ML20151H232
| ML20151H232 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/18/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151H236 | List: |
| References | |
| NUDOCS 8808010195 | |
| Download: ML20151H232 (12) | |
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GA5 COMPANY DELMARVA PCWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY OOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE AmenC 5t No. 133 License No. OPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
lhe application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 20, 1987 as supplemented on February 26, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisiens of the Act, and the rules and regulations of the Comission; L
C.
There is reasonable assurance (1) that the activities authorized by this amendfrent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 0.
The issuance of this amendment will not be inimical to the comon defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been j
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, I
and paragraph 2.C(2) of Facility Operating License No. OPR-44 is hereby amended to read as follows:
5 8808010195 080710 PDR ADOCK 05000277 P
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(2)
Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133, are hereby incorporated in the
-l license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION i
/s/
l Walter R. Butler Director Project Directorate I-2 i
Division of Reactor Projects I/II i
Attachment' Changes to the Technical Specifications
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Date of Issuance: July 18, 1988 i
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Technical Specifications The Technical Specifications contained in Appendices A and B as revised +.hrough Amendecnt No. 133, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Teebrical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COWISSION c2 Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical t
Specifications Date of Issuance: July 18, 1988 J
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ATTACPMENT TO LICENSE AMENDNENT NO.133 FACILITY OPEPATING LICENSE NO. DPR-44 DOCXET NO. 50-277 Replace the following pag'es of the Appendix A Technical Specifications with 1
the enclosed pages.
The revised areas are indicated by rarginal lines.
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PBAPS Unit 2
- 1. 0 DEFINITIONS (Cont'd)
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to thu sensor to actuate the circuit in question, i
Site Boundary - That line beyond which the land is not owned, leased or other-wise controlled by licensee.
Source Check - A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure j'
are bypassed, the reactor protection system is energized with IRM neutron i
monitoring system trip, the APRM 15% high flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the Startup/ Hot Standby position of the mode switch.
Surveillance Frequency - Periodic surveillance tests, chec.s. calibrations, and examinations shall be performed within the specified surveillance intervals.
The operating cycle interval as pertaining to instrument ant,lectrical surv-eillance shall not exceed 18 months.
These specified time intervals may be exceeded by 25%.
In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
Surveillance tests are not required on systems or parts of the systems that are not required to be operable or are tripped.
If tests are missed on parts not required to be operable or are tripped, then they shall be performed pri;r to returning the system to an operable status.
A surveillance test of the diesel generators, that requires a plant outage, may be deferred beyond the calculated due date until the next refueling outage, provided the equipment has been similarly tested and meets the surveillance requirement for the other unit. When a test is deferred under this provision, the next surveillance interval shall commence at the end of the original specified interval.
Transition Boilina - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being com-plately stable.
Trio Systee - A trip system means an arrangement of instrument
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channel trip signals and auxiliary equipeent required to initiate i
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Amendment No, Mf".Mfi133 ;
PBAPS Un i t 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.B golantChemistry
- 4. 6. 8 Coolant Chemistry 1.
Coolant Activity Limits 1.
During the equilibrium power coeration the sampling frequencies Whenever the reactor is critical, of Table I shall apply.
Additional the limits en activity concentra-samples shall be taken whenever the tions in the reactor coolant shall reactor coolant concentration not exceed the equilibrium value exceeds ten percent of the equili-of 0.2 ue/gm of dose equivalent brium value in 3.6.B.1 and one or
- I-131.
more of the following conditions are met:
l This limit may be exceeded for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
During this a.
During startup i
activity transient the iodine b.
Following a si i
powerchange**gnificant b
concentration shall not exceed the
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equilibrium value of 4.0 uc/ gram c.
Following*asignificant l
of dose equivalent I-131 whenever increase in the r
l the reactor is critical.
The reac-equilibrium offgas level tor shall not be operated under at the steam air ejector this exception from the equilibrium over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
activity limits for more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month Additional samples will also be period. If the iodine concentration obtained whenever the equilibrium in the coolant exceeds 0.2 uc/ gram iodine concentration limit of 2
l dose equivalent I-131 for more than 3.6.B.1 is exceeded.
48 continuous hou-s or is greater than 4.0 uc/gm dose equivalent I-131, The additional coolant liquid the reactor shall be shutdown, and samples shall be taken and analyzed l
the steam line isolation valves shall isotopically for dose equivalent l
be closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I-131 at 4-hour intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until two succes-
"That concentration I-131 which sivs samples indicate a decreasing alone would produce the same trend below the limiting value of thyroid dose as the quantity and 0.2 uc/gm dose equivalent I-131.
isotopic mixture actually present.
However, at least 3 consecutive
- The following definition will samples shall be taken in all apply to the term significant cases.
increase in offgas level, a) At release rates less than or equal to 75,000 uc/sec, sig-nificant increase means an increase of 10,000 uc/sec from the previous corresponding power level steady state release rate within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b) At release rates greater than 75,000 uc/sec, significant
- For the purpose of this section increase means an increase of on sampling frequency a signifi-15% from the previous corres-cant power change is defined as ponding power level steady a change exceeding 15% of rated state release rate within 1 hr.
power in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Amendment No. 4Hr;'133
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UNITED $TATES e
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NUCLEAR REGULATORY COMMISSIC
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PHILADELPHIA ELECTRIC COMPANY PUBLIC 5ERVICE ELECTRIC AND GA5 COMPANY DELMADVA DOWER AND LIGHT CO*'PANY ATLANTIC CITY ELECTRIC COMPANY l
00CXET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMEh0 MENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. OPR-56 1.
