ML16161A338
| ML16161A338 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/28/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16161A337 | List: |
| References | |
| NUDOCS 9905040282 | |
| Download: ML16161A338 (3) | |
Text
PAM Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION G.1
- 1. Wide Range Neutron Flux 2
H
- 2. RCS Hot Leg Temperature 2
H
- 3. RCS Hot Leg Level 2
1
- 4. RCS Pressure (Wide Range) 2 H
- 5. Reactor Vessel Head Level 2
I
- 6. Containment Sump Water Level (Wide Range) 2 H
- 7. Containment Pressure (Wide Range) 2 H
- 8. Containment Isolation Valve Position 2 pert a
fl ow H
- 9. Containment Area Radiation (High Range) 2
- 10. Containment Hydrogen Concentration 2
H
- 11.
Pressurizer Level 2
H
- 12. Steam Generator Water Level 2 per SG H
- 13. Steam Generator Pressure 2 per SG H
- 14. Borated Water Storage Tank Water Level 2
H
- 15. Upper Surge Tank Level 2
H
- 16. Core Exit Temperature 2 independent sets of 5(d)
H
- 17. Subcooting Monitor 2
H
- 18. HPI System Flow 1 per train NA
- 19. LPI System Flow 1 per train NA
- 20. Reactor Building Spray Flow 1 per train NA
- 21.
Emergency Feedwater Flow 2 per SG H
- 22. Low Pressure Service Water Flow to LPI 1 per train NA Coolers (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.
(c)
Position indication requirements apply only to containment isolation valves that are electrically control led.
(d) The subcooling margin monitor takes the average of the five highest CETs for each of. the ICCM trains.
9905040282 990428 PDR ADOCK 0500026 P
PDR OCONEE UNITS 1, 2, & 3 3.3.8-5 Amendment Nos. 91 n )
304 Unit 3
pS
~ pRE UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
304 TO FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO.
304 TO FACILITY OPERATING LICENSE DPR-47 AND AMENDMENT NO. 304 TO FACILITY OPERATING LICENSE DPR-55 DUKE ENERGY CORPORATION OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
By letter dated March 1, 1999, Duke Energy Corporation (the licensee) submitted a request for changes to the Oconee Nuclear Station (ONS), Units 1, 2, and 3, Technical Specifications (TS).
The requested changes would revise the number of required channels shown in TS Table 3.3.8-1, "Post Accident Monitoring Instrumentation" for the Reactor Coolant System (RCS) Hot Leg Temperature function from "2 per loop" to "2."
The licensee stated that during the ONS Improved Technical Specification (ITS) conversion program per NUREG-1430, Revision 1, "B&W Plant Standard Technical Specifications," the RCS Hot Leg Temperature function was incorrectly adopted to include two channels per loop.
However, there are only two qualified channels per ONS nuclear unit for this function. This was previously documented in the ONS Updated Final Safety Analysis Report (UFSAR) and also in a letter from the licensee dated September 28, 1984, in response to Supplement 1 to NUREG-0737 (report for Regulatory Guide 1.97 implementation).
2.0 EVALUATION The original ONS Units 1, 2, and 3 TS did not include the Hot Leg Water Temperature instrument channels in the post-accident monitoring (PAM) instrumentation table. In a letter dated September 28, 1984, the licensee provided a report showing that the ONS Units' plant specific variables were in compliance with Regulatory Guide 1.97, Revision 2. With regard to RCS Hot Leg Water Temperature, the report stated that two qualified (Quality Assurance Category 1) channels of wide range RCS Hot Leg Water Temperature indication would be installed.
During the ONS ITS conversion in 1998, the licensee consolidated Regulatory Guide 1.97 Category 1 and Type A variables into one specification (ITS Section 3.3.8) and added Category 1 or Type A variables that were previously not included in the existing TS. In the process of the ITS conversion, the licensee incorrectly adopted the wording of NUREG-1 430, Revision 1, Table 3.3.8-1 requirement for two channels of the RCS Hot Leg Temperature
-2 loop for the PAM function. The staff has verified that in the UFSAR Section 7.5.2.16 and also in the report submitted by letter dated September 28, 1984, the licensee committed to two qualified wide range RCS Hot Leg Temperature instrument channels per nuclear unit for the PAM function. The staff has concluded that this was the accepted licensing basis for ONS 1, 2, and 3 design and that the ITS was worded incorrectly.
3.0
SUMMARY
The change discussed in this submittal corrects errors made during the ITS conversion.
Licensees are not required to adopt more strict requirements when converting the TS to ITS.
The proposed change does not involve a physical alternation of the plant, no new or different equipment is being installed, and no installed equipment is being operated in a new or different manner. Furthermore, no setpoints for parameters that initiate protective or mitigative action are being changed. The proposed change agrees with the UFSAR and the plant design basis.
Therefore, the staff finds the proposed change to TS Table 3.3.8-1 item 2 to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements 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 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 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 (64 FR 14281). 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.
6.0 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 proposed 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: Hulbert Li Date:
April 28, 1999