ML20235F069
| ML20235F069 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/10/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F071 | List: |
| References | |
| NUDOCS 8902220394 | |
| Download: ML20235F069 (15) | |
Text
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- UNITED STATES '
, NUCLEAR REGULATORY COMMISSION n
3 E
WASHINGTON, D. C. 20688 o
PHILADELPHIA ELECTRIC. COMPANY PUBLIC SERVICE ~ ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC' COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No..:138 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for am'endment by Philadelphia Electric Company, et al. (the licensee) dated March 21, 1988 as' supplemented on September.23, 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 provisions of the Act, and the rules and regulations of the Commission';
- q C.
There is reasonable assurance (1) that the activities authorized by I
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 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 satisfied..
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, j
and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8902220394 890210 gDR ADOCK 05000277 PDC s
e i
(2)
Technical-Specifications 4
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 138, are hereby incorporated in the license.- PEC0 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 COMMISSION
/s/
Walter R. Butler, Director Project' Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 10, 1989 i
1 ppfRM OGC PDI-2/D I
Martin:tr JMoore WButler
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t/2a/88 01 /30 /88
/q/88 e < / n/89
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised-through Amendment No. 138, are hereby incorporated in the 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 COMMISSION Walter R. Rutler, Director Proiect Directorate I-2 Division of Reactor Pro,iects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 10, 1989 me 4
}
4 ATTACHMENT TO LICENSE AMENDMENT NO.13g FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 31 31 148 148 1
I i
I
Unit 2 PBAPS
- 1. 2 BASES The reactor coolant system integrity is an important barrier in the prevention of uncontrolled release of fission products.
It is essential that the integrity of this system be protected by establishing a pressure limit to be observed for all operating conditions and whenever there is-irradiated fuel in the reactor vessel.
The pressure safety limit of 1325 psig as measured by the vessel steam space pressure indicator assures not exceeding 1375 psig at the lowest elevation of the reactor coolant system.
The 1375 psig value is derived from the limiting design pressures of the reactor pressure vessel (1250 psig at 575 degrees F) and recirculation system piping (suction piping:
1250 psig at 575 degrees F).
The pressure safety limit is set in l
accordance with the ASME Boiler and Pressure Vessel Code Section III to i
limit the maximum pressure to less then 110% of the design pressures for 1
the reactor vessel (110% x 1250 = 1375 psig) and the recirculation system piping (suction:
110% x 1250 = 1375 psig.).
A safety limit is applied to the Residual Heat Removal System (RHRS) when it is operating in the shutdown cooling mode.
At this time it is included in the reactor coolant system.
f l
. Amendment No.I/.138
i Unit 2 1
PBAPS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps 4.6.E Jet Pumps 1.
Whenever the reactor is in 1.
Whenever there is recirculation the startup or run modes, flow with the reactor in the all jet pumps shall be startup or run modes, jet operable.
If it is determined pump operability shall be that a jet pump is inoperable, checked daily by verifying an orderly shutdown shall be that the following initiated and the reactor shall conditions do not occur be in a Cold Shutdown within simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Flow indications from each of a)
The two recirculation loops have the 20 jet pumps during two.
a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single loop operation operated at the same speed.
shall be verified prior to initiation of reactor startup b)
The indicated value of core flow from a cold shutdown condition.
rate varies from the value derived from loop flow measure-3.
The indicated core flow is the ments by more than 10%.
sum of the flow indication from each of the 20 jet pumps.
Flow c)
During two loop operation, the indication from no more than one diffuser to lower plenum differ-jet pump shall be unavailable ential pressure reading on an during two loop operation.
If individual jet pump varies from two or more jet pump flow indi-the mean of all jet pump differ-cation failures occur during two ential pressures by more than 10%.
loop op'eration, an orderly shut-down shall be initiated within d)
During single loop operation, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the reactor shall be diffuser to lower plenum differ-in cold shutdown condition within ential pressure reading on an the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
individual jet pump in the opera-l ing loop varies from the mean of 4.
During single loop operation, no all jet pump differential pres-jet pump flow indication failures sures in the operating loop by in the operating loop are permit-more than 10%.
sible.
If a jet pump flow indica-tion failure occurs during single 2.
Additionally when operating loop operation, an orderly shutdown one recirculation pump, the shall be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> diffuser to lower plenum and the reactor shall be in cold differential pressure shall be shutdown condi-tion within the follow-checked daily and the differential ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
pressure of any jet pump in the idle loop shall not vary by more than 10% from established pattern.
3.
The baseline data required to evaluate the conditions in I
specification 4.6.E.1 and 4.6.E.2 will be obtained each operating cycle.
-148-Amendment No. 26,35,78,128,138
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UNITED STATES g
E NUCLEAR REGULATORY COMMISSION n
c WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH B01 TOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. DPR-56 1.
The Nuclear Regulatory Comission (the' Comission) has found that:
'A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated March 21, 1988 as supplemented on September 23, 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 provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; j
l D.
