ML20127J513

Safety Evaluation Accepting Amend 7 (TS Change 16) to DPR-22 Re Reactor Vessel Matl Surveillance Program

ML20127J513
Person / Time
Site:	Monticello
Issue date:	02/03/1975
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127J494	List: ML20127J492 ML20127J495 ML20127J513 ML20127J524
References
NUDOCS 9211190359
Download: ML20127J513 (2)

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P SAFETY EVALUATION BY Tile DIVISION OF REACTOR LICC; SING SUPPORTING AMI2TDMENT NO. 7 TO TACILITY PROVISIONAL OPERATING LICD SE NO. DPR-22 (CHANGE NO. 16 TO THE TEC11NICAL SPECIFICATIONS)

NORTilERN STATES POWER COMPANY

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MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 INTRODUCTION By letter dated Hovember 15, 1974, Northern States Power Company (NSP) submitted proposed changes to the Technical 9pecifications of Provisional Operating Licensa No. DPR-22 for the. Monticelle Nuclear Generating Plant.

We have elected to evaluate only $.:em 16 of the licensee's proposed changes to avoid delays in permitting the licensee to return to power operation. This proposed change is to delete a requi ement to remove one basket of material surveillante samples during the third refueling outage scheduled for January 1975. Our evaluation of the licensee's other proposed changes to the Technical Specifications will be issued at a later date.

EVALUATION We have evaluated the licensee's propoccIr to defer the removal of certain reactor vessel material specimens. l e have concluded that more meaningful test results will be obtained by delaying the removal of test specimens until such time that the estimated change in the Nil Ductility Transition Temperature (NDTT) is approximately 50'F, but prior to the time when the estimated fluence is 1010 n/cm2 or at the 15 years operational interval, whichever first occurs. Premature withdrawal of material specimens whose neutron exposure is significantly less than 1018 n/cm2 (Monticallo is currently approximately 1.0 x 10 17 n/cm2) will yield very limited data

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due to minimal change in iiDIT from radiation damage. Since the proposed naterial aurycillance will still comply with 10 CFR 50, Appendix li,

" Reactor Vessel Unterial Surveillance Program Requirements," and will provice more useful onta, we have concluded that t:ic preposed withdraial achedule is acceptable, orrice * ~ -

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2-I CONCLUSION We have concluded, based on the reasons discussed above, that because the change does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve

- a significant decrease in a safety margin, the change does not involve r 1 . a significant hazards consideration. We also conclude that there is J reasonable assurance (i) that the activities authorised by this amandment ,

can be conducted without endangering the health and safety of the public.

and (ii) that such activities will be conducted in complianc.e with the Commission's regulations and the issuance of this amendment will not be

! inimical to the common defense and security or to the health and safety of the public.

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