The Nuclear Regulatory Coisnission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 20, 1987 as supplemented on February 26, 1988, complies with the standards and reouirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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, andparagraph2.C(2)ofFacilityOperatingLicenseNo.DPR-56ishertby l
amended to read as follows:
i
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! i (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Spectiications.
3, This license amendment is effective as of its date of issuance, f
FOR TilE NUCLEAR REGULATORY COMMISSION j
t
/s/
Walter R. Butler, Director i
Project Directorate I-2 l
Division of Reactor Projects 1/11 l
Attachment
- Changes to the Technical Specifications l
Date of Issuance: July 18, 1988 l
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(2)
Technical Specifications The Technical Spec'fications contained in Appendices A and B, as j
revised thrcugh Amentent No.136, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the l
Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
I Walter R. Butler. Director i
Project Directorate I-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical l
Specifications Date of Issuance: July 18, 1988 i
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ATTACHMENT TO LICENSE AMENMENT NO.136 FACILITY OPERATING LICENSE NO. OPR-56 DOCKET NC. 50-278 l
Replace the following pages of the Apperdix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
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8 145 145 i
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PBAPS Unit 3
- 1. 0 OEFINITIONS (Cont'd)
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
5.te Boundary - That line beyond which the land is not owned, leased or other-wise controlled by licensee.
Source Check - A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
Startup/ Hot Standby Mode - In this mode the reactor protection scram trips, initiated by condenser lov vacuum and main steam line isolation valve closure are bypassed, the reactor protection system is energized with IRM neutron monitoring system trip, the APRM 15% high flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the Startup/ Hot Standby position of the mode switch.
Surveillance Frequency - Periodic surveillance tests, checks calibrations,and eta 3Tnations shall be performed within the specified surveillance intervals.
The operating cycle interval as pertaining to instrument and electrical surv-eillance shall not e u sed 18 months.
These specified time intervals may be exceeded by 25%.
- n cases where the elapsed interval has exceeded 100% of the specified interval, the next survaillance interval shall commence at the end of the original specified intervai.
Surveillance tests are not required on systems or parts of the systems that are not reouired to be operable or are tripped.
If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system tn an operable status.
A surveillance test of the diesel generators, that requires a plant outage, may be deferred beyond the calculated due dste until the next refueling outage, provided the equipment has been similarly tested and meets the surveillance requirement for the other unit.
When a test is deferred under this provisica, the next surveillance interval shall commence at the end of the original specified interval.
Transi_ tion Boilina - Transition boiling means the boiling regime between nucleate and film boiling.
Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being com-pletely stable.
Trio System - A trip system means an arrangement of instrument channel tr1D Sionals and auxiliary equipment requirf.d to initiate I
l Amnda,it No. HC,.Ht; 136 l
DSAps Unit 3 LXMIT8NG CON 0!Tf0NS FOR OPERAT!0N SURVEXLLANCE REQUIREMENTS 3.6.B Coolant Chemistry 4.6.8 Coolant Chemistry 1.
Coolant Activity Limits 1.
During the eauilibrium power operation the sampling frequencies Whenever the reactor is critical, of Table I shall Apply.
Additional the limits on activity concentra-samples shall be taken whenever the tiens in the reactor coolant shall reactor coolant concentra; ion not exceed the equilibrium value exceeds ten percent of the equili-of 0.2 uc/gm of dose equivalent brium value in 3.6.B.1 and one or "I-131.
more of the foilowing conditions are met:
This limit may be exceeded for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
During this a.
During startup activity transient the iodine b.
Following a significant l
concentration shall not exceed the power change ***
equilibrium value of 4.0 uc/ gram c.
Following a significant of dose equivalent I-131 whenever increase ** in the the reactor is critical.
The reac-equilibrium offgas level tor shall not be operated under at the steam air ejector this exception from the equilibrium over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
activity limits for more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month Additional samples will also be period. If the iodine concentration obtained whenever the equilibrium in the coolant exceeds 0.2 uc/ gram iodine concentration limit of dose equivalent I-131 for more than 3.6.8.1 is exceeded.
48 continuous hours or is greater than 4.0 ue/gm dose equivalent I-131, The additional coolant liquid the reactor shall be shutdown, and samples shall be taken and analyzed 1
the steam line isolation valves shall isotopically for dose equivalent I
be closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I-131 at 4-hour intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until two succes-
"That concentration 1-131 which sive samples indicate a decreasing alone would produce the same trend below the limiting value of thyroid dose as the quantity and 0.2 uc/gm dose equivalent I-131.
isotopic mixture actually present.
However, at least 3 consecutive
- The following definition will samples shall be taken in all apply to the term significant cases.
increase in offgas level, a) At release rates less than or equal to 75,000 uc/sec, sig-nificant increase means an increase of 10,000 uc/sec from the previous corresponding pener level steady state release rate within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
j b) At release rates greater than j
75,000 ue/sec, significant
- For the purpose of this section increase means an increase of on sampling frequency a signifi-154 from the previous corres-cant power change is defined as
.1 pending power level steady a change exceeding 15% of rated state release, rate within 1 br.
power in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Amendment No M 136
-145-
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