ML20072R348
| ML20072R348 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/02/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072R331 | List: |
| References | |
| NUDOCS 9409130151 | |
| Download: ML20072R348 (3) | |
Text
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UNITED STATES i
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WASHINGTON, D.C. 20555 4001 AFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 92 TO FACILITY OPERATING LICENSE NO. NPF-62 ILLIN0IS POWER COMPANY. ET AL.
CLINTON POWER STATION. UNIT N0. 1 DOCKET NO. 50-461
1.0 INTRODUCTION
License Amendment No. 81, issued by the staff on July 15, 1993, made several changes to the technical specifications that were intended to reduce the overall burden placed on control room operators during plant startup.
Surveillance Requirement (SR) 4.1.3.2, which was modified by this amendment, includes requirements to periodically verify control rod maximum scram insertir, times.
Part of this SR includes identifying those control rods that have ret ved maintenance or have been modified such that their scram inserti.. times could be affected. These control rods must have their scram insertion times measured and verified operational prior to entering Operational Condition 1.
Measurements are not permitted until the reactor coolant system pressure reaches a minimum of 950 psig which is the same time that initiates the 12-hour time clock to test the Automatic Depressurization System Safety / Relief Valves (SRVs) and perform SRV acoustic monitoring calibrations.
The ability to perform these tasks in a timely manner becomes particularly difficult if a significant number of control rods fall into this category.
Thus, these actions were perceived by the licensee as placing considerable stress on control room operators. As a result, License Amendment No. 81 introduced SR 4.1.3.3 that permitted an alternative action to test those specifically affected control rods.
SR 4.1.3.3 provided the option to test these control rods at low reactor coolant system pressure thus balancing the overall work scope for the control room operators as the facility approached Operational Condition 1.
Subsequent to the issuance of License Amendment No. 81, the licensee determined that the existing technical specifications contained two separate surveillance requirements numbered 4.1.3.3.
Therefore, as part of License Amendment No. 82 issued on August 5, 1993, SR 4.1.3.2 and 4.1.3.3 associated with control rod maximum scram insertion times, were renumbered 4.1.3.2.1 and 4.1.3.2.2, respectively.
By letter dated April 18, 1994, the licensee identified several technical specifications that incorrectly reference the surveillance requirements covering control rod maximum scram insertion times. These references had not been revised to reflect the renumbering that had occurred as a result of License Amendment Nos. 81 and 82. Therefore, the licensee has requested to correct these previously overlooked references located in Technical 9409130151 94o902 PDR ADOCK 05000461 P
- Specifications 3/4.1.3.1, " Control Rod Operability," 3/4.1.3.2, " Control Rod Maximum Scram," and 3/4.10.2, " Rod Pattern Control System."
2.0 TNALUATION Prior to License Amendment Nos. 81 and 82, SR 4.1.3.2 was subdivided into parts a, b, and c.
Subsequent to these amendments, the following renumbering occurred:
Previous Desianation New Desianation SR 4.1.3.2.a SR 4.1.3.2.1.a SR 4.1.3.2.b SR 4.1.3.2.2 SR 4.1.3.2.c SR 4.1.3.2.1.b The licensee has proposed.ditorial changes to properly reflect the renumbering of SR 4.1.3.2.a b, and c.
Appropriate changes have been proposed for previously overlooked references found in Technical Specifications 3/4.1.3.1, " Control Rod Operability," 3/4.1.3.2, " Control Rod Maximum Scram,"
and 3/4.10.2, " Rod Pattern Control System." The staff has reviewed these proposed changes and finds them acceptable because they now correctly reference the surveillance requirements on control rod maximum scram insertion times.
The staff is also reissuing Technical Specification page 3/4 8-13 to correct typographical errors introduced by the staff.
Surveillance Requirement 4.8.2.1.d.2 is being reissued to correct misspellings.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
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. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 24749). 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.
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5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
l (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 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: Douglas V. Pickett Date: September 2, 1994 1
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