ML20211E256
| ML20211E256 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/16/1986 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211E261 | List: |
| References | |
| NUDOCS 8610220393 | |
| Download: ML20211E256 (10) | |
Text
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y rar UNITED STATES
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g NUCLEAR REGULATORY COMMISSION D
- j WASHINGTON, D. C. 20555
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LOUISIANA POWER AND LIGHT COVPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment, dated June 25, 1986, as supplemented by letters dated August 4, 1986 and September 2, 1986, by Louisiana Power and Light Company (licensee), complies with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
0610220393 861016 PDR ADOCK 0D000302 P
- (2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
LP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p y, Ja W.; H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B i
Attachment:
Changes to the Technical Specifications Date of Issuance: October 16, 1986 i
i 6
October 16, 1986.
ATTACHMENT TO LICENSE AMENDMENT NO. 7 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4 1-23 3/4 1-24 5-5 5-6 6-5 6-6 6-6A I
e se i
1 j
i 6
9
REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a fully withdrawn position, shall be less than or equal to 3.0 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90% insertion position with:
T,yg greater than or equal to 520 F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY: M0GES 1 and 2.
ACTION:
a.
With the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full-length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following each removal and reinstallation of the reactor vessel head, b.
For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.
At each refueling outage.
}
WATERFORD - UNIT 3 3/4 1-23 AMENDMENT NO. 7 I
REACTIVITY CONTROL SYSTEMS SHUTDOWN CEA INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown CEAs shall be withdrawn to greater than or equal to 145 inches.
APPLICABILITY: MODES I and 2*#**.
ACTION:
With a maximum of one shutdown CEA withdrawn to less than 145 inches withdrawn, within l' hour either:
Withdraw the CEA to greater than or equal to 145 inches, or a.
b.
Declare the CEA inoperable and determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown CEA shall be determined to be withdrawn to greater than or equal to 145 inches withdrawn:
Within15minutespriortowithdr$walofanyCEAsinregulating a.
groups during an approach to reactor criticality, and b.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereaf ter.
- See Special Test Exception 3.10.2.
- With K,ff greater than or equal to 1.0.
- Except for surveillance. testing pursuant to Specification 4.1.3.1.2.
WATERFORD - UNIT 3 3/4 1-24
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 150 inches and contain a nominal total weight of 1807 grams uranium.
The initial core loading shall l
have a maximum enrichment of 2.91 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum i
enrichment of 4.0 weight percent U-235.
I CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 83 full-length and 8 part-length control element assemblies.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
In accordance 'ith the code requirements specified in Section 5.2 a.
of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.
For a pressure of 2500 psia, and For a temperature of 650*F, except for the pressurizer and surge line c.
which is 700"F.
i VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800
+600, -0 cubic feet at a nominal T,yg of 582.1*F.
5.5 METEOROLOGICAL TOWERS LOCATION 5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 5.1-1.
WATERFORD - UNIT 3 5-5 AMENDMENT NO. 7 l
I
DESIGN FEATURES 5.6 FUEL STORAGE l
CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance for uncertainties.
b.
A nominal 10.38 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
- 5. 6. 2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.3 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL.
CAPACITY 5.6.4 The spent fuel pool is designed and shall be maintained with a storage capacity limi~ted to no more than 1088 fuel assemblies.
5.7 COMPONENT CYCLIC OR T.RANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
l WATERFORD - UNIT 3-5-6 AMENDMENT NO. 7
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, OR 4 MODE 5 OR 6 SS la 1
SRO 1*
None R0 2
1 A0 2
1 STA 1*
None l
SS Shift Supervisor with a Senior Operator License SR0 Individual with a Senior Operator License RO Individual with an Operator License A0 Auxiliary Operator STA -
Shift Technical Advisor Except for the Shift Supervisor, the shift crew composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the control room command function.
- An individual with SR0/STA qualifications can satisfy the SS/STA or SR0/STA position requirements simultaneously.
WATERFORD - UNIT 3 6-5 AMENDMENT NO. 7
ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety.
The ISEG shall make detailed recommendations for revised procedures, equipment modifica-tions, maintenance activities, operations activities, or other means of improving unit safety to the Engineering and Nuclear Safety Manager.
COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a bachelor's degree in engineering or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errers are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISEG is an onsite independent technical review group that reports to the Engineering an6 Nuclear Safety Manager.
The ISEG shall have the authority necessary to perform the functions and responsibilities as delineated above.
RECORDS 6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Engineering and Nuclear Safety Manager.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
The STA shall meet the requirements of either Option 1 or 2 as shown below:
a.
Option 1 - Combined SR0/STA Position.
This option is satisfied by 1
assigning an individual with the following qualifications to each operating shift crew as one of the SR0's required by 10 CFR 50.54(m) (C) (1):
- Not responsible for sign-off function.
t WATERFORD. UNIT 3 6-6 AMENDMENT NO. 7
ADMINISTRATIVE CONTROLS SHIFT TECHNICAL ADVISOR (Continued) 1.
Licensed as a Senior Reactor Operator on the unit and 2.
Meets the STA Training Criteria of NUREG-0737, Item I.A.1.1, and one of the following educational alternatives:
(a) Bachelor's Degree in Engineering or Science from an accredited institution; (b) Professional Engineers License obtained by the successful completion of the PE examination; (c) Bachelor's Degree in Engineering or Science Technology from an accredited institution including course work in the physical, mathematical, or engineering sciences.
b.
Option 2 - Dedicated STA Position.
This option is satisfied by placing on each shift a dedicated Shift Technical Advisor (STA) who meets the STA criteria of NUREG-0737, Item I.A.1.1.
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WATERFORD - UNIT 3 6-6a AMENDMENT NO. 7