ML20126L978
| ML20126L978 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/11/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126L963 | List: |
| References | |
| NUDOCS 8506200191 | |
| Download: ML20126L978 (5) | |
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION D
- j WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.123 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
1.0 INTRODUCTION
By letters dated December 5, 1984 and January 24, 1985, Iowa Electric Light and Power Company (IELP), the licensee for the Duane Arnold Energy Center (DAEC), requested changes to the Technical Specifications resulting from the discovery of an error in the logic circuits that actuate the Well Cooling Water Automatic Backwash Valves. To correct the logic circuit problem, the IELP requested that the Well Cooling Water Automatic Backwash Valves be changed to manual valves and kept locked shut.
IELP has observed that the backwash valves have never been used in the operating history of DAEC and no future need for use of these valves is foreseen. Additionally, the licensee has observed some inconsistencies between the as-built DAEC Group 6 and 7 containment isolation valve logic circuits and the DAEC Technical Specifications (TS). To correct this problem, the licensee has requested additional Technical Specification changes to reflect the as-built logic circuits. Other changes are requested to make the Technical Specifications clearer, more concise, or complete.
Of the 23 changes requested in the licensee's applications dated December 5,1984 and January 24, 1985, seven items (3, 4, 5, 6, 13, 16 and 22) require additional information from the licensee, and will be evaluated in a separate action. The remaining 16 items have been evaluated in this Safety Evaluation (SE).
2.0 EVALUATION The 16 items of requested Technical Specification changes evaluated in this SE (identified with the item numbers used in the licensee's application) are:
(1) In Table 3.2-A on page 3.2-5, the trip level setting for Reactor Low-low-low Water Level is made consistent with the rest of the table by replacing "at or above" with " greater than."
(2)
In Table 3.2-A on page 3.2-Sa, the trip level setting for Reactor Low-low-low Water Level is reworded to be consistent with the format i
of the rest of the table, hk POR P
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.- (7)
In Table 3.2-B on page 3.2-8, low pressure coolant injection (LPCI) loop select infomation is added in columns 4 and 5 for the Reactor Low-low-low Water Level trip function to better reflect as-designed instrumentation.
4 (8)
In Table 3.2-8 on page 3.2-8, Remark I for the Reactor Low-low-low Water Level trip function is clarified to distinguish the operation of the valves from the operation of the pumps.
i (9) In Table 3.2-B on page 3.2-8, Remark 4 is added to indicate that the Group 7 isolation valves are closed upon receipt of a Reactor Low-low-low Water Level signal. This is an administrative change, since this infomation already appears in the notes for Table 3.7-3 on page 3.7-29.
(10) On pages 3.2-9 and 3.2-10, the numbering of remarks is deleted since each trip function has only one remark.
(11) In Table 3.2-B on page 3.2-9, the remarks for High Drywell Pressure and Reactor Low Pressure Trip functions are modified to clarify their
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relation to each other and with Reactor Low-low-low Water Level.
(12)InTable4.2-Aonpage3.2-24,aspellingerroriscorrectedonitem 1
4.
In the Instrument Check column "One" is replaced by "Once."
(14) In Table 3.7-2 on page 3.7-22, the four Well Cooling Water Automatic Isolation Valves, CV-5719A, CV-57198, CV-5703A, CV-5703B, are changed to Manual Valves, V-57-75 V-57-76, V-57-77, V-57-78, to be consistent with hardware change to the well water backwash valves.
(15) In Table 3.7-2 on page 3.7-23,(CRD) return.
boundary valve V-17-54 is added to the entries for control rod drive It was removed in error by a previous amendment.
(17) In Table 3.7-2 on page 3.7-23, the listing of boundary valves is adjusted to make the listing more organized and easier to read.
(18) In Table 3.7-3, for clarity the one asterisk note is moved from page 3.7-29a to page 3.7-26 (19) In Table 3.7-3 on page 3.7-26, the three-asterisk note is added to clarify the operation of the high pressure coolant injection (HPCI)
Discharge to feedwater valve and the reactor core isolation cooling (RCIC) Discharge to Feedwater valve.
