ML18010A746
| ML18010A746 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/02/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18010A747 | List: |
| References | |
| NPF-63-A-029 NUDOCS 9209100154 | |
| Download: ML18010A746 (6) | |
Text
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4 UNITEDSTATES CLEAR REGULATORY COMMISSI WASHINGTON, D. C. 20555 CAROLINA POWER 5 LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
29 License No.
NPF-63 2.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 8 Light Company, (the licensee),
dated February 27,
- 1992, 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 will 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 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; 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.
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:
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I 3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 29, are hereby incorporated into this license.
Carolina Power 5 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Chayges to the Technical Specifications Date of Issuance:
September 2,
1992
TTACHMENT TO LICENSE AMENDMENT NO.
29 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 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 3/4 7-4 3/4 7-5 B 3/4 7-2 Insert Pa es 3/4 7-4 3/4 7-5 8 3/4 7-2
UXI ARY E
DW ER SYSTE LI ITING COND TION FOR OPE TIO 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two motor-driven auxiliary feedwater
- pumps, each capable of being powered from separate emergency buses, and b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With two auxiliary feedwater pumps inoperable, 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
S VEIL CE E U EME 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1.
Demonstrating that each motor-driven pump satisfies performance requirements by either:
a)
Verifying each pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1514 psid at a recirculation flow of greater than or equal to 50 gpm (25 KPPH), or b)
Verifying each pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1259 psid at a flow rate of greater than or equal to 430 gpm (215 KPPH).
SHEARON HARRIS - UNIT 1 3/4 7-4 Amendment No.
ZZ> 29
0 UXILIARYFEEDWATER SYST SURVEILLANCE RE UIREMENTS Continued 2.
Demonstrating that the steam turbine - driven pump satisfies performance requirements by either:
NOTE:
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
a)
Verifying the pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1433 psid at a recirculation flow of greater than or equal to 90 gpm (45 KPPH) when the secondary steam supply pressure is greater than 210 psig, or b)
Verifying the pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1400 psid at a flow rate of greater than or equal to 430 gpm (215 KPPH) when the secondary steam supply pressure is greater than 280 psig.
3.
Verifying by flow or position check that each valve (manual, power-operated, or automatic) in the flow path that is not locked,
- sealed, or otherwise secured in position is in its correct position; and 4.
Verifying that the isolation valves in the suction line from the CST are locked open.
b.
At least once per 18 months during shutdown by:
Verifying that each motor-driven auxiliary feedwater pump starts automatically, as designed,,upon receipt of a test signal and that the respective'ressure control valve and motor-operated recirculation isolation valve for each motor-driven pump respond as required; 2.
Verifying that the turbine-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; and 3.
Verifying that the motor-operated auxiliary feedwater isolation valves and flow control valves close as required upon receipt of an appropriate test signal for steamline differential pressure high coincident with main steam isolation.
SHEARON HARRIS - UNIT 1 3/4 7-5 Amendment No. 29 I
ZBSZ S
ST The auxiliary feedwater pumps are capable of delivering the 430 gpm (215 KPPH) feedwater flow rate required to mitigate the most limiting design basis accidents analyzed in SHNPP FSAR Chapter 15.
The most limiting accident scenarios are the Loss of Normal Feedwater (LONF) and the Feedline Break (FLB).
The accident analyses assume the pressure in the steam generators reaches the setpoint of the lowest set steam generator safety relief valve for at least a portion of the accident duration.
Therefore, each of 'the AFW pumps (motor-driven and turbine-driven) must be capable of supplying at least 430 gpm (215 KPPH) total to at least two steam generators at a steam generator inlet pressure of 1217 psig.
The 1217 psig pressure is based on the lowest safety relief valve setting plus margin for accumulation and setting error.
Each AFW pump must be capable of supplying the full 430 gpm (215 KPPH) flow following all credible single failure scenarios.
This capacity is sufficient to ensure adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F so the Residual Heat Removal System may be placed into operation.
3 4 3
CONDENSATE STORAGE The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with. steam discharge to the atmosphere concurrent with total loss-of-offsite power.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics, and the value has also been adjusted in a manner similar to that for the RWST and BAT, as discussed on page B 3/4 1-3.
3 4 4
SPEC IC ACTIVI The limitations on Secondary Coolant System specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose also includes the effects of a coincident 1 gpm reactor-to-secondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions, used in the safety analyses.
3 4 5
IN STEAM LINE SO ON VALVES The OPERABILITY of >he main.steam line isolation valves ensures that no more
-:than o5e steam generator will;51%w 4own in the event of"a steam line rupture.
This restiiction is requiied to:
(1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analyses.
3 4 2
S EAM GENERATO PRESSURE TEMPERA E LI I 0
The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70'F and 200 psig are based on a steam generator RT~z of 60'F and are sufficient to prevent brittle fracture.
SHEARON HARRIS - UNIT 1 B 3/4 7-2 Amendment No.
29