ML20151E048
| ML20151E048 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/14/1988 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151E051 | List: |
| References | |
| NUDOCS 8807250342 | |
| Download: ML20151E048 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHINGTO N, D. C. 20555
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
DOCKET N0. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 License No. NPF-58 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated July 12, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (1) that the activities authorized by l
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 l
defense and security or to the health and safety of the public; and 1
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 Ts,.iical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
88')7250342 000714 PDR ADOCK 05000440 P
PNU
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Tlan contained in Appendix B, as revised through Amendment No.14 are hereby inenroorated into this license. The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment was effective on July 12, 1988.
FOR THE NUCLEAR REGULATORY COMMISSION
><l9 W Gary H. Holahan, Assistant Director Region III and V Reactors Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 14, 1988
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ATTACHMENT TO LICENSE AMENDMENT N0.14 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET N0. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain' document completeness.
Remove Insert 3/4 6-21 3/4 6-21 B 3/4 6 4 B 3/4 6-4 l
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CONTAINMENT SYSTEMS DRYWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OIERATION 3.6.2.6 Drywell average air temperature shall not er.ceed 145*F.
l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With the drywell average air temperature greater than 145"F, retuce the l
average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.6 The drywell average air temperature shall be the arithmetical average
- of the temperatures at the following elevations # and shall be determined to be within the limit at ? east once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Elevation Azimuth a.
653'-8" 315, 220', 135*. 34*
b.
634'-0" - 640'-0" 340', 308', 215, 145,
30, 20' c.
604'-6" - 609'-8" 310, 308, 253', 212,
150*, 140, 80'
- At least one reading from each elevation for an arithmetical average.
- The temperature at each elevation shall be the arithmetical average of the temperatures obtained from all available instruments at that elevation.
PERRY - UNIT 1 3/4 6-21 Amendment No. 6,14
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T CONTAINMENT SYSTEMS 314.6.3 DEPRESSURIZATION SYSTEMS SUPPRESSION P0OL LIMITING CONDITION FOR OPERATION 3.6.3.1 The suppression pool shall be OPERABLE with the pool water:
3 and 118,548 ft3 equivalent to a level a.
Volume between 115,612 ft between 18'0" and 18'6", and a b.
Maximum average temperature of 90'F except that the maximum average temperature may be pamitted to increase to:
3 1.
105*F during testing which adds heat to the suppression pool.
2.
110*F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
3.
120'F :ith the mair, steam line isolation valves closed following a scram.
APPL NABILITY-OPERATIONAL CONDIT10hs 1, 2 and 3.
ACTION:
a.
With the suppression pool water level outside the above 1%its, restore the water level to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the suppression pool average water temperature greater than 90*F, restore the average temperature to less than or equal to 90*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as pemitted above:
1.
With the suppression pool average water temperature grea*.er than 105'F during iesting which adds heat to the suppression pool, stop al' testing which adds heat to the suppression pool and
'e average temperature to less than 90 F within rester i
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ir be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With the suppression pool average water temperature greater inan:
a) 90*F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and THERMAL NWER greater than 1% of RATED THERMAL POWER, be in at least HOT SHUTDOWN
- ! S within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 WN.,
hours.
E b) 110*F, place the reactno mode switch in the Shutdown
?
- v. n position and operate at least one residual heat removal loop in the suppression pool cooling mode.
PERRY - UNIT 1 3/4 G-2?
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CONTAIM4ENT SYSTEMS BASES DRYWELL AND CONTAIW4ENT PURGE SYSTEM (Continued) i Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of rollient material seal degradation and will allow the opportunity for repair befc.e gross leakage failure develops.
The 0.60 L, leakage limit shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously deterwined total for all valves and
. penetrations subject to Type B and C tests.
3/4.6.1.9 FEiDWATER LEAKAGE CONTROL SYSTEM The OPERA 8ILITY of the feedwater leakage control system is required to meet the restrictions on overall containment leak rate assumed in the accident analyses.
3/4.6.2 DRYWELL 3/4.6.2.1 DRYWELL INiEGRITY Drywell integrity ensures that the steam released for the full spectrum of drywell pipe breaks is condensed inside the primary containment either by the suppression pool or by containment spray.
