ML20137Y821
| ML20137Y821 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/14/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137Y819 | List: |
| References | |
| NUDOCS 9704230249 | |
| Download: ML20137Y821 (6) | |
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UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30666-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 202 AND 83 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 MOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYIVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLVMINATING COMPANY THE TOLEDO EDIS0N COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated September 9,1996, the Duquesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos.
I and 2 (BVPS-1 and BVPS-2) Technical Specifications (TSs).
The requested changes would modify the design features section (Section 5.0) of the TSs to make the design features section consistent with the four criteria specified in 10 CFR 50.36 and with the guidance provided in the NRC's Standard Technical Specifications, Westinghouse Plants (NUREG-1431, Revision 1).
2.0 EVALUATION The proposed change to the design features section (Section 5.0) of the TSs would delete certain requirements from the current TSs and add some other requirements not presently included in the TSs. The proposed changes to the TSs would include some minor editorial changes and would correct the TS Index pages. The proposed editorial changes and the Index pages are acceptable since they do not change the intent of any TSs nor do they change any TS requirements. The proposed deletions and additions are evaluated below.
Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to include TSs as part of the license.
The Commission's regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. That regulation requires that the TSs include items in five specific categories, including (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation;
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- (3) surveillance requirements; (4) design features; and (5) administrative controls.
The four criteria defined by 10 CFR 50.36 for determining whether particular limiting conditions for operation are required to be included in the TSs, are as follows:
(1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier;
' system, or component that is part of the primary success p(3) a structure, ath and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (4) a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
Existing TS limiting conditions for operation which do not satisfy these four specified criteria may be relocated to the Updated Final Safety Analysis Report (UFSAR), such that future changes could be made to these provisions pursuant to 10 CFR 50.59. Other requirements may be relocated to more appropriate documents (e.g. Security Plan, Quality Assurance (QA) plan, and Emergency Plan) and controlled by the applicable regulatory requirement.
While the content of the TSs design features and administrative controls are specified in 10 CFR 50.36(c)(4) and 10 CFR 50.36(c)(5), respectively, particular details of the design features and administrative controls may be relocated to licensee-controlled documents where 10 CFR 50.59 or comparable regulatory controle exist.
With respect to design features, 10 CFR 50.36(c)(4) requires that design features to be included in TSs are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered as TS safety limits, limiting safety system settings, limiting conditions for operation, or surveillance requirements.
Based on the guidance provided in 10 CFR 50.36 and in NUREG-1431, Revision 1, the licensee has proposed the following TS changes, deletions, and additions:
1.
TS 5.1 (Site) would be modified to be consistent with the guidance provided in NUREG-1431, Revision 1.
TS 5.1 would be' re-titled to Site Location and consistent with NUREG-.1431, Revision 1, would include a text description of the site rather than referencing and including BVPS-1 TS Figures 5.1-1 through 5.1-6 and BVPS-2 TS Figures 5.1-1 through 5.1-4.
The site boundary, shown in TS Figure 5.1-1 for both unitt., is also shown in Figure 5.1-1 of the offsite dose calculation manual ;00CM).
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3.
- Reference to BVPS-1 TS Figure 5.1-2 in TS 5.1.2 would be deleted since BVPS-1 TS Figure 5.1-2 was previously deleted by License Amendment No.
121. Therefore, deletion of reference to BVPS-1 TS Figure 5.1-2 in TS j
5.1.2 is acceptable.
The exclusion area boundary, shown on TS Figure 5.1-3 for both units, is also described and shown in BVPS-1 Updated Final Safety Analysis Report i
(UFSAR) Section 2.1.1 and BVPS-1 UFSAR Figure 2.1-7 and in BVPS-2 UFSAR Section 2.1.2.1 and BPVS-2 UFSAR Figure 2.1-2.
The low population zone shown on TS Figure 5.1-4 for both units, is also described in BVPS-1 UFSAR Section 2.1.2 and in BVPS-2 UFSAR Section 2.1.3.5.
The gaseous and liquid release points shown.n BVPS-1 TS Figures 5.1-5 and 5.1-6 and in BVPS-2 TS Figure 5.1-2 are also shown in ODCM Figure 2.4-2 for the gaseous release points and ODCM Figures 1.4-1 and 1.4-2 for
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the BVPS-1 and BVPS-2 liquid release points.
The flood control requirements of TS 5.1.5 are also described in BVPS-1 UFSAR Section 2.3.3 and in BVPS-2 UFSAR Section 3.4.1.
