ML17156A593
| ML17156A593 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/03/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A594 | List: |
| References | |
| NUDOCS 8805180389 | |
| Download: ML17156A593 (16) | |
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0O UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSOUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
8O 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 5
Liqht Company, dated December 15, 1987 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 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 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:
(7)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
8O and the Environmental Protection Plar contained in Appendix 8, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8805180389 880503 PDR ADOCN,- 05000387; P
3.
This license amendment is effective upon issuance, and is to be implemented prior to Unit 2 startup (currently scheduled for May, 1988) following second refueling and inspection outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1988
/S/
Malter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Previously concurred*
P DI-2/PM*
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3.
This license amendment is effective upon issuance, and is to be implemented prior to Unit 2 startup (currently scheduled for May, 1988) following second refueling and inspection outage.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes
?o the Technical Specifications Date of Issuance:
May 3, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.
8O FACILITY OPERATING LICENSE NO.
NPF-14 OOCKET 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 the area of change.
The overleaf page is provided to maintain document completeness.*
REMOVE 3/4 3-81 3/4 3-82 3/4 3-83 3/4 3-84 INSERT 3/4 3-81*
3/4 3-82 3/4 3-83 3/4 3-84
INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.i.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table
- 3. 3.7. 10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification
- 3. 11. l. 1 are not exceeded.
The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters described in the Offsite Dose Calculation Manual (ODCM).
APPLICABILITY: At al 1 times.
ACTION:
a.
b.
C.
With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7. 10-1.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain why this inoperability was not corrected in a timely manner in the'ext Semiannual Radioactive Effluent Release Report.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE
- CHECK, CHANNEI CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.
4 SUS(jUEHANNA UNIT 1 3/4 3-81 Amendment No.
26
TABLE 3. 3.7.10-1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 5
1.
GROSS RADIOACTIVITYMONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line~
2.
GROSS RADIOACTIVITYMONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE MINIMUM CHANNELS OPERABLE ACTION 100 a.
Service Water System Effluent Line 101 b.
RHR Service Water System Effluent Line 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line b.
Cooling Tower Blowdown"*
1/loop 101 102 102 g
- OPERABILITY of this monitor includes the proper functioning of the discharge valve interlocks (sample pump low flow, high radiation alarm, and radiation monitor failure).
- OPERABILITYof this device includes the proper functioning of the Liquid Radwaste Effluent Line discharge valve interlock (i.e. cooling tower blowdown low flow).
TABLE 3.3.7. 10-1 (Continued ACTION 100 -
Mith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
a.
If effluent releases are necessary, they may continue for up, to 14 days provided that prior to initiating a release:
l.
At least two independent samples are analyzed in accordance with Specification 4. 11. l.l. 1, and 2.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
b.
If effluent releases are not occurring and the cause of the inoperable channel is a discharge valve interlock in an off-normal condition or not functioning, maintain at least one isolation valve closed between each source of release and the liquid radwaste discharge valves.
ACTION 101-Mith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-~ microcurie/mL.
ACTION 102 -
Mith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
ao b.
If effluent releases are necessary, they may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump, curves generated in situ may be used to estimate flow.
If effluent releases are not occurring and the cause of the inoperable channel is the discharge valve interlock in an off-normal condition or not functioning, maintain at least one isolation valve closed between each source of release and the liquid radwaste discharge valves.
SUS(UEHANNA - UNIT 1 3/4 3-83 Amendment No.
80
TABLE 4.3.7.10-1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.
GROSS RADIOACTIVITYMONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION R(3)
CHANNEL FUNCTIONAL TEST aci)
I
~
2.
GROSS RADIOACTIVITYMONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Water System Effluent Line b.
RHR Service Water System Effluent Line 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line b.
Cooling Tower Blowdown D(4)
D(4)
N.A.
N.A.
R(3)
R(3)
S(2) e(2)
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No.
NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8t Liqht Company, dated December 15, 1987 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; 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,orth in 10 CFR Chapter 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 F..
The issuance nf this amendment is in accordance with 10 CFR Part 51 of the Commission's requlations and all applicable requirements have been satisfied.
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-22 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.
46 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective upon issuance, and is to be implemented prior to Unit 2 startup (currently scheduled for May, 1988) following second refueling and inspection outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Charoes to the Technical Specifications Date of Issuance:
May 3, 1988
/S/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Previously concurred*
PDI gPgLA P0 I-2/PM*
M('HY/en MThadani:mr
- -'/
'( /88 04/15/88 OGC*
APH 04/25/88 PDI-2/D*
WButler
$ /P/88
3.
This license amendment is effective upon issuance, and is to be implemented prior to Unit 2 startup (currently scheduled for Hay, 1988) following second refueling and inspection outage.
FOR THE NUCLEAR REGULATORY COMMISSION Malter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.
46 FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 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.
The overleaf page is provided to maintain documen't completeness.*
REMOVE 3/4 3-83 3/4 3-84 3/4 3-85 3/4 3-86 INSERT 3/4 3-83 3/4 3-84 3/4 3-85 3/4 3-86*
TABLE 3.3.7.10-1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT 1.. GROSS RADIOACTIVITYMONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line*
2.
GROSS RADIOACTIVITYMONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Mater System Effluent Line b.
RHR Service Mater System Effluent Line 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line b.
Cooling Tower Blowdown**
MINIMUM CHANNELS OPERABLE 1/loop ACTION 100 101 101 102 xoz
- OPERABILITY of this monitor includes the proper functioning of the discharge valve interlocks (sample pump low flow, high radiation alarm, and radiation monitor failure).
- OPERABILITYof this device includes the proper functioning of the Liquid Radwaste Effluent Line discharge valve interlock (i.e. cooling tower blowdown low flow).
TABLE 3.3.7.10-1 (Continued ACTION STATEMENTS ACTION 100 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
a.
If effluent releases are necessary, they may continue for up to 14 days provided that prior to initiating a release:
1.
At least two independent samples are analyzed in accordance with Specification 4. 11. l. 1. 1, and 2.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
b.
If effluent releases are not occurring and the cause of the inoperable channel is a discharge valve interlock in an off-normal condition or not functioning, maintain at least one'isolation valve closed between each source of release and the liquid radwaste discharge valves.
ACTION 101 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-~ microcurie/mL.
ACTION 102 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
b.
If effluent releases are necessary, they may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
Pump curves generated in situ may be used to estimate flow.
If effluent releases are not occurring and the cause of the inoperable channel is the discharge valve interlock in an off-normal condition or not functioning, maintain at least one isolation valve closed between each source of release and the liquid radwaste discharge valves.
SUSQUEHANNA - UNIT 2 3/4 3-84 Amendment No.
46
TABLE 4. 3. 7. 10-1 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.
GROSS RADIOACTIVITYMONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION R(3)
CHANNEL FUNCTIONAL TEST Q(1) 2.
GROSS RADIOACTIVITYMONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Water System Effluent Line b.
RHR Service Water System Effluent Line 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line b.
Cooling Tower Blowdown D(4)
D(4)
N.A.
N.A.
R(3)
R(3)
A(2) 9(2)
TABLE 4. 3. 7. 10-1 Continued TABLE NOTATION (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm/trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
l.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
SUS(UEHANNA UNIT 2 3/4 3"86