ML20049H866
| ML20049H866 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/01/1982 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20049H863 | List: |
| References | |
| NUDOCS 8203040384 | |
| Download: ML20049H866 (6) | |
Text
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l Proposed Technical Specification Proposed Change Reference is made to Pilgrim Nuclear Power Station, Unit #1 Technical Specifica-tion, Section 3.2 " Protective Instrumentation - Limiting Conditions for Operations and Section 4.2 - Surveillance Requirements for Protective Instrumentation.
Add:
Section 3.2.H, Drywell Temperature Limiting Conditions of Operations and Section 4.2.H Drywell Temperature Surveillance Requirements as shown on Page 44b & 44c.
Table 3.2.H, Drywell Temperature Surveillance Instrumentation as shown on Page 59b attached.
Table 4.2.H, Minimum Test & Calibration frequency for Drywell Tempera-ture Sueveillance Instrumentation as shown on Page 66b attached.
Bases 3.2 Continued, Drywell Temperature as shown on Page 73a attached.
Reason for Change We propose these changes at the behest of USNRC, as stated in a meeting conducted between Boston Edison and NRC on December 18, 1981 and restated on Page 2 of a meeting summary issued January 5,1982.
Safety Considerations These proposals are made at the request of NRC. They do not present unreviewed safety questions. They have been reviewed and approved by the Operations Review Coninittee, and reviewed by the Nuclear Safety Review and Audit Committee.
Schedule of Change These changes will be put into effect upon our receipt of the Commission's approval.
Fee Determination Pursuant to 10 CFR Section 170.12, Boston Edison Company proposes this change as a Class III.
82030403e4 820301 PDR ADOCK 05000293 p
Liciting Condition: for Op:r,ations Surveillance Rtg 3.2.H Drywell Temperature 4.2.H Drywell Temperature 1.
The drywell temperature shall 1.
be maintained within the follow-When reactor coolant temperature ing limits when the reactor is above 212*F, the drywell air temperature limits will be de-coolant temperature is above 212*F.
termined by reading the instruments listed in Table 3.2.H.
These in-
- Above elevation 40' :(194*F struments shall be logged once per shift, and each reading compared Equal to or Below elevation to the limits of Section 3.2.H.1.
40' :-4150*F 2.
Instrumentation shall be calibratec Upon determination that the dry-and checked as indicated in Table well temperature at any elevation 4.2.H.
has exceeded the above limits, the drywell temperature at each elevation shall be logged every 30 minutes. The drywell tempera-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-wise, corrective action shall be as specified in 3.2.H.2, 3.2.H.3.
2.
If the drywell temperature has 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.
3.
If the requirements of 3.2.H.2 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 />.
4.
If the drywell temperature at any elevation exceeds 215*F and dit temperature canno' be reduced to below 215*F within 30 minutes a reactor shutdown shall be initiated and the reactor shall be in cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
44b
5.
The limiting conditions of op-eration for the instrumentation that monitors drywell tempera-ture are given in Table 3.2.H.
G 1
44c l
PNPS TABLE 3.2.H Drywell Temperature Surveillance Instrumentation Nominal Minimum # of Instrument Operable Elements Instrument #
Elevation Type Note Abova 40 Feet Elevation 1/ELEV TE-5050A 1/2 80' RTD (1) (2) (4).
TE-50508 1/2 80' 1/ELEV TE-5050C 1/2 87' RTD (1) (2) (4)
TE-5050D 1/2 87' 1/ELEV TE-5050E 1/2 60' RTD (1) (2) (4)
TE-5050F 1/2 60' Below 40 Feet Elevation 1/ELEV TE-5050G 1/2 41' RTD (1) (3) (4)
TE-5050H 1/2 1/ELEV TE-5050J 1/2 32' RTD (1) (3) (4)
OR TE-5050K 1/2 Notes:
1.
The 5050 series temperature elements are dual-elements 2.
At least one element of one RTD on each elevation shall be operable.
3.
At least one element of one RTD on elevation 41 and one element of one of the RTD's at nominal elevation 32 shall be operable.
4.
If the minimum number of operable RTD's as specified in Note 2 and 3 above are not availiable 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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PNPS TABLE 4.2.H Minimum Test & Calibration Frequency for Drywell Temperature Surveillance Instrumentation Instrument Channels /
Calibration Instrument Nominal Elevation Frequency Check 80 Feet Each Refueling Once per Shift Outage 87 Feet Each Refueling Once per Shift Outage 60 Feet Each Refueling Once per Shift Outage 41 Feet Each Refueling Once per Shift Outage 32 Feet Each Refueling Once per Shift Outage i
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BASES (Continued) 3.2 Drywell Temperature The dyrwell 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 temperature 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 ambient temperature on equipment design limits and material degradation of components required for accident mitigation or plant shutdown. The evaluation process addressed the actual assessment of potential damage and the determination of equipment status from the standpoint of both qualification integrity (for 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.
0 The Ifmiting 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 equipment operability based upon engineering judgement.
I 73a