ML20097J663
| ML20097J663 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/25/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20097J660 | List: |
| References | |
| NUDOCS 9504280261 | |
| Download: ML20097J663 (3) | |
Text
o "og a.e.
1 UNITED STATES g
g NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20566-0001 49*****
SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO, 209 TO FAClllTY OPERATING LICENSE NO. DPR-49 4
' TIES UTILITIES INC.
CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE RV.ANE ARN0LO ENERGY CENTER DOCKET N0. 50-331
1.0 INTRODUCTION
By letters dated November 10, 1994, and March 1, 1995, IES.Vtilities Inc.
requested changes to' the Duane Arnold Energy Center (DAEC) Technical i
Specification (TS) Section 3.2.A.
The requested. change would revise the
" Applicable Operating Mode" and " Action" for the Offgas Vent Stack radiation monitors.
The revision would make the requirements for instrument operability match the assumption for when the isolation would occur and provide allowance for reasonable, preplanned compensatory measures for the times when these instruments are not operable, but there is a need to continue venting. The change to the isolation setpoint provides a reference to the appropriate offsite dose limit in the Offsite Dose Assessment Manual (ODAM).
The required Action for the other two isolation functions initiating secondary containment
., isolation is a correction.
The licensee's current practice is to isolate secondary containment when either of these isolation functions are out-of-service. The March 1, 1995, letter from.IES Utilities Inc., requested that an
" editorial change t>e made to bring the TS table'of contents into conformance with the TS and did not change the initial proposed no significant hazards consideration determination.
2.0 EVALVATION The Offgas Stack radiation monitors provide an-isolation signal to the secondary containment isolation valves based upon an indication of increased activity in the gaseous effluent during normal and post-accident venting or purging of primary containment.
The isolation signal was added to satisfy the requirement of NUREG-0737, Item II.E.4.2(7), to provide automatic termination of radioactive releases during containment venting in the eve'nt that those releases exceed a predetermined setpoint.
The revised TS would add Action Statement 27 which allows provision for opening the containment vent and purge valves with the trip function inoperable, provided that administrative control is established for these valves.
This is consistent with the actions specified in DAEC's TS for Primary Containment Power Operated Isolation Valves.
The revised TS Action Statement 27 will assure that containment venting is terminated upon detection of increased gaseous effluent radioactivity beyond acceptable limits.
The staff, therefore, finds the addition of TS Action Statement 27 acceptable.
9504280261 050125 PDR ADOCK C5000331 g
P PDR
In 1993, a revision to TS 3.2.A became effective, which required the Offgas Vent Stack Radiation monitors to be operable in Modes 1, 2 or 3.
This requirement is unnecessarily restrictive, since the necessity for the isolation is only postulated during containment venting or purging.
The g revised TS would. change thei" Applicable Operatirg Mode" to. venting or purging of primary containment, at any time when primary containment integrity is required. When the containment. vent and purge valves are closed, there is no need for an automatic isolation.
The staff therefore, finds the revised TS
" Applicable Operating Mode" for the Offgas Vent Stack radiation monitors acceptable.
The proposed revision would also allow the Offgas Vent Stack high radiation setpoint to be derived from the ODAM. The staff finds this methodology of deriving the setpoint acceptable.
Consequently, the staff finds the proposed changes to the TS requirements and Basis for the Offgas Vent Stack High Radiation monitors acceptable.
Action Statement 26 corrently requires that secondary containment integrity be established and the Standby Gas Treatment System be operated, whenever the Refuel floor Exhaust Duct or Reactor Building Exhaust Shaft High Radiation monitors are out-of-service. The appropriate and more conservative action is to isolate Secondary Containment and operate the Standby Gas Treatment System.
The revised TS Action will assure that no unmonitored releases take place by requiring secondary containment isolation, in the event that the isolation function monitoring the Refuel Floor Duct or the Reactor Building Exhaust Shaft are inoperable.
Consequently, the staff finds the proposed change to this Action statement acceptable.
In addition, the staff finds the proposed editorial change to the TS table of contents acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Jowa State official was notified of the proposed issuance of the amendment.*The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The staff has determined that the amendment involves no significant increase in the 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 exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards
. consideration and there has been no public comment on such finding (59 FR 65815).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
4 i
i
5.0 CONCLUSION
.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..not.be.endange. red by. operation in the proposed manner, (2).such c
activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
J. Sebrosky Date:
April 25, 1995 l
b F
v
- =