4 The requirements of 10 CFR 50.36(c)(4) do not require the inclusion of figures showing site arrangements.
However, 10 CFR 50.36(c)(4) does require the inclusion of geometric arrangements.
The proposed change to TS 5.1 provides a text description, which meets this criteria. A text description of the site is consistent with the guidance provided in NUREG-1431, Revision 1.
The TS figures are also shown in UFSAR and ODCH figures. Any changes to UFSAR figures will be subject to the requirements of 10 CFR 50.59, while any changes to 0DCM figures will be subject to the change requirements of TS 6.14.
Therefore, the proposed changes to TS 5.1 are acceptable.
2.
TS 5.2 (Containment) would be deleted. The requirements contained in i
TS 5.2 are contained in BVPS-1 UFSAR Sections 5.2.1, 5.2.2, 5.2.4, and Table 14.3.3a and in BVPS-2 UFSAR Sections 3.8.1, 6.2.1, 6.2.4, and Table 6.2-3.
Details regarding containment leakage rates, containment air lock leakage rates, and containment structural integrity are retained in TSs 3/4.6.1.2, 3/4.6.1.3, and 3/4.6.1.6 to en:ure any changes that may significantly affect safety would require prior NRC review and approval.
Design features, which are being relocated from the TSs, would not have a significant effect on safety if altered or modified and are not otherwise required to be in the TSs pursuant to 10 CFR 50.36(c). Any changes to the UFSAR will be subject to the requirements of 10 CFR 50.59.
Therefore, the proposed deletion of TS 5.2 is acceptable.
3.
TS 5.3 (Reactor Core) would be renumbered to TS 5.2.
The text for renumbered TS 5.2.1 (Fuel Assemblies) and TS 5.2.2 (Control Rod Assemblies) would not be changed for either unit. The proposed changes are administrative only and are, therefore, acceptable.
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4.
TS 5.4 (Reactor Coolant System) would be deleted. The requirements contained in TS 5.4 are also contained in BVPS-1 UFSAR Section 4.1 and 4.2 and in BVPS-2 UFSAR Sections 5.2, 5.3, and 5.4.
Details regarding reactor coolant system leakage and structural integrity are retained in TSs 3/4.4.6.2 and 3/4.4.10 to ensure any changes that may significantly affect safety would require prior NRC review and approval.
Design features, which are being relocated from the TSs, would not have a significant effect on safety if altered or modified and are not otherwise required to be in the TSs pursuant to.10 CFR 50.36(c). Any changes to the UFSAR will be subject to the requirements of 10 CFR 50.59.
Therefore, the proposed deletion of TS 5.4 is acceptable.
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TS 5.5 (Emergency Core Cooling Systems) would be deleted. The requirements contained in TS 5.5 are also contained in UFSAR Section 6.3 for both units.
Details of the design features and operability requirements for the emergency core cooling system are retained in TSs 3/4.5.1, 3/4.5.2, 3/4.5.3, 3/4.5.4.1.1, 3/4.5.4.1.2, and 3/4.5.5 to ensure any changes that may significantly affect safety would require prior NRC review and approval. Design features, which are being relocated from the TSs, would not have a significant effect on safety if altered or modified and are not otherwise required to be in the TSs pursuant to 10 CFR 50.36(c). Any changes to the UFSAR will be subject to i
the requirements of 10 CFR 50.59. Therefore, the proposed deletion of TS 5.5 is acceptable.
6.
TS 5.6 (Fuel Storage) would be renumbered to TS 5.3.
The text for renumbered TS 5.3.1 (Criticality) would be replaced with TS 5.3.1.1 for the' spent fuel storage racks and with TS 5.3.1.2 for the new fuel storage racks.
The proposed revision to renumbered TS 5.3.1 would make its format consistent with NUP.5G-1431, Revision 1; TS 5.3.1.1 would contain the design requirements for the spent fuel storage racks and TS 5.3.1.2 would contain the design requirements for the new fuel storage racks.
Proposed TS 5.3.1.1.a would specify a maximum U-235 enrichment of spent fuel assemblies in the spent fuel racks as set forth in TS 3.9.14.
TS 3.9.14 specifies storage of spent fuel in the various regions of the spent fuel storage pool as a function of original enrichment percentage and fuel burnup. Although proposed TS 5.3.1.1.a does not specify a single enrichment value, as does NUREG-1431, Revision 1, proposed TS 5.3.1.1.a is acceptable since it is consistent with TS 3.9.14 which was issued as License Amendment No. 178 for BVPS-1 and as License Amendment No. 12 for BVPS-2.
