ML17139C935
| ML17139C935 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/15/1985 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139C936 | List: |
| References | |
| NUDOCS 8502250830 | |
| Download: ML17139C935 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALL GH NY L
R R
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N D CKFT N
-38 SUSQUEHANNA S TION, UNIT 1 ND ENT F
L P
R NG C
NS Amendment No.
32 License No. NPF-l4 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8 Light Company, dated September 7,
1984, 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 application, 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 o< 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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facilities in accordance with the Technical Specifications and the Environmental Protection Plan.
8502250830 850215 1
PDR ADOCK 05000387 P
3.
This amendment is effective upon start-up following the first refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
FEB 15 Q5 A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing
3.
This amendment is effective upon start-up following the first refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
FEB ~> ~
>><g1nal spy~~ b A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing D:
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ATTACHMENT TO LICENSE AMENDMENT NO.
32 F-1 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 the area of change.
REMOVE 3/4 8-23 3/4 8-24 3/4 8-27 3/4 8-28 INSERT 3/4 8-23 3/4 8-24 3/4 8-27 3/4 8-28
~
~
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS. Continued 2.'he measured response time will be compared to the manufacturer's data to insure that it is less than or equal to a value specified by the manufacturer.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional representative sample i of at least 10K of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.
Each representative sample of fuses shall include at least 10X of all fuses of that type.
The functional test shall consist of a non-destructive resistance measurement test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found inoperable during these functional testing shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these functional tests, an additional representative sample of at least 10K of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.
3.
Functionally testing each overcurrent relay listed in Table 3.8.4.1-1.
Testing of these relays shall consist of injecting a current in excess of 120X of the nominal relay initiation current and measuring the response time.
The measured response time shall be within 2 10X of the specified value.
b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer s recommendations.
SUSQUEHANNA - UNIT 1 3/4 8-23 A~~Wc&+, 32
TABLE 3.8.4.1-1 PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES CIRCUIT BREAKER FRAME LOCATION TYPE" RATING/UL a.
T e 2 Molded Case Circuit Breakers 1.
- 1B219022, HF8-M 150/30 TRIP SET POINT
~Am eres 270
RESPONSE
TIME (Milli-seconds/
~Cc1ee SYSTEMS OR E UIPMENT POWERED HVB311F031A RRP "A" DSCH VLV 2.
18237043 3.
18236052 4.
1B236023 5.
1B236011 6.
1B236033 7.
1B236021 8.
18236032 9.
18236042 10.
1B236043 11.
1B236082 12.
1B23 6102 13.
1B236053 14.
1B237072 15.
1B219023 HFB-M 150/30 HFB-M 150/30 HFB-M 150/3 HFB-M 150/30 HFB-M 150/30 HFB"M 150/30 HFB-M 150/30 HFB-M 150/30 HFB"M 150/30 HFB-M 150/30 HFB-M 150/3 HFB"M 150/5 HFB-M 150/5 HFB"M 150/10 270 215 18 250 220 175 180 150 160 150 25 80 NA NA NA NA NA NA HVB311F023A Recirc.
PP "A" Suction HVElllF009 RHR Pump Suction Shutoff HV12603 Containment Inst.
Compressor Suet.
Iso. Valve lV413A - Drywel 1 Area Unit Cooler lV414A - Drywel 1 Area Unit Cooler 1V417A - Drywel1 Area Unit Cooler lV412A - Drywel 1 Area Unit Cooler lV411A - Drywel1 Area Unit Cooler 1V416A - Drywel 1 Area Unit Cooler IV415A - Drywel 1 Area Unit Cooler HVB211F001 " Reactor Head Vent Valve HVG331F001 - Reac.
Wtr. Clean up inboard isolation HVB211F016 - Main ca Stm.
Line Drain Inboard Isolation HVB311F032A -
RRP "A" Dsch Byps,Vlv SUSQUEHANNA " UNIT 1 3/4 8-24 Amendment No. >~
TABLE 3.8.4.1-1 (Continued)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES CIRCUIT BREAKER LOCATION b.
T e 3 Molded Case Cit cuit Bt eakers'.
1B23 6103 2.
1B246033 3.
1B226103
, 4.
1B216092 5.
1B253 041 6.
1B263021 TYPE""
KB"TH KB"TH KB-TM FRAME RATING/UL 250/150 250/150 250/150 250/150 150/15 150/15
RESPONSE
TIME (Mi1 li-seconds/
~Cc les NA NA SYSTEMS OR E UIPMENT POWERED lE440C - Containment Recomb Elect. Htr. Ass'y.
lE440D - Containment Recomb Elect. Htr. Ass'y.
1E440B - Containment Recomb Elect. Htr. Ass'y.
lE440A - Containment Recomb.
Elect. Htr. Ass'y.
TBB15 Pri. Cont.
MSIV Iso.
Hoist TBB16 Pri. Cont.
MSIV Iso.
Hoist C.
2.
1A20502 3.
1A20601 4.
1A20602 50o 50D 50D
'DCircuit Breakers Tripped By Relay Overcurrent Rela s
~Te 1.
1A20501 5GD Relay Initiation Current
~Am eres
Response
Time
~Seconds 80 80 80 80 Systems or E ui ment Powered 1 P401A Reactor Recirc Pump 1 P401A Reactor Recirc Pump 1 P401B Reactor Recirc Pump 1 P401B Reactor Recirc Pump
""KB-TH - Westinghouse Type KB, Thermal-magnetic SUSQUEHANNA - UNIT 1 3/4 8-27 Amendment No. 32
ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION 3.8.4.2 The thermal overload protection of each valve shown in Table 3.8.4.2-1 shall be bypassed continuously by an OPERABLE bypass device integral with the motor starter.
APPLICABILITY:
Whenever the motor operated valve is required to be OPERABLE.
ACTION:
With thermal overload protection for one or more of the above required valves not bypassed continuously by an OPERABLE integral bypass
- device, take admin-istrative action to continuously bypass the thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the affected valve(s) inoperable and apply the appropriate ACTION statement(s) for the affected system(s).
SURVEILLANCE RE UIREMENTS 4.8.4.2. 1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously by an OPERABLE integral bypass device by verifying that the thermal overload protection is bypassed:
a:
At least once per 18,months, and b.
Following maintenance on the motor starter.
4.8.4.2.2 The thermal overload protection shall be verified to be bypassed following activities during which the thermal overload protection was temporarily placed in force.
SUSQUEHANNA " UNIT 1
, 3/4 8-28 Amendment No. 2.g