(20) In Table 3.7-3 on page 3.7-26, the number of Well Cooling Water Automatic Isolation Valves is changed from 8 to 4 to be consistent with hardware change. The 4 Well Cooling Water Backwash Valves are being changed to Manual Valves, but the 4 Well Cooling Water Automatic Isolation Valves used for normal Well Water Cooling are being left i
intact.
. (21) In the notes to Table 3.7-3 on page 3.7-29, the following remark is added to the Group 7 Containment Isolation Valve actuation description:
"(Note: The level sensors utilized for this function are part of the core and containment cooling logic)."
(23) In the notes to Table 3.7-2 on page 3.7-24, the sentence " Manual valves V-57-75, V-56-76, V-57-77 and V-57-78 will be normally closed" is added to conform to the action prescribed in conjunction with the hardware change HA1.
The evaluation of the proposed modification of the 4 well water valves and the above 16 items of Technical Specification changes is as follows:
Having the proposed Containment Isolation Valves locked closed is equivalent to a current requirement that the open valves be capable of automatic closure by an isolation signal. We find the requested change to be acceptable.
(1) This is an administrative change, and thus we find it acceptable.
(2) This is an administrative change, and thus we find it acceptable.
(7, 8 and 11) These Technical Specification changes to the " remarks" column of Table 3.2-B (Instrumentation that initiates or Controls the Core and Containment Cooling Systems) are for clarification purposes only. No Technical Specification requirements are affected. The added remarks more clearly identify the safety-related equipment actuated by existing protection system instrumentation channess, which have been previously reviewed and accepted by the NRC. Thr,efore, we find these Technical Specification changes to be acceptele.
(9) As is stated in the description of this addition to the Technical Specifications, this addition simply repeats information already in the Technical Specifications, and thus we find it acceptable.
(10) This is an administrative change, and thus we find it acceptable.
(12) This is an administrative change, and thus we find it acceptable.
(14) The Manual Isolation Valve numbers are correct, and thus we find the change of valve numbers to be acceptable. However, the manual valves are improperly labelled in the Technical Specifications (valves are correctly identified in the plant). Valves V-57-75 and V-57-76 should be labelled "Well Cooling Backwash Return" and valves V-57-77 and V-57-78 should be labelled "Well Cooling Backwash Supply." IELP has committed to a future submittal of an administrative Technical Specification amendment application to correct this mislabelling.
(15) This change corrects a previous error in the Technical Specifications, and thus we find the change acceptable.
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i i (17) This change rearranges Table 3.7-2 without changing any of the information, and thus we find the change acceptable.
I (18) This change is an administrative change, and thus we find it acceptable, j
(19) We find the addition of the three-asterisk footnote acceptable, since it describes exactly what signal actuates the 2 Discharge to Feedwater valves in Group 6, namely a signal that the corresponding steam i
turbine inlet or outlet valvec have closed. However, in the notes I
for Technical Specifications Table 3.7-3 the specific' signals which actuate the steam turbine valves are not listed, but are specified to as "any signal representing a steam line break." IELP has comitted to i
a future submittal of an administrative Technical Specification amendment application to add the precise signals which actuate the j
closure of the steam turbine valves to the notes for Table 3.7-3.
(20) This change is consistent with the modifications of the well water backwash valves discussed above, and thus we find it acceptable.
I (21)Thisaddednoteisaclarificationwithnoactionassociatedwithit, and thus we find it acceptable.
l (23) This addition is in confomance with hardware change to the well water backwash valves, and thus we find this addition to the Technical i
Specifications acceptable. However, to make the statement in the Technical Specifications more concise, we requested that the Technical Specifications be modified to read " Manual valves V-57-75 V-57-76, V-57-77 and V-57-78 will be normally locked closed." IELP has added the word " locked" to this sentence, and the Technical Specification page has been appropriately corrected.
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3.0 ENVIRONMENTAL CONSIDERATION
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This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents i
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 this amendment involves no l
significant hazards consideration and there has been no public coment on such finding. Accordingly, this 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 this amendment.
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4.0 CONCLUSION
i We have concluded, based on the considerations discussed above, that (1) l there is reasonable assurance that the health and safety of the public l
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, will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Cormission'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.
Principal Contributor:
P. Kapo Dated:
June 11, 1985 A