ML20024G420
| ML20024G420 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/24/1975 |
| From: | Wachter L NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G299 | List: |
| References | |
| NUDOCS 9102120423 | |
| Download: ML20024G420 (4) | |
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s UNITED STATES NUC1IAR REGULATORY CO?NISSION NORDiERN STATES POWER COMPANY Monticello Nucicar Generating Plant Docket No. 50 263 REQUEST FOR AMENDMENT TO OPERATING LICENSE NO. DPR 22 (License Amendment Request Dated March 24, 1975)
Northern States Power Company, a Mirnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B.
Exhibit A describes the proposed changes along with reasons for the change.
Exhibit B is a set of Technical Specification pages incorporating the proposed changes.
This request contains no t.stricted or other defense information.
NORTHERN STATES POWER COMPANY YGjad81)
By T J Wachter Vice President, Power Production 6 System Operation On this 24th day of March 1975, before ce a notary public in and for said County, personclly appeared L J Wachter, V* cc President, Power Production 6 System Operation, and first being duly sworn acknowledged that he is authorized to execute this docu_ent in behalf of Northern States Power Company, that he knows the conten:s thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
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JOHN J. SMITH Notsff Pu%c, Nnne$ bay, Minnemte ky"-
Ex taprea March 3,1976 9102120423 750324 PDR ADOCK 05000263 P
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EXHIBIT A MONTICELLO NUCLEAR GENERATING PIANT DOCKET NO. 50-263 AMENDMENT REQUEST DATED r.3RCH 24, 1975 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS APPENDIX A 0F OPERATING LICENSE NO. DPR-22 j
Pursuant to 10CFR50.59, the holders of the above mentioned license hereby pro-pose the following changes to Appendix A Technical Specifications:
1.
Specification 3.7.A.1 Proposed Changes Change Specification 3.7.A.1 to read:
1.
Whenever primary containment is required, the volume and temperature of the water it the suppression chamber shall be maintained within the following limits:
1 1
(a) }bximum water volume - 77,970 cubic feet.
(b) Minimum water volume - 68,000 cubic feet.
(c) Maximmn water temperature 1.
During power operation, except as specified 0
in item 3.7. A.1.(c). ii below - 90 F.
ii. During testing which adds heat to the suppression pool - 100 F.
iii. Following a seres from a condition where the suppression pool temperature is 90 F or less, the reactor pressure vessel shall be de-pressurized at normal cooldown rates to less than 200 psig if the suppression pool 0
temperature exceeds 120 F.
iv.
During power operation if the temperature reaches 1100F the reactor shall be scrammed nu:ediately and depressurized at normal cool-down rates to less than 200 psig.
j i
Exhibit A
- (d)
In order to continue power operation after exceeding the limit of 1(c)i, the suppression pool temperature cust be reduced to 90 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the temperature cannot be reduced within this time 10mit, normal reactor shutdown procedures shall be initiated.
Reason for Change To minimize the probability of steam quenching vibration in the suppression pool by precluding the development of elevated te=peratures in che pool.
Ths temperature 1Lnits specified in this proposed change were based on con-servative engineering judgments by the General Electric Company'. An analysis is planned that will establish a definitive set of temperature limits besed on the Hbnticello plant configuration. When this analysis is completed the new limits will be reflected in a further technical specification change request.
2.
Specification 4.7. A.1 Proposed Changes Change Specification 4.7. A.1 to read:
1.
Checks and inspections of the suppression chamber structures, water level and temperature shall be conducted as follows:
(a) Water level and temperature shall be checked once per day.
(b) The interior painted surfaces above the water level shall be inspected at each refueling outage.
(c) Whenever there is indication that there was relief valve operation with the tecperature of the suppression pool exceeding 160 F and the reactor vessel pressure greater than 200 psis, an external visual examination of the pressere suppression chamber shall be conducted before resuming power operation.
Ecaron for Channe Specification 4.7.A.1 (c) has been added to provide assurance that no significant damage resulted from the occurrence described in the specification.
Exhibit A I
' 3.
Bases 3.7.A proposed Channes a.
Change the next to last line of the third full paragraph on page 157 to read:
"... restricted by Specification 3.7.A.1(c) by limiting the suppression pool initial temperature and the..."
b.
Add the following paragraph af ter the third paragraph on page 157:
Experimental data indicates that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is maintained below 160 F during any period of relief valve operation with sonic conditions at the discharge exit.
Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure supprersion chamber loadings; Reason for Changes To provide bases for the proposed changes to Specification 3.7. A.1.
4.
Bases 4.7. A Proposed Change Add the following paragraph to page 161:
The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.
Particular attention should be f ocused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be points of highest stress.
Reason for Change To provide bases for the proposed changes to Specification 4.7. A.1.
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