By utilizing the suppression pool as a heat sink, energy released to the containment is minimized and the severity of the transient is reduced.
3/4.6.2.2 ORYWELL BYPASS LEAKAGE The limitation on drynell bypass leakage rate is based on having contain-ment spray OPERABLE.
It ensures that the maximum leakage which could bypass the suppression pool during an accident would not result in the containment exceeding its design pressure of 15.0 psig.
The integrated drywell leakage value is limited to 10% of the design drywell leakage rate.
The limiting case accident is a very small reactor coolant system break which will not automatically result in a reactor depressurization. Tne long term differential pressure created between the drywell and containment will result in a significant pressure buihtup in the containment due to this bypass leakage.
3/4.6.2.3 ORYWELL AIR LOCK The limitations on closure for the drywell air lock is required to meet the restrictions on DRWELL INTEGRITY and the drywell leakage rate given in Specifications 3.6.2.1 and 3.6.2.2.
The specification makes allowances for the fact that there may be long periods of time when the air lock will be in a closed and secured position during reactor operation. Only one closed door in the air lock is required to maintain the integrity of the drywell.
The air supply to the drywell air lock and seal system is the service and iastrument air system. This eystem censists of two 100% capacity sir compressors ger gab, and can u crost conucted.
This system is redundant and e'xtremely aliable and provir.as systas pressure indicaticn in the control room.
PERRY - UNIT 1 8 3/4 6'3
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. CONTAINMENT SYSTEMS BASES 3/4.6.2.4 DRYWELL S~.AUCTURAL INTEGRITY This limitation ensures that the structural integrity of the drywell will be maintained comparable to the original design specification for the life of the unit. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.2.5 DRYWELL INTrRNAL PRESSURE The limitations on drywell-to-containment differential pressure ensure that the drywell peak calculated pressure of 21.8 psig does not exceed the design pressure cf 30.0 psig and that the containment peak pressure of 11.31 psig does not exceed the design pressure. of 15.0 psig during LOCA conditions.
The maximum external drywell pressure differential is limited to +0.5 psid, well below the 2.4 psid at which suppression pool water will be forced over the weir wall and into the drywell.
The limit of 2.0 psid for initial positive drywell to contain-ment pressure will limit the drywell pressure to 21.8 psig which is less than the design pressure and is consistent with the safety analysis.
3/4.6.2.5 DRYWELL AVERAGE AIR TEMPERAT'!RE The drywell average temperature is an input parameter to the containment /
drywell response analyses as the result of a DBA-LOCA.
Furthermore, the drywell average temperature is important in drywell equipment qualification considerations.
3/4.6.3 DEPp.ESSURIZATION SYSTEMS The specifications of this section ensure that the drywell and containment pressure vill not exceed the design pressure of 30 psig and 15 psig, respectively, during primary system blowdown from full operating pressure.
The suppression pool water volume must absorb the associated decay and structural sensible heat released during a reactor blowdown from 1045 psig.
Using conservative p?rameter inputs, the maximum calculated containment pressure during and following a design basis accident is below the containment design pressure of 15 psig.
Similarly the drywell pressure remains below the design pressure of 30 psig. The maximum and minimum water volumes for the suppression pool are 118,548 cubic feet and 115,612 cubic feet, respectively. These values include the water volume of the containment pool, horizontal vents, and weir annulus.
Testing in the Mark III Pressure Suppression Test Facility and analysis have l
assured that the suppression pool temperature will not rise above 185'F for the full range of break sizes.
l Should it be necessary to make the suppression pool inoperable, this shall l
cnly be done as specified in Specification 3.5.3.
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Experimental data indicates that effective steam condensation without excessive load on the containment pcoi walls will occur with a quencher device and pool temperature belou 200*F during relief valve operation.
Specifications have been placed on the envelope of reactor operating conditions to assure the bulk pool terrperature does not rise above 185'F w. compliance with the contain-l ment structural design criteria.
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PERRY - UNIT 1 B 3/4 6-4 Amendment No. 14 i
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