ML20217K758
| ML20217K758 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/29/1998 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Sellman M WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-M92346, TAC-M92347, NUDOCS 9805040105 | |
| Download: ML20217K758 (4) | |
Text
c Michnl B. S;llm:n April 29,1998 Chi;f Nucirr Offictr Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RE: TECHNICAL SPECIFICATION CHANGE REQUESTS RELATING TO RADIATION MONITORS (TAC NOS. M92346 AND M92347)
Dear Mr. Sellman:
Additional information is needed to complete the review of Technical Specifications (TS)
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Change Request (TSCR)-172, submitted May 2,1995, as supplemented by letters dated i
October 12,1995, March 26,1996, and December 15,1997. The December 15,1997, submittal was in response to a request for additionalinformation issued August 15,1997.
This additional request for information is enclosed. A response is requested within 30 days of the date of this letter.
r Sincerely, ORIGINAL SIGNED BY Linda L. Gundrum, Project Manager Project Directorate lil-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation j
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Docket Nos. 50-266 and 50-301 i
Enclosure:
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cc w/ encl:
See next page DISTRIBUTION:
Docket File (50-266, 50-301) '
gt PUBLIC I
PDill-1 Reading E. Adensam (EGA1)
C. Jamerson L. Gundrum C. Miller i
OGC NE N EMB MM l
. McCormick-Barger, Rill DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTB92347.LTR 72,eceive a copy of this document, ind6cate in the bon "C" = Copy without attachment / enclosure "E"* Copy with attachment / enclosure "N"
- No copy OFFICE PM:PD31 lE LA:PD31 LD:PD31 NAME LGundrum:db f(d CJamerson (lf CACarpenteQf DATE 04/M /98 04/.11/98f/
04/ A /98 OFFif/AL RECORD COPY 9805040105 900429 PDR ADOCK 05000266 P
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's Mr. Michael B. Sellman Point Beach Nuclear Plant Wisconsin Electric Power Company Units 1 and 2 cc:
Mr. John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Washington, DC 20037-1128 l
Mr. Richard R. Grigg President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Scott A. Patuiski Site Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42
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Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 l
Madison, Wisconsin 53707-7854 Regional Administrator, Region ill U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office l
U.S. Nuclear Regulatory Commission 6612 Nuclear Road l
Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854 mmh me Madison, Wisconsin 53707-7854
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le REQUEST FOR ADDITIONAL INFORMATION 1.
The information included in Wisconsin Electric (WE) Power Company's December 15, 1997, submittal, did not supply sufficient information to conclude that the control room l
radiation monitors RE-101 and RE-235 should not remain in TS Table 15.4.1-1, l
" Minimum Frequencies for Checks, Calibrations, and Tests of instrument Channels."
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l Verify that the current control room dose analysis does rely on shifting the control room ventilation to Mode 4 (outside air filtration) to meet the dose guidelines of General Design Criterion 19. It would seem that the performance of checks, calibrations, and testing is required to assure system operability between system functional tests. If the monitors are added, justify any changes you propose regarding the table entries if different from the RMS entries. Specifically, if WE plans to increase the testing to quarterly in accordance with Generic Letter 93-05, "Line item Technical Specifications i
Improvements to Reduce Surveillance Requirements for Testing During Power
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Operation," then please discuss if the recommendations of NUREG-1366,
" improvements to Technical Specifications Surveillance Requirements," are compatible with plant operating experience similar to the justification of the main steam line i
l monitors given in WE's October 12,1995, submittal.
2.
The air ejector monitors 1(2)RE-215 or 1(2)RE-225 can provide indication of a steam generator primary-to-secondary leak or may be indicative of potential airbome radiation exposure in turbine hall. Currently, TS 15.3.1.D.8, states in part, " Secondary coolant gross radioactivity shall be monitored continuously by an air ejector gas monitor." To ensure that these monitors are operable, it would seem that performance of checks, j
calibrations, and testing of RE-215 and RE-225 currently required by TS Table 15.4.1-1 l
should be performed, if the monitors are added, justify any changes you propose regarding the table entries if different from the RMS entries. Specifically, if WE plans to l
increase the testing to quarterly in accordance with Generic Letter 93-05, then please discuss if the recommendations of NUREG-1366 are compatible with plant operating i
experience similar to the justification of the main steam line monitors given in WE's October 12,1995, submittal.
3.
The August 15,1997, request for additional information (RAI) requested WE to verify that the monitors included in the radiation monitoring system as described in the tables appended to the RAI were accurately identified, included in the lists provided with the l
RAI were 1(2)RE-126,1(2)RM-127, and 1(2)RM-128. Final Safety Analysis Report, Section 7.7.4.4," Containment High-Range Radiation," states
- Independent of the Radiation Monitoring System described in Section 11.2.3, three radiation detectors per containment structure sense high radiation levels which might exist in the post-accident environment." Please clarify that these monitors are not in the RMS and are included in Table 15.4.1-1 as line item 25.
4.
For RE-218, waste disposal system liquid monitor, and RE-233, waste distillate overboard monitor, please justify the change in the frequencies of the check, calibrate, and test columns. Specifically, if WE plans to increase the testing to quarterly in accordance with Generic Letter 93-05, then please discuss if the recommendations of NUREG-1366 are compatible with plant operating experience similar to the justification of the main steam line monitors given in WE's October 12,1995, submittal.
ENCLOSURE t
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l'. 5.
During the review of Table 15.4.1-1, the definitions of power (PWR) and ALL in the notation section of Table 15.4.1-1 incorrectly refers to 15.1.n for the definition of low power operation. The correct reference should be 15.1.m. Please verify that this is an administrative oversight and submit the appropriate changes.
6.
During the review of Table 15.4.1-1, notes 10 and 21 refer to the " Overpressure Mitigating System." This nomenclature was changed in the majority of the TS including Table 15.4.1-1, line item 32, as a result of Amendments 172 and 176. Please submit the appropriate TS changes to correct the inconsistency.
1 7.
The justification for removing RE-214 auxiliary building vent exhaust gas monitor is that it is presently not required for mitigation of any accident for Pt. Beach. However, TSCR-204 does credit auxiliary building releases being filtered and since no changes were proposed to add the auxiliary building monitors into the limiting conditions for operation and since no surveillance requirements were proposed to ensure the instrumentation remains checked, calibrated, or tested, please provide additional justification for removal from the TS or plans to address these requirements for TSCR-204.
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