electrical Equipment Protective Devices."
Technical Specification 3/4.8.4 delineates the operability and surveillance requirements for the containment penetration conductor overcurrent protective devices listed in Table 3.8-1.
The requirements of this Technical Specification ensure these devices will not prevent safety-related valves from performing their function. The proposed change to Table 3.8-1 consists of the following three parts:
a.
Item 8, 480 Volts Power from MCCs, of Table 3.8-1 (page 3/4 8-24) currently lists the valve number as ISI-V1508 TK 1B. The proposed change will correct the typographical error in the tank designation suffix to accurately list the valve number as ISI-V1508 TK 28.
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b.
Item 57,120 Volts Control Power from PDPs or MCCs, of Table 3.8-1 (page 3/4 8-39) currently lists the Power Distribution and Motor Data (PDMD) sheet number for primary protection as 148. The proposed change will correct the typographical error to accurately list the PDMD sheet number as 148A.
c.
Item 71, 120 Volts Control Power from PDPs or MCCs, of Table 3.8 (page 3/4 8-41) currently lists the valve number as 2BM-P237. The i
proposed change will correct the typographical error in the code class prefix to accurately list the valve number as 7BM-P237.
Crane Travel - Fuel Handling Euilding The proposed change revises the Appendix A Technical Specifications by changing Technical Specification 3/4.9.7, " Crane Travel-Fuel Handling Building," so that use of the spent fuel handling machine is not required for movement of new fuel outside the spent fuel pool.
The purpose of Technical Specification 3/4.9.7 is to restrict movement of loads in excess of the nominal weight of a fuel assembly, control element assembly (CEA), and associated handling tool over other fuel assemblies in the spent fuel pool to ensure that in the event this load is dropped, (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critidal array..The original intent of the Specification, as it relates to_new fuel, was to require new fuel within the spent fuel pool be handled by the spent fuel handling machine to protect against damage to irradiated fuel.
The proposed change to Technical Specification 3.9.7 will clarify that the use of the spent fuel handling machine is not required for movement of new fuel assemblies outside the spent fuel pool and will also allow for movement of new fuel assemblies in areas other than the spent fuel pool.if the spent fuel handling machine is inoperable.
Along this line, the proposed change will bring Technical Specification 3/4.9.7 into conformance with FSAR Section 9.1.4 which specifies the use of other fuel handling equipment (cask crane, new fuel elevator, etc.) for the movement of new fuel outside the spent fuel pool.
The proposed change consists of the following two parts:
a.
Technical Specification 3.9.7 currently states in part:
" Cranes in the fuel handling building shall be restricted as follows:
- a. The spent fuel handling machine shall be used for the movement of fuel assemblies (with or without CEAs) and shall be OPERABLE with...."
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- The proposed change will add the following note of clarification:
"Not required.for movement of new fuel assemblies outside the spent fuel pool."
b.
The proposed change will add the following Action Statement to Technical Specification 3.9.7:
"The provisions of Specification 3.0.4 are not applicable."
Specification 3.0.4 normally pr' events entry into the applicable mode or condition (movement of fuel assemblies in this case) unless the conditions of the Limiting Condition for Operation are met. This added ACTION Statement will allow for start of new fuel movement in areas other than the spent fuel pool while ACTION Statement a. is in effect.
Steam Generator Pressure / Temperature Limits The proposed change revises the Appendix A Technical Specifications by changing Technical Specification 3/4.7.2 " Steam Generator Pressure / Temperature Limits" and reflecting this change in the related section of the Bases.
The purpose of Technical Specification 3/4.7.2 is to ensure that steam generator secondary pressure and temperature is limited so that pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The purpose of Specification 3.7.2(b) is to ensure, in the event of a low temperature overpressurization of the steam generator secondary, that an engineering evaluation is completed and it is detennined that the steam generator remains acceptable for continued operation.
The proposed change will. allow for steam generator temperatures up to 200 F prior to completion of the engineering evaluation, consistent with the Revision 3 of the CE Standard Technical Specifications. The present temperature value of 115 F, with respect to perfonning an eng(ineering evaluation, is incorrect.
The LIMITING CONDITION FOR OPERATICN LCO) 3.7.2 properly requires that secondary side steam generator temperature be greater than 115*F when secondary side pressure is above 210 psig. The limitation to 115*F and 210 psig is based on a steam cenerator RT of 40*F, which is sufficient to prevent brittle fracture. However, N n the Waterford 3 Technical Specifications were issued, the LC0. temperature of 115'F was inadvertently substituted into ACTION statement 3.7.2.b.
As noted above, the CE Standard Technical Specification temperature limitation of 200*F prior to completion of the engineering evaluation (the ACTION statement temperature) should not have been stated as 115 F.
