ML20148P488
| ML20148P488 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/04/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148P475 | List: |
| References | |
| NUDOCS 8804110235 | |
| Download: ML20148P488 (11) | |
Text
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UNITED STATES
+
g NUCLEAR REGULATORY COMMISSION 5
8 WASHINGTON. D. C. 20655
's,.... +,o COMMONWEALTH E0! SON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-39 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (thelicensee),datedMay 29, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The factitty will operate in conformity with the application, the provisions of the Act, and the regulations of the Comitsion; 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 comon 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 Comission's regulations and Cl 3pplicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the enclosure to this license amendment and para-graph 2.C.(2) of the Facility Operating License No. DPR-39 is hereby amended to read as follows:
P
2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.110, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective as of the dete of its issuance.
FOR THE NUCLEAR REGOLATORY COMMISSION Daniel R. Muller Director Project Directorate III-2 Division of Reactor Projects - Ill, IV, Y and Special PrJjects
Enclosure:
Changes to the Technical Specifications Date of Issuance: April 4, 1988 D
I J
i ATTACHMENT TO LICENSE AMENDMENTS AMENDHENT NO.110 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.
99 FACILITY OPERATING LICENSE NO. OPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
i REMOVE INSERT j
82 82 83 83 83a 83b 93 93 i
94 94 1
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A
1.
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.2.G. Low Temperature Overpressure Protection 4.3.2.G. Low fenperature Overpressure Protection 1.
At least one of the following low 1.
Surveillance and testing of the low temperature protection methods shall be temperature overpressure protection available:
methods shall be perfonned as follows:
a.
Two power operated relief valves a.
Each PORY shall be demonstrated as (PORVs) with a lift setting of 435 OPERABLE by:
psig shall be OPERA 8LE, or 1.
Performance of a CHANNEL FUNCTIONAL TEST on the PORY actuation channel within 31 da"s prior to entering a condition in which the PORY is required OPERA 8tE, and at least once per 31 days thereaf ter when the PORV is required OPERA 8LE.
2.
Verifying the PORY backup tir supply is charged, within 31 days prior to entering a condition in which the PCRV is required OPERA 8LE, and at least ence per 31 days thereaf ter when tfse PORY 15 required DPERABLE; 3.
Ferforimmace of a CHANNEL CALIBRAT102 on the PORV actuation channel at least once per refueling e tage.
LIMITING CONDITION FOR OPERATION SURVE!LLANCE REOUIREMENT 3.3.2.G. Low Temperature Overpressure Protection 4.3.2.G. tow Tempe iture Overpressure Protection (Continued)
(Continued) 4.
Verifying each PORV's isolation valve is open at leist once per shift when this method is being used for low temperature cverpressure protection.
b.
The Reactor Coolant System (RCS) b.
The RCS pressure shall be verified pressure shall be less than 100 to be less than '.00 psig, and psig, and the pressurizer level less pressurizer level shall be verified than 25%, or to be less than 25% a least once per shift, when this method is being used hr low temperature overpressure protection.
4 c.
The RCS is depressurized and one c.
Verifying one PORY and it's PORY and it's isolatior, valve are isolation valve are open at least open.
Once per shift, when this method is being used for low temperature overprcssure protection.
2.
A maximum of one* charging pump or safety 2.
At least four of the five pumps (charging injection pump, aligreed for injection pumps and safety injection pumps), and into the RCS, and rio accumulators shall all accumulators, shall be verified to be be OPERABLE.
incapable of injecting inte the RCS prior to entering a condition ire which they are required to be inoperable, and at leas?.
once per shif t thereaf ter wnlle they are required to be inoperable.
O Fer short durations of time during pump switchover, two charging pumps may be OPERABLE for the purpose cf maintaining seal injection flow to the reactor coolant pumps.
Amendment Nos.110. 99
~~,--.--,,n
J LIMITING CONDITION FOR OPERATION 4
SURVEILLANCE REQUIREMENT 3.3.2.G. Low Temperature Overpressure Protection (Continued) 4.3.2.G. Low Temperature Overpressure Protection (Continued) 3.
When starting a reactor coolant pump, 3.
Not applicable.
when no reactor coolant pumps are running, the temperature in the secondary side of the steam generator in the loop in which the reactor coolant pump is to be started shall be less than 50*F higher than the RCS temp!rature.
APPLICA81LITY:
Mode 4 when the temperature of any RCS cold leg is less than or equal to 250*F, MODE 5 and MODE 6 with the reactor vessel head on.
ACTION:
a.
