ML20005D840

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Safety Evaluation Supporting Amend 75 to License DPR-34
ML20005D840
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/14/1989
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20005D837 List:
References
NUDOCS 9001020056
Download: ML20005D840 (4)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 75 TO FACILITY OPERATING LICENSE NO. DPR-34 j

PUBLIC SERVICE COMPANY OF COLORADO i

FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267 1

1.0 INTRODUCTION AND BACKGROUND

By letter dated September 14, 1989 as revised December 4, 1989 Public Service CompanyofColorado(thelicensee)submittedproposedTechnicalSpecifications (TS) changes on fuel handling and storage for Fort St. Vrain (FSV) in response 1

to NRC letter dated August 8, 1989. The December 4,1989 revision to the j

September 14, 1989 application deletes a portion of the September 14 requested change to the TS but does not change the staff's previous determination of no significant hazards consideration.

2.0 EVALUATION The proposed TS clarify certain TS definitions and add new, more conservative requirementsforfuelhandlingandstorage. This evaluation discusses the acceptability of the licensee s proposed TS on an item by item basis and provides NRC staff conclusions. The staff has independently reviewed each of the proposed TS changes.

Editorial Changes The proposed TS add definitions for " core alteration" and " shutdown margin" (TS 2.26 and 2.30) to clarify these words as they are used in the TS.

The proposed deletion of the TS on " Reactor Vessel Internal Maintenance" (TS 4.5.2) is acceptable because the requirements of those TS are now addressed in TS 4.7.1 of the proposed TS. Since there is no reduction in the require-ments, the staff has found this change acceptable.

The proposed TS on " Fuel Handling and Storage" (TS 4.7) specifies the applicability of each requirement separately rather than the present general applicability statement for the entire TS section. This proposed TS states the applicability of each requirement more clearly than present TS.

I Each of the above changes is editorial only to clarify and reorganize the TS.

I The staff has reviewed these changes and found them hcceptable as they do not decrease the requirements of current TS.

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Fuel Handling in the Reactor. Limiting Condition for Operation (LCO) 4.7.1 The proposed TS is more conservative than present TS because a new condition is added. The added condition requires the reinstallation of the control rod drive and orifice assembly under certain core temperature conditions to prevent i

damage to reactor isolation valve seal material.

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The staff has reviewed the proposed change and found it acceptable because it is more conservative with respect to protecting the isolation valve soals.

Fuel Handling Machine. LCO 4.7.2

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The proposed TS add requirements for the fuel handling machine that are more conservative than current TS, Requirements are added for:

1) an additional l

cooling water coil; 2) attaching the fuel handling machine to specified systems i

for it to be declared operational; and 3) additional switches and alarms for verifying the orientation and placement of fuel elements.

The staff has reviewed this proposed TS change and finds it acceptable because each of the proposed changes is more conservative than current TS.

Fuel Storage Wells LCO 4.7.3 This LCO is more restrictive than current TS because it prohibits storage of fuel in the central column of a fuel storage well where cooling may not be adequate. Since this requirement is more conservative than current TS, the staff finds this proposed change acceptable.

i Spent Fuel Shipping Cask. LCO 4.7.4 The proposed TS is more conservative than current TS in that it prohibits loading of cask with irradiated fuel having less than 100 days of fission product decay.

The staff finds this change acceptabic as it is more conservative than present l

TS.

In addition, the reactor was permanently shutdown on August 18, 1989 and l

all spent fuel now has more than 100 days of fission product decay.

Instrumentation. LCO 4.7.5 The proposed TS is an additional requirement not in current TS. The proposed TS requires the core to be continuously monitored by at least two neutron flux monitors during any core alterations /defueling. The staff has reviewed this proposed TS and has determined that it is acceptatie because it is more conservative than current TS.

t Communications During Core Alterations. LCO 4.7.6 l

This is an additional requirement for two-way communications between operators in the Control Room and the Fuel Handling Machine Control Room. Since the current TS have no such requirement, the staff has determined that this is a more conservative requirement and is acceptable.

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Fuel Handling Machine. Surveillance Requirement (SR) 5.7.1 The proposed TS adds additional surveillance requirements for the fuel handling l

machine that are more conservative than current TS. Therefore, the staff j

finds the proposed TS acceptable, i

Fue) Storage Wells. SR 5.7.2 i

The proposed TS adds additional surveillance requirements for the fuel Storage Wells and is more conservative than the current TS.

Therefore, the staff finds j

this TS acceptable.

r Fuel Handling and Maintenance in the Reactor, SR 5.7.3 l

This proposed TS requires additional surveillance of reactor shutdown margin, l

pressure and temperature that is not required in current TS.

It therefore j

l provides greater assurance that changes in reactor conditions will be detected 1

in time to permit corrective actions.

The staff has reviewed this proposed TS and finds it acceptable.

Spent fuel Shipping Cask SR 5.7.4 The proposed TS is more conservative than present TS because it adds a i

surveillance requirement to determine that all irradiated fuel elements shall have undergone fission product decay of 100 days or more before being loaded into shipping casks.

In addition, since the plant was permanently shutdown on August 18, 1989 all of the irradiated fuel has now decayed more than 100 days.

The staff therefore finds this proposed change acceptable.

I Instrumentation, SR 6.7.5 The proposed TS is an additional surveillance requirement for surveillance of l

neutron flux monitors used during defueling. The staff has reviewed the proposed TS and has determined that it is acceptable because it is more i

conservative than present TS.

Comunications During Core Alterations. $R 5.7.6 I

The proposed TS is a new requirement for surveillance of communication systems used during operation of Fuel Handling Machine.

Since this is an additional, nere conservative requirement, the staff finds it acceptable, i

3.0 ENVIRONMENTAL CONSIDERATION

l The amendment involves a change in a requirement with respect to the installa-l tion or use of a facility corponent located within the restricted area as l

defined in 10 CFR part 20 and changes to surveillaneg requirements. The staff has determined that the amendment involves no significant increase in the L

amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures. The Commission has previously I

issued a proposed finding that the amendment involves no significant hazards i

consideration and there has been no public coment on such finding.

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Accordingly, the amendment meets the eligibility) criteria for categorical i

exclusionsetforthin10CFRSection51.22(c)(9.

Pursuant to 10 CFR 51.22(b),

i no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

4.0 CONCLUSION

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The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will i

not be endangered by operation in the aroposed u.anner, and (2) such activities will be conducted in compliance with tie Comission's regulations, and the l

issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributor: James R. Miller OTSB 1

Kenneth L. Htitner, PDNP Peter B. Erickson, PDNP Dated: December 14, 1989

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