ML20128B125
| ML20128B125 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/24/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128B129 | List: |
| References | |
| NUDOCS 8507030135 | |
| Download: ML20128B125 (7) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION r,
-j WASHipvGTON,0. C. 2C555 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SU MER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 43 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Virgil C. Sumer Nuclear Station, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated April. 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this license 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 43 are hereby incorporated into this license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8507030135 850624 PDR ADOCK 05000395 l
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2 3.
This license amendment is effective seven days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hL e
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Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: June 24, 1985 5
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ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 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 areas o,f change. The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf
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3/4 1-14 3/4 1-13 B3/4 1-4 B3/4 1-3
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l REACTIVITY CONTROL SYSTEMS i
SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE-a.
At least once per 7 days by:
1.
Verifying the boron concentration in the water, 2.
Verifying the contained borated water volume of the water -
source, and 3.
Verifying the boric acid storage system solution temperature when it is the source of borated water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40*F.
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$UMMER - UNIT 1 3/4 1-13
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1 I
4 REACTIVITY CONTROL SYSTEMS t
3/4.1.3 M0VA8LE CONTROL ASSEN8 LIES I
GROUP HEIGHT
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LIMITING CONDITION FOR OPERTION i
3.1.3.1 All full length (shutdown and control) rods which are inserted in the L
core shall be OPERA 8LE and positioned within i 12 steps (indicated position) of their group step counter demand position.
APPLICA8ILITY: MODES 1* and 2*
ACTION:
a.
With one or more full length rods inoperable due to being immovable
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as a result of excessive friction or mechanical interference or 9
known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within I hour and be in i
l HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1
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With'more than one full length rod misaligned from the group step l
b.
counter demand position by more than i 12 steps (indicated position),
be in H0T STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With more than one full length rod inoperable due to a rod control urgent failure alare or obvious electrical problem in the rod control system for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in NOT STAN08Y within the fol-lowing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i d.
With one full length rod inoperable due to causes other than addressed l
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by ACTION a., above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within one hour either:
i 1.
The rod is restored to OPERABLE status within the above alignment requirements, or 1
2.
The remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod within one hour i
while maintaining the rod sequence and insertion limits of Fig-l ures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted l
pursuant to Specification 3.1.3.6 during subsequent operation, or l
3.
The rod is declared inoperable and the SHUT 00WN MARGIN l
requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
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- See Special Test Exceptions 3.10.2 and 3.10.3.
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SUMMER - UNIT 1 3/4 1-14 Amendment No. 43 i
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REACTIVITY CONTROL SYSTEMS BASES l
BORATION SYSTEMS (Continued)
MARGIN from expected operating conditions of 1.77% delta k/k after xenon decay and cooldown to 200*F. The maximum expected boration capability requirement I
occurs at EOL from full power equilibrium xenon conditions and requires 12475 gallons of 7000 ppm borated water from the boric acid storage tanks or 64,040 gallons of 2000 ppm borated water from the refueling water storage tank.
With the RCS temperature below 200'F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 275'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.
The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 2 percent delta k/k af ter xenon decay and cooldown from 200*F to 140'F. This condition requires either 2000 gallons of 7000 ppm borated water from the boric acid storage tanks or 9690 gallons of 2000 ppm borated water from the refueling water storage tank.
The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on 1
mechanical systems and components.
i The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES
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The specifications of this section ensure thati(1) acceptable power distribution limits are maintained, (2) the minimur SHUTDOWN MARGIN is main-tained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
SUMMER - UNIT 1 B 3/4 1-3 l
REACTIVITY CONTROL SYSTEMS BASES i
i MOVABLE CONTROL ASSEMBLIES (Continued) 1 For purposes of determining compliance with Technical Specification 3.1.3.1, any inoperability of full length control rod (s), due to being immovable, i
invokes ACTION statement "a".
The intent of Technical Specification 3.1.3.1 ACTION statement "a" is to ensure that before leaving ACTION statement "a" and utilizing ACTION statement "c" that the rod urgent failure alarm is illuminated or that an obvious electrical problem is detected in the rod control system by minimal electrical troubleshooting techniques. Expeditious action will be taken to determine if rod immovability is due to an electrical problem in the rod control system.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued operation.
In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation, j
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T,yg greater than or equal to 551'F and with all reactor coolant pumps operating ensures that the 2
measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
i SUMER - UNIT 1 8 3/4 1-4 Amendment No. 43 4
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