Raising the ACTION statement temperature limitation to 200*F corrects this error and is more conservative in the event of an overpressure condition.
3.0 EVALUATION Containment Penetration Conductor Overcurrent Protective Devices The proposed changes to Table 3.8-1, as described above, are purely admin-istrative and will only correct typographical errors to bring the Technical Specification into conformance with other plant documents. Therefore, the proposed changes will not involve a.significant increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated or involve a significant reduction in the margin of safety.
The staff finds these proposed changes to be acceptable.
Crane Travel - Fuel Handling Building The proposed change to Technical Specification 3/4.9.7, as described ab'ove, will allow for the use of fuel handling equipment designed and intended for the movement of new fuel outside the spent fuel pool and bring the Technical Specification into conformance with the FSAR.
The Fuel Handling Accident Analysis in FSAR Chapter 15 is based on the Fuel Handling System described in FSAR Subsection 9.1.4.
The proposed change only allows for the use of fuel handling equipment as described by FSAR Subsection 9.1.4 and continues to restrict the movement of heavy loads over fuel assemblies in the fuel spent pool..Therefore, the proposed change will not involve any increase in the probability or consequences of any accident previously evaluated.
Operation of the' facility will be in accordance with the assumptions made in the FSAR and the Technical Specification that fuel will be handled in accordance with the designed fuel handling system and movement of heavy loads in the spent fuel pool will be restricted. Therefore, the proposed change will not involve any reduction in margin of safety.
Operation of the facility will be in accordance with the assumptions made in the FSAR and the Technical Specification that fuel will be handled in accordance with the designed Fuel Handling System and movement of heavy loads in the spent fuel pool will be restricted. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The staff concludes that the proposed change is acceptable.
Steam Generator Pressure / Temperature Limits The proposed change will change the temperature value of 115'F by revising Technical Specification 3.7.2(b) to reflect the 200 F temperature value shown in the CE Standard Technical Specifications, which is the temperature value originally intended for this ACTION. Thus, the proposed change will correct an error that occurred during development of the Technical Specifications.
~
The lowest service temperature for the secondary side of the steam generators is 115 F when pressure is 210 psig or greater. Assuming steam generator temperature drops below 115 F, the Technical Specification as currently written limits temperature to 115'F or below while an engineering evaluation is performed.
In so doing, the Technical Specification unnecessarily exposes the steam generators to the potential for brittle fracture in the event of an overpressure condition. The proposed change would allow an increase in steam generator temperature up to 200 F while perfoming the engineering evaluation, this providing a more conservative condition with respect to brittle fracture should an overpressure condition occur. Therefore, the proposed change will not involve any increase in the probability or consequences of any accident previously evaluated.
In fact, the probability of brittle fracture will decrease.
Temperatures less than 200"F do not impact Loss of Ccolant Accident or Main Steam Line Break considerations. The proposed change requires temperatures be maintained to 200*F or less until it is determined that the steam generator remains acceptable for continued operation. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The lowest service temperature for the secondary side of the steam generators is 115'F. ~ The Technical Specification, as currently written, limits the temperature to 115*F or below and is nonconservative because it unnecessarily exposes the steam generator to brittle fracture in the event of an overpressure condition.
The proposed change allows for temperatures up to 200*F, providing for a more conservative condition by allowing temperatures that will place the steam generator material in the ductile range and making them less susceptible to brittle fracture. Therefore, the proposed change increases rather than decreases the margin of safety.
The brittle fracture resistance of the Waterford 3 steam generator materials increases with increased temperature. Since the increase in temperature (from 115'F to 200'F) would result in an increase in brittle fracture resistance of the steam generator materials, the staff concludes that the proposed change is acceptable.
In order to be consistent with the change made in TS 3/4.7.2, the related section of the Bases is being changed to reference the 200 F temperature limitation while the engineering evaluation is being performed.
4.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Administrator, Nuclear Energy Division, Department of Environmental Quality, State of Louisiana of the proposed determination of no significant hazards consideration. No coments were received.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of facility components located within the restricted area..The staff has detemined that the amendment involves no significant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual-or
cumulative occupation radiation exposure. The Commission has previously issued proposed findings that the amendment involves no significant hazards consideration, and there has been no public comment on such findings.
(The change in the Bases for TS 3/4.7.2 required no prior notice of consideration of issuance of amenemnt.) 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 this amendment.
6.0 CONCLUSION
Based upon our evaluation of the proposed changes to the Waterford 3 Technical Specifications, we have concluded that:
there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendments will not be inimical to the connon defense and security or to the health and safety of the public.
We, therefore, conclude that the proposed changes are acceptable, and are hereby incorporated into the Waterford 3 Technical Specifications.
Dated: October 16, 1986
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