ML20205D728
| ML20205D728 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/26/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205D721 | List: |
| References | |
| NUDOCS 9904020289 | |
| Download: ML20205D728 (5) | |
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[l UNITED STATES j
NUCLEAR REGULATORY COMMISSION i-WASHINGTON, D.C. 20555 0001
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,o SAFETY EVALUATION BY THE OFFICE OF NUCJmEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 220 AND - 97 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY I
PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS.1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated October 15,1998, as supplemented December 14,1998, February 18,1999, and February 23,1999, the Duquesne Light Company (DLC or the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos.1 and 2 (BVPS-1 and BVPS-2), Technical Specifications (TSs). The requested changes would make several changes that are administrative in nature. The changes would (1) make editorial changes to delete obsolete material or material adequately described elsewhere, change action statement numbers, update TS index pages, and make changes to be consistent with the guidance provided in the improved standard technical specifications (ISTS) for Westinghouse reactors (NUREG 1431, Revision 1); (2) delete reporting requirements that are duplicated in various sections of Title 10 of the Code of Federal Reaulations, and (3) relocate the requirement for meteorological monitoring instrumentation from the TSs to the Licensing Requirements Manual. The Decernber 14,1998, February 18,1999, and February 23,1999, letters did not change the initial proposed no significant hazards consideration determination or expand the amendment beyond the scope of the initial notice. The February 18,1999, and February 23,1999, letters, withdrew a portion of the amendment request which would have removed the description of the site exclusion boundary from the TSs.
2.0 EVALUATION The licensee proposed the following changes in its October 15,1998, license amendment request. The NRC staff's evaluations of the proposed changes are as follows:
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Deletio~ n of BVPS-1 Ucense Condition 2.C.(9), which provided a one-time extension of surveillance interval to 24 months to coincide with tr.9 Cycle 9 refueling wtage. License Condition 2.C.(9) had been incorporated by BVPS-1 L! cense Amandment No.168, dated December 31,1992. The surveillance interval extension provided by License Condition 2.C.(9) has exp; red, therefore, deletion of BVPS-1 License Condition 2.C.(9) is acceptable.
2.
Deletion of BVPS-2 License Condition 2.G., which provided for initial notification with written follow-up of any violations of requirements contained in Section 2.C. of the BVPS-2 Facility Operating License (License No. NPF-73). The NRC's requirements for immediate notification with written follow-up requirements (Licensee Event Reports) of events at operating nuclear power reactors have been incorporated in 10 CFR 50.72 and 10 CFR 50.73.' The requirements of BVPS-2 License Condition 2.G. are redundant to the requirements of 10 CFR 50.72 and 10 CFR 50.73. Therefore, License Condition 2.G. of License No. NPF-73 may be deleted.
3.
BVPS-1 License Amendment No. 213 and BVPS-2 License Amendment No. 90 added TS 3.0.6 for both units. TS 3.0.6 provides guidance for restoring equipment to service under administrative control when the equipment has been removed from service or declared inoperable to comply with ACTION statement requirements. To be consistent with the guidance provided in the ISTS for Westinghouse plants (NUREG-1431, Revision 1), which was used for guidance in the preparation of License Amendment Nos. 213 and 90, reference to TS 3.0.6 should have been added to TS 3.0.1 at that time. However, due to an oversight by the licensee in its request for License Amendment Nos. 213 and 90, this reference was not included in that request for license amendment. The proposed addition of reference to TS 3.0.6 in TS 3.0.1 corrects this j
previous oversight and makes the BVPS-1 and BVPS-2 TS 3.0.1 consistent with the guidance provided in NUREG-1431, Revision 1. Therefore, the NRC staff determined that the proposed addition of reference to TS 3.0.6 in TS 3.0.1 is acceptable.
4.
Revision to the definition of CORE ALTERATION (TS 1.12) to limit core alteration to the movement of fuel, sources, or reactivity control components. The present definition of j
CORE ALTERATION states that CORE ALTERATION shall be the movement or 1
manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. The proposed change would allow flexibility in movement of components that may be used in refueling activities (i.e., lights, cameras, etc.) that have no effect on core reactivity. The proposed change is consistent with current NRC staff positions as reflected in the ISTS for Westinghouse plants (NUREG-1431, Revision 1) and is therefore, acceptable.
S.
Revision to the definition of OFFSITE DOSE CALCULATION MANUAL (TS 1.30) to make the reference to the reporting requirements of the administrative controls TSs consistent with the reformatting of that portion of the TSs. This change is purely an i
editorial change that does not change the requirements of the TSs and is therefore, ccatable.
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Revision to the definition of MEMBER (S) OF THE PUBLIC (TS 1.36) to make this definition consistent with the definition in 10 CFR 20.1003. The proposed change includes all individuals except those that are receiving occupational doses and is consistent with the definition used in 10 CFR 20.1003 and is therefore, acceptable.
7.
