ML19290D632
| ML19290D632 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/20/1980 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19290D617 | List: |
| References | |
| TAC-13038, TAC-13039, NUDOCS 8002220428 | |
| Download: ML19290D632 (8) | |
Text
{{#Wiki_filter:. Exhibit A Prairie Is. lard Nuclear Generating Plant License Amendment Request dated February 20 , 1980 Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 & -60 Pursuant to 10 CFR 50.59, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, Technical Specifications. Specification 3.10.E (Rod Misalignment Limitations) Proposed Changes
- 1. Change the first sentence of Specification 3.10.E.1 to read-
"If a full-length or part-length rod control cluster (RCC) assembly is misaligned from its bank as described in 3.10.E.2, the rod will be realigned or the core peaking factors shall be determined within 2 hours and Specification 3.10.B applied."
- 2. Add Specification - 3.10.E.2 as follows-
"2.(a) If the bank demand position is greater than or equal to 215 steps, or less than or equal to 30 steps, and the rod position indicator channel differs by more than 24 steps, that rod control cluster shall be considered misaligned.
(b) If the bank demand position is between 30 steps and 215 steps, and the rod position indicator channel differs by more than 12 steps, that RCCA shall be considered misaligned."
- 3. Change Specification 3.10.E.2 to read-
"3. If the misaligned rod control cluster is not realigned within a total of 8 hours the rod shall be considered inoperable.
Reason For Change By letter dated October 29, 1979, A Schwencer (NRC) to L 0 Mayer (NSP), the NRC Staff requested Northern States Power Company review the existing - Technical Specifications regarding RCCA misalignment to determine if control rods are required to be maintained within +12 steps indicated and rod position indication (RPI) system verified to be accurate within 12 steps. By letter dated December 5,1979, L 0 Mayer (NSP) to Director of Nuclear Reactor Regulation (NRC), NSP notified the NRC that it planned to submit a technical specification change. Safety Evaluation The individual rod position indicator (IRPI) channel readings as rods are withdrawn typically do not show exact agreement with the bank demand position stepcounter as shown in Figures 1-4. In Figure 1, the IRPI were calibrated to agree with bank demand position at 20 and 200 steps. In Figures 2-4, the IRPI were calibrated to agree with bank demand position at 20 and 210 steps, the ranges normally encountered when the plant is shut down 3 o02220 m g
or operating, respectively. 'Ihe maximum deviation from bank demand was 13 steps (Figure 3) in tests conducted at Hot Zero Power (HZP). As power is raised, the temperature in the vicinity of the RPI coils should increase and could cause possibly higher deviations. For this reason, agreement to within +12 steps of bank demand position cannot be assumed and specifications as 3.10.E.2 are proposed. Sensitivity of core behavior to rod misalignment is of greater significance when the rods are inserted further into the core because of the higher rod worth in that region. The safety analyses are typically conducted with the maximum F0 (2.32), a condition expected when rods are inserted closer to the insertion limit. Note that Technical Specification 3.10.B. limits F to 2.21 based on ECCS requirements so that anq F of 2.32 is not allowed.9 Safety analyses typically assume a ryecified scram reactivity and correspond-ing insertion limits. If rods are at the insert ion limit and misaligned excessively, the actual scram reactivity could be dif ferent from that assumed. Likewise, if rods are inserted into the central core region, a more profound ef fect on power distribution might be expected than if rods are placed in the peripheral regions, where rod worth is less. If the rods are nisaligned as described in revised Specification 3.10.E.2(a) or (b), rod realignment corrects the problem. If this is not done (or the readings are erroneous), determination of the core peaking factors provides assurance that the assumptions of the safety analyses (Fq and Fg) are complied with. On this basis, greater tolerance is allowed in the peripheral regions than in the central region. For these reasons and the fact that these changes are more restrictive than the current specification, there should be no significant effect on the public health and safety. D c) fh J JO hlh dhuu h.M h J[}b on [ Calibrated at 20 and 200 steps t-
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Exhibit B Prairie Island Nuclear Generating Plant License Amendment Request dated February 20, 1980 Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Exhibit B consists of revised pages of the Prairie Island Nuclear Generating Plant. Technical Specifications, Appendix A, as listed below: Page (TS- ) 3.10-5
TS.3.10-5 REV E. Rod Misalignment Limitations
- 1. If a full-length or part-length rod cluster control (RCC) assembly is misaligned from its bank as described in 3.10.E.2, the rod will l be realigned or the core power peaking factors shall be decermined within 2 hours, and Specification 3.10.B applied. If peaking factors are not determined within 2 hours, the high neugron flux trip setpoint shall be reduced to 85 percent of rating.
- 2. (a) If the bank demand position is greater than or equal to 215 steps, or less than or equal to 30 steps and the rod position indicator channel differs by more than 24 steps, that rod control cluster assembly (RCCA) shall be considered misaligned.
(b) If the bank demand position is between 30 and 215 steps and the rod position indicator channel differs by more than 12 steps, that RCCA shall be considered misaligned.
- 3. If the misaligned rod cluster control is not realigned within a total of 8 hours, the rod shall be declared inoperable.
F. Inoperable Rod Position Indicator Channels
- 1. If a rod position indicator (RPI) channel is out of service then (a) For operation between 50% and 100% of rating, the position of the RCC shall be checked directly by core instrumentation (excore detector and/or thermocouples and/or movable incore detectors) every shift or subsequent to rod motion exceeding a total of 24 steps, whichever occurs first.
(b) During operation below 50% of rating, no special monitoring is required.
- 2. The plant shall be brought to the hot shutdown condition should more than one RPI channel per sub-bank or more than two RPI channels per bank be found to be inoperable during power operation.
- 3. If a full length or part length rod having a rod position indicator channel out of service is found to be misaljgned from 1.a. above, then Specification 3.10 E. will be applied.
G. Inoperable Rod Limitations
- 1. An inoperable rod is a rod which (a) does not trip, (b) is declared inoperable under Specification 3.10 E. or 3.10 H. or (c) cannot be moved by its drive mechanism and cannot be corrected within 8 hours.
See footnote 2, page TS.3.10-4. See footnote 2, page TS.3.10-4.}}