ML20206M102
| ML20206M102 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/12/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206M090 | List: |
| References | |
| NUDOCS 8608200457 | |
| Download: ML20206M102 (10) | |
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UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.105 TO FACILITY OPERATING LICENSE NO. DPR-66 DUQUESNE LIGHT COMPANY-OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 INTRODUCTION By letter dated October 8,1984, and revised by letter dated February 3,1986, Duquesne Light Company (the licensee) submitted a proposed amendment to the technical specifications (Appendix A of Operating License No. DPR-66) for Beaver Valley Power Station, Unit No.1, to add requirements and bases for the reactor coolant system vents, to add instruments in the accident monitoring i
instrumentation section, to revise requirements for combustible gas control, and to add administrative requirements for a post-accident monitoring program.
The four proposed changes address technical specification changes requested by the NRC in Generic letter 83-37. No existing requirements are to be deleted.
We have reviewed the requested changes, and the results are as follows.
EVALUATION AND DISCUSSION 10 CFR 50.44(c)(3)(iii) specifies reouirements for reactor coolant system (RCS) vents. By letter dated September 8, 1983, the NRC issued a safety evaluation (SE) which found the licensee-proposed RCS vents to be technically acceptable.
The licensee proposes to incorporate limiting conditions for operation (LCOs),
surveillance requirements, and bases for the RCS vents which are consistent with Generic Letter 83-37 and the September 8,1983 SE. The proposed RCS vent requirements and bases are acceptable.
NUREG-0737 requires the installation of wide-range instruments to monitor containment pressure and water level under accident conditions. By letter dated May 17, 1983, the NRC issued an SE which found the licensee-proposed instruments for these parameters to be technically acceptable. The licensee proposed to add these instruments to the existing tables for Accident Monitoring Instrumentation (Table 3.3-11) and Accident Monitoring Instrumentation Surveillance Requirements (Table 4.3-7).
This is consistent with the May 17, 1983 SE and Generic Letter 83-37. The proposed addition of these requirements is acceptable.
8608200457 860812 PDR ADOCK 05000334 P
i Also, the licensee proposed to add an additional instrument to Table 3.3-11, in order to be consistent with Table 4.3-7.
Specifically, Amendment No. 45 added a surveillance requirement to calibrate the power-operated relief valve (PORV) control channels to paragraph 4.4.11.1.b and added the control channels to Table 4.3-7, Accident Monitoring Instrumentation Surveillance Requirements, for listing of frequency. Since the control channels are currently listed in Table 4.3-7 but not in Table 3.3-11, which contains the corresponding LCOs, the licensee proposed adding the control channels to Table 3.3-11 for consistency.
However, in an April 24, 1986 telephone conversation, the licensee representative, 1
S. Sovick, agreed to delete this proposed addition, because it would apply two conflicting LCOs to the PORV control channels.
NUREG-0737 requires the installation of wide-range instruments to monitor containment hydrogen under accident conditions. By letter dated May 17, 1983, the NRC issued an SE which found the licensee-proposed instruments for hydrogen l
monitoring to be technically acceptable.
Currently, Section 3/4.6.4, Combustible Gas Control, provides requirements for containment hydrogen analyzers. The licensee proposes to revise the existing requirements so that it is clear that the requirements apply to the wide-range hydrogen analyzers installed as part of NUREG-0737 and to add an additional action statement.
This is consistent with Generic Letter 83-37 and the May 17, 1983 SE. The proposed revision of the hydrogen monitoring requirements is acceptable.
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NUREG-0737 requires the implementation of a program for post-accident sampling, including training, procedures, and equipment maintenance. Generic Letter 83-37 provided an acceptable technical specification change for the administrative requirements for this program. The licensee proposes to add a new Section 6.8.4, consistent with Generic Letter 83-37, to accomplish this. The proposed addition of administrative requirements for the post-accident sampling program is acceptable.
We have evaluated the proposed changes to the technical specifications and conclude that these changes do not involve any physical change to the plant's safety-related structures, systems or components. Further, these changes do not increase the likelihood of a malfunction of safety-related equipment, or increase the consequences of an accident previously analyzed or create the possibility of a malfunction different from those previously evaluated.
Therefore, we find the licensee's requested changes to be acceptable, ENVIRONMENTAL CONSIDERATIONS j
This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 or change in a surveillance requirement. The staff has deterinined that this amendment involves no significant increase in the amounts, and no significant l
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 Connission has previously published a proposed finding that this amendment involves no significant hazards consideration and there has been no public courant on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR z51.22(c)(9).
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This amendment also involves changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(10). Pursuant to 10 CFR 651.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION We have 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, and (21 such activities will be conducted in compliance with the Commission'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.
Dated: August 12, 1986 Principal Contributor:
Glenn W. Meyer 6
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