Renumber Action Statement 36 of TS Table 3.3-6 to Action Statement 35 for both units and make er onding changes in Table 3.3-6. This change is being made since Action Ste
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35 is not used. This change is purely editorial and does not change the requit ett if the TS and is therefore, acceptable.
8.
Relocation of the ieteorological Monitoring requirements (TS 3/4.3.3.4) and asecciated bases from the BWS-1 and BVPS-2 TSs to the Licensing Requirements Manual (LRM).
The Meteorological Monitoring requirements specified in TS 3/4.3.3.4 do not meet any of the four criteria specified in 10 CFR 50.36(c)(2)(ii) regarding items for which a limiting condition for operation must be established. The LRM was developed and issued by the licensee to control and maintain those items removed from the TSs. Changes to the LRM are controlled in accordance with the requirements of 10 CFR 50.59. The current requirements of TS 3/4.3.3.4 are not being changed in their relocation to the LRM.
Therefore, the NRC staff has concluded that relocation of the Meteorological Monitoring requirements and associated bases of TS 3/4.3.3.4 to the LRM is acceptable.
9.
Revision to bases for BVPS-1 TS 3.4.1.3. BVPS-1 License Amendment No.160, revised the enable temperature for the low temperature overpressure protection system j
from 275 'F to 292 'F. However, a corresponding change to the bases for TS 3.4.1.3 was not included in that amendment. The proposed bases change makes these bases consistent with License Amendment 160. The NRC staff has no objection to the proposed change.
10.
Ramoval of asterisk from BVPS-2 TS 3.9.8.1. BVPS-2 License Amendment No. 25 deleted the footnote previously associated with TS 3.9.8.1; however, this amendment failed to remove the asterisk at the end of TS 3.9.8.1. The proposed removal of this asterisk is purely editorial and is therefore, acceptable.
11.
Clarification of action to be taken when the temperature of an idle reactor coolant loop is exactly 50 *F above the cold leg temperature of the non-isolated loops. BVPS-2 TS 3.4.1.6 prohibits starting an idle reactor coolant pump in a non-isolated loop unless the secondary water temperature of each steam generatoris less than 50 *F above ea h of the inservice reactor coolant system cold leg temperatures. The action statement for TS 3.4.1.6 provides the actions to be taken when the temperature of the steam generator in the loop associated with the reactor coolant pump being started is greater than 50 *F above the cold leg temperature of the other non-isolated loops, but does not provide the
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.4 actions to be taken if this temperature difference is equal to 50 *F. The proposed change would provide the actions to be taken when this temperature difference equals 50 *F. The actions to be taken in this event are the same as when the temperature difference exceeds 50 *F. This is a conservative approach, which the NRC staff finds acceptable; therefore, the proposed change to TS 3.4.1.6 is acceptable.
12.-
Revision to reporting requirements for Special Reports. TSs 3.3.3.3, 4.3.3.3.2, 3.3 3.11, 4.4.5.5,3.5.2, 3.5.3,4.7.9.1.3,3.11.1.4, and 3.11.2.5 require Special Reports to be submitted to the NRC pursuant to TS 6.9.2. This reporting requirement is redundant to 10 CFR 50.4, therefore, the licensee has proposed to revise the subject TSs to require that Special Report be submitted in accordance with 10 CFR 50.4 and that the Special Report requirements of TS 6.9.2 be deleted. TS 6.9.2 would be redesignated as Annual Radiological Environmental Operating Report. Additionally, TS 3.3.3.11 would be modified to specify that this Special Report be submitted within 30 days, which is consistent with the submittal time of similar reports.- These proposed changes do not decrease the effectiveness of the TSs and still require that Special Reports be submitted to the NRC, therefore, the proposed changes to the subject TSs are acceptable.
13.
Reformatting of reporting requirements for routine reports. TSS 6.9.1,6.9.1.1,6.9.1.2, 6.9.1.3, 6.9.1.4, 6.9.1.5, 6.9.1.6, 6.9.1.7, 6.9.1.8, 6.9.1.9, 6.9.1.10, 6.9.1,11, and 6.9.1.12 would be revised, updated, and reformatted to be consistent with the current NRC staff guidance as reflected in ISTS for Westinghouse plants (NUREG-1431, Revision 1) except for the Annual Radioactive Effluent Release Report requirement, (previously TS 6.9.1.11, now TS 6.9.3) which would be retained in its current form as it more clearly specifies the reporting period and report due date. The proposed changes are consistent with the current NRC staff guidance and are therefore, acceptable.
14.
Update of TS index pages. The TS index pages would be updated to address the relocation of the Meteorological Monitoring requirements from the TSs to the LRM.
These are purely editorial changes and are therefore, acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. ' The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirem.ent with respect to installation or use of a facility component located within the restricted area as defin6d in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve 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 4
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' occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (63 FR 64111). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusions set forth in 10 CFR 51.22(c)(9) and (10), Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the
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amendments.
5.0 CONCLUSION
The Commission 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 propcsed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: D. Brinkman i
D. Collins Date: March 26,1999 I
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