ML20054E067
| ML20054E067 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/20/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Boston Edison Co |
| Shared Package | |
| ML20054E068 | List: |
| References | |
| DPR-35-A-058 NUDOCS 8204260098 | |
| Download: ML20054E067 (8) | |
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UNITED STATES d
NUCLEA' REGULATORY COMMISSION R
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p WASHINGTON. D. C. 20555
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f BOSTON EDISON COMPANY DOCKET NO. 50-293
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PILGRIM NUCLEAR POWER STATION t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated Mr.ch 1,1982 complies with the standards and i
requirements 0: the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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;
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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; 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.' DPR-35 is hereby amended to read as follows:
B.
Technical Specifications i
The Technical Specifications contained in Appendices A and i
B, as revised through Amendment No. 58, are hereby incorporated j
in the license. The licensee shall operate the facility in l
accordance with the Technical Specifications.
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8804360035 l
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSI0N Domenic B. Vassallo, Chief:
Operating Reactors Branch #2
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Division of 1.icensing
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Attachment:
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Changes to the Technical 2 - ~---
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Specifications Date of Issuance: March 20,1982 O
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sc ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Add the following new pages:
44b 44c 59b 66b 73a G
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' Limiting C:ndititna'fcr OparctitnD Surva111cnce R:q 3.2.H Drywell Temperature 4.2.H Drywell Te=perature 1.
The drywell temperature shall 1.
When reactor coolant te=perature be maintained within the follow-is above 212*F, the dryvell air ing limits when the reactor temperature limits will be de-coolant temperature is above termined by reading the instruments 212*F.
listed in Table 3.2.H.
These in-
- Above elevation. 40' :4194*F stru=ents shall be logged once per shift, and each reading compared Equal to or Below e'levation to the limits of Section 3.2.H.l.
40' :g,150*F 2.
Instru=entation shall be calibrated Upon determination th'at the-dry-
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- and checked as indicated in Table
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well temperature at any elevation 4.2.H.
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has exceeded the above limits, the drywell te=perature at each elevation shall be logged every 30 minutes. The drywell te=pera-ture shall be reduced to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; other vise, corrective action shall be as specified in 3.2.H.2, 3.2.H.3.
J2. If the drywell temperature has
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exceeded either limit of 3.2.H.1 for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an engineering evaluation shall im-mediately be initiated to assess potential damage and render a determination of ability of safety related equipment to per-form its intended function.
If either limit of section 3.2.H.1 has been exceeded for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, further action to justify continued op-eration shall be determined by an engineering evaluation, which must be completed within one week.
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If the requirements of 3.2.H.2 l
have not been met an orderly Shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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If the drywell temperature at any elevation exceeds 215'F and the te=perature cannot be reduced to below 215*F within 30 minutes a reactor shutdown shall be initiated and the reactor shall be in cold shutdown condition 44b within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 58
5.
Tha limiting c:nditiens of op-eration for the instrumentation that monitors drywell tempera-ture are given in Table 3.2.H.
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1 44c Amendment So. 58
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h TABLE 3.2.ll g
Drywell Tempe'rature Surveillance Instrumentation
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5 Nominal Minimum # of Instrument Note ui
" Operable Elements Instrument #
Elevation
- Type, Above 40 Feet Elevation 1/ELEV TE-5050A 1/2 80' RTD (1) (2)'(4)
TE-5050B 1/2 80' 1/ELEV TE-5050C 1/2 87' RTD (1) (2) (4) 87' TE-5050D 1/2,-
(1) (2) (4) i 1/ELEV TE-5050E 1/2 60' RTD TE-5050F 1/2 60' B110w 40 Feet Elevation -
1/ELEV TE-5050G 1/2 41' RTD (1) (3) (4)
TE-5050ll 1/2 1/ELEV TE-5050J 1/2 32' RTD (1)'(3) (4)
OR TE-5050K 1/2 a
Notes:
1.
The 5050 series temperature elements are dual-elements 2.
A,6 least one element of one RID on each elevation shall be operable.
3.
At least one element of one RTD on elevation 41 and one element of one of the RTO's at nominal elevation 32 i
shall be operable.
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If the minimum number of operable RTD's as specified in Note 2 and 3 above are not availlable and cannot be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an orderly shutdown shall initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of shutdown initiation.
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k TABLE 4.2.11 k
Minimum Test & Calibration Frequency f5r Drywell
-lg Temperature Surveillance Instrinnentation Instrument Channels /
Calibration Instrument Nominal Elevation Frequency Check 80 Feet
'E'a'ch Refuel 1.ng Once per Shift Outage 87 Feet Ea.ch Refueling Once per Shift Outage j
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60 Feet Each' Refueling Once per Shift j
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41 Feet Each Refueling Once per Shift Outage 32 Feet Each Refueling Once per Shift Outage j'
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BASES (Continued)
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3.2 Drywell Temperature The dyrwel'1 temperature limitations of Specification 3.2.H.1 ensure that safety related equipment will not be subjected to excess temperature.
Exposure to excessive temperatures may degrade equipment and can cause loss of its operability.
The temperature elements for monitoring drywell temparature specified in Table 3.2.H were chosen on the basis of their reliability, location, and their redundancy (duel - element RTD's). These temperature elements are the primary elements used for the PCILRT.
The temperature limits specified in 3.2.H.1 are based on the BECo report entitled Drywell Temperature Report, dated January 28, 1982. The limits
' derived from this report take into consideration the long-term effects of a'mbient temperature on equipment design limits and material degradation of The evaluation components required for accident mitigation or plant shutdown.
process addressed the actual assessment of potential damage and the determination of equipment status from the standpoint of both qualification integrity (for i
safety-related equipment) and reliability to perform it's intended function.
If the drywell temperature exceeds the. limits specified in 3.2.H.1 an engineering evaluation must be initiated in order to determine whether any safety related component has been adversely affected.
The limiting drywell temperature value of 215'F (Section 3.2.H.2) was selected as to guarantee that ECCS trips occur on/or before present Technical Specification values.
The time interval of 30 minutes between successive drywell temperature in-strument readings (Section 3.2.H.1) was selected so as to guarantee that ECCS trips occur on/before present Technical Specification values in the event of a drywell temperature excursion in excess of 215 F.
The instrument check interval of once per shift provides adequate assurance of l
equipmert operability based upon engineering judgement.
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i 73a Amendment No. 58
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