ML17158C309
| ML17158C309 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/23/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Allegheny Electric Cooperative, Pennsylvania Power & Light Co |
| Shared Package | |
| ML17158C310 | List: |
| References | |
| NPF-14-A-169 NUDOCS 9709300261 | |
| Download: ML17158C309 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 205554001 PENNSYL A IA POWER 8( LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.
OOOKET KO. 55-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.169 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated September 15,
- 1997, as supplemented by letter dated September 16,
- 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in =conformity with the'pplication, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; 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.
970'7300261 9709'23 PDR ADGCK OS000387 P
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2) Tech ical S ecifications and Environmental Protection Pla The Technical Specifications contained in Appendix A, as revised through Amendment No. 169 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PPLL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented on the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
n F. Stolz, Director P o ect Directorate I-Dsvision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
$epzembex; Q3
$997
TTACHMENT 0 LICENSE AMENDMENT NO. 169 FACI ITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating'he area of change.
REMDVE 3/4 4-5 3/4 3-71 INSERT 3/4 4-5 3/4 3-71
lh CO QCm zz I
C INSTRUMENT 1.
Reactor Vessel Steam Dome Pressure 2.
Suppression Chamber Water Level REQUIRED NUMBER OF CHANNELS MINIMUM CHANNELS OPERABLE TABLE3.3.7.6-1 ACCIDENTMONITORINGINSTRUMENTATION ACTION 80 80 80 APPLICABLE OPERATIONAL CONDITION 1,2 1.2 1.2 4.
Suppression Chamber Water Temperature 5.
Suppression Chamber Air Temperature 6.
Prima Containment Pressure 7.
DrywellTemperature 8.
Drywell Gaseous Analyzer
- a. Oxygen
- b. Hydrogen 9.
Safety/Relief Valve Position Indicators 10.
Containment High Radiation 11.
Noble gas monitors"
- a. Reactor Bldg. Vent
- b. SGTS Vent
- c. Turbine Bldg. Vent 12.
Neutron Flux 8,6 locations 2/range 1/valve*
6,1/location 1/range 1/valve*
80 80 80 80 80 82 80 81 81 81 81 80 1,2 1,2 1,2 1.2 1,2 1,2 1,2 1.2 1,2and***
1, 2 and ***
1.2 1.2 2
O.
2 z0
'61
- Acoustic monitor. Compliance with these requirements for the "S" SRV acoustic monitor is not required for the period beginning September 12, 1997, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the 10th refueling and inspection outage.
- Mid-range and high-range channels
- When moving irradiated fuel in the secondary containment.
0 See Special Test Exception 3.10.1
REACTOR COOLANTSYSTEM i 3/4.4.2 SAFETY/RELIEF VALVES LIMITINGCONDITION FOR OPERATION 3.4.2 The safety valve function of at feast 12 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve function liftsettings: * **
2 safety-relief valves @1175 psig t 1%
6 safety-relief valves @1195 psig t 1%
8 safety-relief valves @1205 psig a 1%
APPLICABILITY: OPERATIONALCONDITIONS 1, 2 and 3.
ACTION:
a.
With the safety valve function of one or more of the above required safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 105'F, close the stuck open relief valve(s); if unable to close the open valve(s) within 2 minutes or if suppression pool water temperature is 105'F or greater, place the reactor mode switch in the Shutdown position.
c.
With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN"within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCEREQUIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE with the setpoint verified to be 0.25 of the full open noise level by performance of a:
a.
CHANNELFUNCTIONALTEST at least once per 31 days, and a b.
Calibration in accordance with procedures prepared in conjunction with its manufacturer's recommendations at least once per 1S months.
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpolnts until the next refueling.
¹ Compliance with these requirements for the "S" SRV acoustic monitor ls not required for the period beginning September 12, 1997, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the 10th refueling and inspection outage.
¹¹ The provision of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
SUSQUEHANNA - UNIT 1 3/4 4-5 Amendment No. 95, Qg, 169