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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. OPR-56 is hereby amended to read as follows:
1
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the 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 COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: February 10, 1989
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Technical Specifications The Technica1' Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the.
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 COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Chances to the Technical Specifications Date of Issuance: February 10, 1989 J
R
~
ATTACHMENT TO LICENSE AMENDMENT NO.140 FACILITY OPERATING LICENSE ig. DPR-56 DOCKET NO. 50-278 l'
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert
.31 31 80 80 148 148 180 180 185 185
?
Unit 3 PBAPS
- 1. 2 BASES The reactor coolant system integrity is an important barrier in the i
prevention of uncontrolled release of fission products.
It is essential that the integrity of this system be protected by establishing a pressure limit to be observed for all operating conditions and whenever there is irradiated fuel in the reactor vessel.
The pressure safety limit of 1325 psig as measured by the vessel steam space pressure indicator assures not exceeding 1375 psig at the lowest elevation of the reactor coolant system.
The 1375 psig value is derived from the limiting design pressures of the reactor pressure vessel (1250 psig at 575 degrees F) and recirculation system piping (suction piping:
1250 psig at 575 degrees F).
The pressure safety limit is set in accordance with the ASME Boiler and Pressure Vessel Code Section III to limit the maximum pressure to less than 110% of the design pressures for the reactor vessel (110% x 1250 = 1375 psig) and the recirculation system piping (suction:
110% x 1250 = 1375 psig.).
A safety limit is applied to the Residual Heat Removal System (RHRS) when it is operating in the shutdown cooling mode.
At this time it is included in the reactor coolant system.
1 Amendment No.Z 140
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Unit 3 PBAPS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.E Jet Pumps-4.6.E Jet Pumps 1.
Whenever the reactor is in 1.
Whenever there is recirculation the startup or run modes, flow with the reactor in. the all jet pumps shall be startup or run modes, jet operable.
If itLis determined pump operability shall be-that a jet pump is inoperable, checked. daily by verifying _
an orderly shutdown shall be that the following initiated and the reactor shall conditions do not occur be in a Cold Shutdown within simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Flow indications from each of a)
The two-recirculation loops have the 20 jet pumps during two a flow imbalance of 15% or loop operation or 10 jet pumps more when the pumps are during single' loop operation operated at the same speed.
shall be verified prior to initiation of reactor startup b)
The indicated value of core flow from a cold shutdown condition.
rate varies from the value derived from loop flow measure-3.
The indicated core flow is the ments by more than 10%.
sum of the flow indication from each of the 20 jet pumps.
Flow c)
During two loop operation, the indication from no more than one diffuser to lower plenum differ-jet pump shall be unavailable ential pressure reading on an during two loop operation.
If individual jet pump varies from two or more jet pump flow indi-the mean of all jet pump differ-cation failures occur during two ential pressures by more than 10%.
loop operation, an orderly shut-down shall be initiated within d)
During single loop operation, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the reactor shall be diffuser to lower plenum differ-in cold shutdown condition within ential pressure reading on an the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
individual jet pump in the opera-ing loop varies from the mean of 4.
During single loop operation, no all jet pump differential pres-jet pump flow indication failures sures in the operating loop by in the operating loop are permis-more than 10%.
sible.
If a jet pump flow indica-tion failure occurs during single 2.
Additionally when operating loop operation, an orderly shutdown one recirculation pump, the shall be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> diffuser to lower plenum and the reactor shall be in cold differential pressure shall be i
shutdown condition within the follow-checked daily and the differential ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -
pressure of any jet pump in the j
idle loop shall not vary by more than 10% from established pattern.
3.
The baseline data required to evaluate the conditions in i
specification 4.6.E.1 and f
4.6.E.2 will be obtained each operating cycle.
-148-Amendment No. -W, M, M, 4M; 140
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Unit 3' PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES 7A
.A0-2-80A; A0-2-86A MSIV (1) (2) (3) (5) (9)-
78-A0-2-80B; A0-2-86B 7C A0-2-80C; A0-2-86C 70 A0-2-800; A0-2-86D 8
M0-2-74; M0'2-77 (1) (2) (4) (5) (9) 9A MO-23-19; MO-23-20; MO-23-21 9A MO-2-38A; MO-3663 9B MO-13-21; MO-13-20; M0-13-30; M0-12-68; 9B M0-2-388; M0-3663 10 M0-13-15; M0-13-16 11 M0-23-15; MO-23-16; A0-5807*
12 MO-10-17; M0-10-18 13A M0-10-25B; M0-10-154B; SV-5222 13B M0-10-25A; MO-10-154A; SV-5221 14 M0-12-15; M0-12-18 16A MO-14-12B; MO-14-11B; SV-5224 16B MO-14-12A; MO-14 11A; SV-5225 i
18 A0-20-82; A0-20-83 19 A0-20-94;*A0-20-95 Effective upon completion of the modification authorized by i
Amendment No. 46.
l 1
-185-Amendment No.J67140
_ _ _ _ - _ _ _ _ _ _ _.