ML18009A308
| ML18009A308 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/07/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18009A310 | List: |
| References | |
| NPF-63-A-016 NUDOCS 8912200371 | |
| Download: ML18009A308 (8) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POMER 8 LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POMER PLANT UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 5 Light Company, (the licensee),
dated March 30,
- 1989, as supplemented April 25,
- 1989, and Hay 16, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility wi 11 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 viith 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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-63 is hereby amended to read as follows:
8912200 7
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Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix 8, both of which are attached
- hereto, as revised through Amendment Ho. 16,. are hereby incorporated into this license.
Carolina Power 5 Light Company sha'1 1 operate the facility in accordance with the Technical-Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION E.G. Tourigny/for
Attachment:
Changes to the Technical Specifications Elinor G. Adensam,'irector Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 7, 1989
[Sharris Amend 72883]
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ATTACHMENT TO LICENSE AMENDMENT NO. 16 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 I
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es xi 3/4 9-1 3/4 9-2 3/4 9-3
~IP xi 3/4 9-1 3/4 9-2 3/4 9-3
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3/4.10 F 1 3/4'0 '
3/4.10 '
3/4 10.4 SHUTDOWN MARGINo ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
GROUP HEIGHTN INSERTIONN AND POWER DISTRIBUTION LIMITS'
~
PHYSICS TESTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
REACTOR COOLANT LOOPS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3/4'0 '
POSITION INDICATION SYSTEM SHUTDOWNo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
SECTION 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices.
~ ~... ~.......
~. ~ ~.. ~....-....
TABLE 3 '
1 DELETED
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
MotorWperated Valves Thermal Overload Protection........
TABLE 3 ~ 8 2 DELETEDo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~. ~ ~ ~ ~ ~
TABLE 3.9-1 ADMINISTRATIVECONTROLS TO PREVENT DILUTION DURING REFUELINGo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~
3/4 ' '
INSTRUMENTATION,~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3/4.9.3 DECAY TIME. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS ~... ~. ~ ~.....
~ ~ ~ ~. ~.. ~..
3/4 ~ 9 ~ 5 COMMUNICATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~
3/4.9.6 REFUELING MACHINE. ~............
~.
~ ~...
~.
~ ~.. ~ ~ ~ ~ ~ o.o....
3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING,~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~..
3/4.9o8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION Hxgh Water Level... ~......
~.......
~ ~ ~. ~ ~ ~ ~. ~ ~ ~............
Low Water Level. ~ ~ ~ ~. ~..........
~ ~.".. ~. ~ ~..............
3/4'.9 CONTAINMENT VENTILATION ISOLATION SYSTEM. ~. ~ ~. ~ ~.. ~.....
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3/4.9.10 WATER LEVEL REACTOR VESSEL. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~
3/4.9.11 WATER LEVEL - NEW AND SPENT FUEL POOLS'
~ ~. ~.....
~. ~. ~ ~.
3/4 9ol2 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM. ~ ~ ~... ~. ~
3/4.10 SPECIAL TEST EXCEPTIONS PAGE 3/4 8-19 3/4 8-21 3/4 8-39 3/4 8-40 3/4 9"1 3/4 9-2 3/4 9-3 3/4 9-4'/4 9-5 3/4 9-6 3/4 9"7 3/4 9"8 3/4 9"9 3/4 9-10 3/4 9-11 3/4 9-12 3/4 9-13 3/4 9"14 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 3/4 10-5 SHEARON HARRIS - UNIT 1 Amendment No. 7g, 1 6
3/4. 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1.a The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either.'1)
A Keff of 0.95 or less, or (2)
A boron concentration of greater than or equal to 2000 ppm.
3.9.1.b The valves listed in Table 3'-1.shall be in their positions required by Table 3.9-1.
APPLICABILITY:
MODE 6 ~
ACTION:
a ~
With the requirements of Specification 3.9.l.a not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity
- changes, and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until K f is reduced to less than or equal to 0.95 or
.e f the boron concentration is restored to greater than or equal to 2000
- ppm, whichever is the more restrictive.
b.
With the requirements of Specification 3.9.1.b not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity
- changes, and initiate action to return the valve(s) to the position required by Table 3.9-1.
SURVEILLANCE RE UIREMENTS 4.9.1.1 The more restrictive of the two reactivity conditions of Specification 3.9.1.a shall be determined prior to.
a.
Removing or unbolting the reactor vessel
- head, and b.
Withdrawal of any control rod in excess of 3 feet from its fully inserted position within the reactor vessels 4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis to be within the limits of Specification 3.9'.a at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4.9.1.3 At least once per 31 days, verify that the valves listed in Table 3.9"1 are in their positions required by Table 3.9-1.
SHEARON HARRIS - UNIT 1 3/4 9-1 Amendment No.
16
TABLE 3.9-1 ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURING REFUELING CP&L VALVE NO.
(Ebasco Valve No.)
DESCRIPTION RE UIRED POSITION 1CS-149 (CS-D121SN)
Reactor Makeup Water to CVCS Makeup Control System Lock closed; may be opened to permit makeup to Refueling Water Storage Tank provided valves 1CS-156 and 1CS-155 are maintained closed with their main control board control switches in "shut" position, and manual valves 1CS-274, 1CS-265 and 1CS-287 are locked closed.
1CS-510 (CS-D631SN) 1CS-503 (CS-D251)
Boric Acid Batch Tank Outlet Reactor Makeup Water to Boric Acid Batch Tank Locked closed; may be opened provided the boron concentration of the boric acid batch tank > 2000 ppm and valve 1CS-503 is closed.
Lock closed, may be opened provided valve 1CS-510 is closed.
1CS"93 (CS"D51SN) 1CS-320 (CS-D641SN) 1CS-570 (CS-D575SN)
Resin Sluice to CVCS Demineralizers Boron Recycle Evaporator Feed Pump to Charging/SI Pumps CVCS Letdown to Boron Thermal Regeneration System Lock closed.
Lock closed.
Closed with main control board control switc in "shut" position, and BTRS function selector switch maintained in "off" position',
no lock required.
1CS-670 (CS-D599SN) 1CS-649 (CS-D198SN) 1CS-98 (CS-D740SN)=
Reactor Makeup Water to Boron Thermal Regeneration System Resin Sluice to BTRS Demineralizers Lock closed.
Lock closed.
Boron Thermal Regeneration System Bypass Opened with main control board control switch maintained in "open" position',
no lock required.
REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY:
MODE 6.
ACTION:
a.
With one or more of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes'.
With both of the above required monitors inoperable or not operating, in addition to Action a. above, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:
a.
A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE A1 TERATIONS, and c.
An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.
SHEARON HARRIS - UNIT 1 3/4 9-3 Amendment No. 16