With one PORY inoperable, restore the inoperable PORY to OPERA 8LE status within 7 days, or within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either; Depressurize the RCS to less than 100 psig and lower pressurizer !evel to less than 25%, or Depressurize the RCS and open at least one PORY and it's block valve.
09200/09210 83a
LIMITING CONOITION FOR OPERATION SURVEILLAMCE REI)UIREMENT 3.3.2.G. Low Temperature Overpressure Protection 4.3.2.G. Low Temperature Overpressure Protection (Continued)
(Continued) b.
With both PORY's inoperable, within the next 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> either; Depressurize the RCS to less than 100 psig and lower pressurizer level to less than 25%, or Depressurize the RCS and open at least one PORV and it's block valve.
c.
In the event that a PORY is used to mitigate an RCS pressure transient, a SPECIAL REPORT shall be prepared and submitted to the Coguaission pursuant to Specification 6.6.3.8.
The report shall include the following infonmation:
1.
A description of the circumstances initiating the transient, and 2.
The effect of the PORV's on the transiest, and 3.
The corrective action necessary to prevent reoccurrence.
d.
The provisions of Specification 3.0.4 are not applicable.
09200/09210 l 83h n
10, 99
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Bas s:
Low Temperature Overpressure Protection i
3.2.2.G There are 3 means of protecting the RCS from overpressurization by a pressure transient at low temperatures (below 250*F). The first type of protection is ensured by the speration and surveillance of the power 4.2.2.G operated relief valves with a lif t setting of 435 psig.
i A single power operated relief valve (PORV) will relieve a pressure transient caused by 1) a mass addition into a solid RCS from a charging pump or 2) a heat input based on a reactor coolant pump being started in an idle RCS and circulating water into a steam generator whose temperature is 50'F greater than the RCS temperature.
(1) t The second means of pretection is ensured by a P0tV being open.
It will have the same relieving capab111tles as mentioned above.
The third means of protection limits the pressurizer level to 25% and the g.ressurizer pressure to 100 psig.
A pressure transient caused by the inadvertent mass addition from a charging pump running for 10 minutes will be relieved by the large gas volume and low pressure present in the pressurizer as mentioned above.
l Maintaini g the pressurizer level below 25% will als,o make the h1 pressurizer level deviation alara eva11able to the operator during a mass addition accident.
t In the event that a single PORV becomes inoperable, the repair period of 7 days is based on allowing sufficient time to effect repairs using safe and proper procedures and upon the operability of the redundant PORV. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period to reach the restrictive conditions in the~ pressurizer provides sufficient time to meet these conditions.
In the event that both PORV's becom= inoperable, the condition is more serious than for a single inoperable i
PORV, therefore every attempt should be made to depressurize the RCS in a controlled manner as rapidly as possible.
The 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> time period to reach the restrictive conditions in the pressurizer represents a I
reasonable amount of time to meet these cocd1tions under an expedited circumstance.
The Low Temperatur2 Overpressure Protection System must be tested on a periodic bases consistent with the need for its use.
A CNANNEL FUNCTIONAL TEST shall be performed prior to enabling the overpressure protection system during cooldoun and startup.
4 The limitations and surveillance requirements on the ECCS equipment provides assurance that a mass addition i
i pressure transient can be relieved by the operation of a single PORV or the limiting conditions placed on the pressertzer.
The restrictions for startup of a RCP limits the heat input accident to within the r?lleving capabilities of I
3 a single PORV.
}
(1)
Pressure Mitigating Systems Transient Analysis Results July 1977 Westinghouse Owners Group on RCS j
Overpressurization.
1 1
! 09200/09210 94
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UNITED STATES I
NUCLEAR REGULATORY COMMISSION e
b WASHING TON, 0, C. 20666
- %,,,, /
COR40NWEALTH EDISON COMPANY f
l DOCKET NO. 50-304 t
IION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
\\
Amendment No. 99 License No. DPR-48 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (thelicensee),datedMay 29, 1987, and supplemented l
March 3, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in confonnity with the applicction, the provisions of the Act, and the regulaticas of the Comission; f
C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (11) that cuch activities will be condu:ted i
in compliance with the Comission's regulations; D.
The issuance of this amendrent will net be inimical to the co r n defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of t
the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the er. closure to this license atendrent and para-i graph 2.C.(2) of the Fccility Operating License No. DPR-48 is hereby i
amended to read as follows:
j s
1 J~
2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This arnendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATOP.Y COMMISSION Daniel R. Muller, Director Project Directorate III-?
Division of Reactor Projwets - III, IV, Y and Special Projects l
Enclosure:
4 Changes to the Technical Specifications Date of Issuance:
April 4, 1988 l
l J