ML20116H248
| ML20116H248 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/28/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116H245 | List: |
| References | |
| NUDOCS 9211130016 | |
| Download: ML20116H248 (4) | |
Text
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 4r TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
H RRY NUCLEAR POWER PLANT. UNIT NO. 1 DQCKET NO. 50-440
1.0 INTRODUCTION
On June 19, 1992, as supplemented September 24, 1992, the Cleveland Electric Illuminating Company (the licensee) requested an amendment to Facility Operating License No. NPF-58, for the Perry Nuclear Power Plant (PNPP),
Unit 1.
The proposed amendment would remove certain Technical Specification (TS) tables that include lists of components referenced in individual specifications.
In addition, the TS requirements have oeen modified such that all references to these tables have been removed.
Finally, the TSs have been modified to state requirements in general terms that include the components listed in the tables removed from the TSs.
Guidance on the proposed TS changes was provided by Generic Letter (GL) 91-08, dated May 6, 1991.
A " Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing" for the proposed action was published in the Federal Reaister on August 19, 1992 (57 FR 37560).
The additional information provided by the licensee on Septeaber 24, 1992 did not affect the staff's determination as documented in the referenced notice.
2.0 EVALUATION The licensee proposes to relocate the component lists for Containment Isolation Valvet (Table 3.6.4-1) and Containment Penetraticn Conductor Overcurrent Protection Devices (Table 3.8.4.1-1) from the PNPP Unit 1 TSs to the PNPP Operations Manual, Volume 18 (the Plant Data Cook).
In addition, TSs referencing those tables will also be revised, and footnotes in those tables that modify the TS requirements will be retained in new limiting Conditions for Operation, as appropriate.
2.1 Removal of Table 3.6.4-1 The licensee has proposed the removal of Table 3.6.4-1, " Containment Isolation Valves," referenced in,
3!4.6.4. With the removal of this table, the 9211130016 921028 ADOCK OS00 0
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. statement of the Limiting Condition for Operation (LCO) for TS 3.6.4 will read as follows:
Each containment isolation valve shall be OPERABLE.
The licensee has also revised the Action requirements under TS 3.6.4, and the Surveillance Requirements of TS 4.6.4.1 through 4.6.4.3 to remove all references to Table 3.6.4-1.
Footnote "f" is added to the revised LCO, to retain certain exceptions currently allowed in footnotes to Table 3.6.4-1.
These include:
a.
A provision stating that Containment Vessel and Drywell Purge system 42-inch inboard purge valves 1H14-F045 and -F085 are not required to be OPERABLE in OPERATIONAL CONDITION 1,2 and 3.
b.
A provision stating that the Reactor Core Isolation Cooling system containment isolation valves are not required to be OPERABLE in OPERATIONAL CONDITION ** (when handling irradiated fuel in the primary containment, during CORE ALTERATIONS and operations with a potential for draining the reactor vessel),
c.
A provision allowing Fire Protection system manual hose reel containment isolation valves IP54-F726 and -F727 to be opened as necessary to supply fire mains in OPERATIONAL CONDITION **.
In addition, footnote # includes a statement that locked or sealed closed isolation valves may be opened on an intermittent basis under administrative controls.
This provision will apply to all containment isolation valves not addressed above that have the locked or sealed closed feature consistent with General Design Criteria 55, 56 and 57 of Appendix A to 10 CFR Part 50.
The licensee has r.lso revised TS Bases Section 3/4.6.4, " Containment Isolation Valves," to better define the intent of opening valves under administrative controls, as recommended by the staff in GL 91-08.
The information deleted from Table 3.6.4-) will be retained in the PNPP Plant Data Book, which will be controlled via the requirements for procedures in TS Section 6.0, " Administrative Controls." The proposed changes to TS 3.6.4, including the removal of Table 3.6.4-1 and changes to the associated Bases, are consistent with the guidance of Generic letter 91-08 and are therefore acceptable.
2.2 References to Table 3.6.4-1 As a resait of the proposed removal of Table 3.6.4-1, aumerous reforences to the table throughout the TS also need to be modified for consistency. TS definition 1.33, " Primary Containment Integrity" and Surveillance Requirements 4.6.1.1.1.b and 4.6.1.1.2.a. " Primary Containment Integrity-Operating" and
" Shutdown," respectively, have been modified to delete the reference to Table 3.6.4-1, and to allow the opening of certain valves as specified in new TS 3.6.4.
Although the words "under administrative control" are omitted, the revised statements are consistent with the intent of GL 91-08 because new TS 3.6.4 does specify that locked or sealed closed isolation valves may be opened
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- on an intermittent basis under administrative controls. Therefore, this requirement is implicit in the revised statements, and these changes are acceptable.
TS Tables 3.3.2-1, " Isolation Actuation Instrumentation", 3.3.2-3, " Isolation Actuation Instrumentation Response Time" and 3.3.7.5-1, " Accident Monitoring Instrumentation" are revised to remove explicit references to valve groups and isolation times listed in Table 3.6.4-1.
Similarly, TS 3.6.1.2, " Primary Containment Leakage" and the associated Surveillance requirements are revised to remove all references to Table 3.6.4-1, consistent with GL 91-08. These changes are editorial and do not revise existing requirements; therefore, they are acceptable.
2.3 Removal of Table 3.8.4.1-1 The licensee has proposed the removal of Table 3.8.4.1-1, " Containment Penetration Conductor Overcurrent Protective Devices" and revisions to the associated TS 3/4.8.4.1.
The revised statements in the LC0 and Surveillance Requirements are consistent with the guidance of Generic Letter 91-08 and do not change any existing requirements. The Bases are also revised to indicate that the list of devices is included in the PNPP Plant Data Book.
2.4 Summary On the bacis of the above review, the staff finds that the proposed changes to the TS for the Perry Nuclear Power Plant, Unit 1, are primarily administrative in nature and do not alter the requirements set forth in the existing TS.
Overall, these changes will allow the licensee to make corrections and updates to the lists of components for which these TS requirements apply, under the provisions that control plant procedures as specified in Section 6.0, Administrative Controls, of the PNPP Unit 1 TS. These controls include raquirements for the review of changes in accordance with 10 cFR 50.59, review and approval by the Plant Operations Review Ccmmittee, and approval by the plant General Manager.
Therefore, the staff finds that the proposed TS changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 My EfNMENTAL CONSIDERATION This amendment involves a change to a requirement with respect'to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change to a surveillance requirement. 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 this amendment involves no significant hazards
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A consideration and there has been no public conment on such finding (57 FR 37560). 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.
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 endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) 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:
J.R. Hall Date:
Octooer 28, 1992 h
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