Proposed TS 5.3.1.1.b would require the spent fuel storage racks be designed and maintained with K,,,tainties.
s 0.95 if flooded with unborated water including an allowance for uncer This requirement is equivalent to current TS 5.6.1.
Therefore, proposed TS 5.3.1.1.b is acceptable.
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i-Proposed TS 5.3.1.1.c specifies the spacing of fuel assemblies in storage
. racks. The proposed TS provides the same spacings as in part of current j
TS 5.6.1; therefore, proposed TS 5.3.1.1.c is acceptable.
Proposed TS 5.3.1.1.d would require that fuel assembly storage shall comply with the requirements of TS 3.9.14.
This is acceptable since TS
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3.9.14 provides adequate requirements for spent fuel storage.
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Proposed.TS 5.3.1.2.a would specify a maximum U-235 enrichment of 4.5 weight percent for BVPS-1 and 4.85 weight percent for BVPS-2 new fuel assemblies in the new fuel storage racks. These maximum enrichment i
values are acceptable since they are consistent with the maximum i
enrichment values and criticality analyses approved in License Amendment No. 114 for BVPS-1 and License Amendment No. 12 for BVPS-2.
l Proposed TS 5.3.1.2.b would require the new fuel storage racks be j
designed and maintained with K water including an allowance f.,, s 0.95 if fully flooded with unborated i
or uncertainties. This requirement is j
consistent with the criteria piovided in BVPS-1 UFSAR Section 9.12 and BVPS-2 UFSAR Section 9.1 and in the NRC's Standard Review Plan (NUREG-
-0800) Section 9.1.1.
Therefore, proposed TS 5.3.1.2.b is acceptable.
Proposed TS 5.3.1.2.c would require the new fJel storage racks be designed and maintained with k,,, s 0.95 if moderated by aqueous foam (low density optimum-moderation conditions) including an allowance for j
uncertainties.
This requirement is consistent with the criteria provided i
in BVPS-1 UFSAR Section 9.12 and BVPS-2 UFSAR Section 9.1 and in the i
NRC's Standard Review Plan (NUREG-0800) Section 9.1.1.
Therefore, proposed TS 5.3.1.2.c is acceptable.
Proposed TS 5.3.1.2.d would require the new fuel storage racks be 1
designed and maintained to provide a nominal 21-inch center-to-center i
spacing between fuel assemblies placed in the storage racks. This 4
requirement ensures that k is maintained s 0.95 (in accordance with the requirements of the NRI'#s Standard Review Plan (NUREG-0800)
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Section 9.1.1) and is consistert with the criteria provided in BVPS-1
.UFSAR Section 9.12 and BVPS-2 UFSAR Section 9.1.
Therefore, proposed TS 5.3.1.2.d is acceptable.
7.
TS 5.6.2 (Drainage) and TS 5.6.3 (Capacity) would be renumbered to TS 5.3.2 and TS 5.3.3, respectively; the text for these TSs would not be changed for either unit. The proposed changes are administrative only and are, therefore, acceptable.
8.
TS 5.7 (Seismic Classification) and TS 5.8 (Meteorological Tower Location) would be deleted from the TSs. The requirements contained in TS 5.7 are also contained in BVPS-1 UFSAR Appendix B and BVPS-2 UFSAR Section 3.7.
The location of the meteor'ological. tower is also provided in ODCM Figure 5-1.
The requirements of 9 CFR 50.36(c)(4) do not require the inclusion of the seismic c1t
.'ication of structures, systems, and components nor the inclus0
, the meteorological tower 1
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- location in TSs.
The seismic classification of structures, systems, and components is adequately specified in the UFSARs and the meteorological tower location is adequately specified in the ODCM. Any changes to the UFSARs will be subject to the requirements of 10 CFR 50.59 and any changes to the ODCM will be subject to the requirements of TS'6.14.
Therefore, the proposed deletion of TSs 5.7 and 5.8 is acceptable.
3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the Pennsylvania State official was notified of i.he proposed issuance of the amendments. The State official had no coments.
4.0 ENVIRONMENTAL CONSIDERATION
t The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR 1
Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant changa in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation i
exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public coment on such finding (61 FR 64384). Accordingly, the amendments meet 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 amendments.
5.0 CONCLUSION
The Comission' 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 the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor: Donald S. Brinkman Date: April 14, 1997
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