ML14183A115
| ML14183A115 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/11/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A114 | List: |
| References | |
| NUDOCS 8804150125 | |
| Download: ML14183A115 (4) | |
Text
.o5 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION X
WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 116 TO FACILITY OPERATING LICENSE NO. DPR-23 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261
1.0 INTRODUCTION
By letter dated June 16, 1987, the Carolina Power & Light Company (CP&L, the licensee) requested a revision to Technical Specifications (TS) for the H. B. Robinson Steam Electric Plant, Unit 2, as set forth in Facility Operating License No. DPR-23.
The amendments request changes to the TS to
- 1) delete references to the number of neutron flux detectors, detector drives and thimbles in the Basis of Section 3.11 and the reference to the number of monitor channels in Section 4.11.1.4, 2) replace references to radiation monitor R-19 with R-19a, R-19b and R-19c in Tables 3.5-6 and 4.19-1, and 3) correct a typo graphical error in Table 4.1-1.
2.0 EVALUATION In a June 16, 1987 submittal, the licensee proposed revisions to the H. B. Robinson Unit 2 Technical Specifications. Each of the proposed changes is evaluated as follows:
la.
In the Basis for Section 3.11, Movable In-core Instruments, the proposed change is to delete the references to the specific number of detector drives (5), detectors (5) and thimbles (48).
The proposed change in the Basis would not affect the requirements of Specification 3.11 for the minimum number of accessible flux thimbles (15) and the minimum number of operable movable in-core detectors per quadrant (2) during recalibration of the excore symmetrical offset detection system. In addition, the proposed deletion does not change the description of "Movable Miniature Flux Detectors," as discussed in Section 7.7.1.5.2.2 of the Updated Final Safety Analysis Report (UFSAR). However,the deletion of referencing the specific numbers would prevent the potential of creating an ambiguity, e.g., when the exact number of operable thimbles.changes pD ABO4C, 05 PDR
)
-2 (while still within T.S. requirements and meets the functional description in the UFSAR).
Furthermore, this deletion does not affect the meaning and the purpose of the Basis as these numbers were only descriptions of the system.
lb. The proposed change would delete the reference to the number of total neutron flux monitoring channels (48) in Section 4.11.1.4.
However, the number of channels specified in Section 4.11.1.4 from which the power distribution map will be based remains the same (36 or more). Therefore, the proposed change would not affect the required number of channels to develop the power distribution map.
While the proposed change would not change the functional requirement of the neutron flux monitoring channels, it would prevent the potential for confusion regarding the actual total number of operable channels.
- 2) In accordance with commitments made during the review of Regulatory Guide 1.97 (R.G. 1.97), a plant modification has replaced the single radiation monitor (R-19) on the steam generator common blowdown header, with a separate monitor for each of the three individual steam generator blowdown lines, R-19a, R-19b and R-19c (CP&L Letters; NLS-84-509, December 31, 1984 and NLS-85-198; July 18, 1985).
The staff has previously reviewed the new configuration as part of the R.G. 1.97 review and found it to be acceptable (NRC Letter to CP&L; March 5, 1987).
The new configuration improves monitoring sensitivity by reducing dilution and provides additional information as to which steam generator is the source for primary coolant leakage. The proposed changes in Tables 3.5-6 and 4.19-1 would replace the refer ences to monitor R-19 with R-19a, R-19b and R-19c. These changes are consistent with the actual configuration which has been previously reviewed and accepted.
- 3) The retyped version of this page, submitted and subsequently issued as Amendment No. 97, inadvertently omitted remark (2) to Item 10. of Table 4.1-1. Item 10 was not involved with the change being requested, and the typographical error went undetected until subsequent review following the issuance of the amendment. The proposed change to correct the typographical error is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
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 Part 20. The 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 there should be no significant increase in individual or cumulative occupational radiation
-3 exposure. The Commission has previously published a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding. 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.
4.0 CONCLUSION
The Commission made a proposed determination that this amendment involves no significant hazards consideration which was published in the Federal Register (52 FR 35789) on September 23, 1987, and consulted with the State ofNorth Carolina. No public comments were received, and the State of North Carolina did not have any comments.
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 (2) such activities will be conducted in compliance with the Commission's regulations, and 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: S. J. Vias, RH R. Lo, NRR Dated:
April 11, 1988
AMENDMENT NO. 116 TO FACILITY OPERATING LICENSE NO. DPR-23, H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DISTRIBUTION:
Docket No. 261 NRC PDR Local PDR PD21 r/f S. Varga G. Lainas R. Lo OGC-B D. Hagan E. Jordan J. Partlow T. Barnhart (4)
Wanda Jones E. Butcher S. Vias, RII ACRS (10)
GPA/PA ARM/LFMB