ML20236T176
| ML20236T176 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/17/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236T175 | List: |
| References | |
| NUDOCS 9807280006 | |
| Download: ML20236T176 (17) | |
Text
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. easas anni
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SAFETY EVALUATION BY THE OFFICE OF NUCI FAR REACTOR REGULATION RELATED TO AMENDMENT NO. 185 TO FACILITY OPERATING LICENSE NO. DPR-24 AND AMENDMENT NO. 189 TO FACILITY OPERATING LICENSE NO. DPR-27 WISCONSIN FtFCTRIC POWER COMPANY POINT BEACH NUCI FAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
By letters dated May 2,1995, October 12,1995, March 26,1996, December 15,1997, and May 27,1998, the Wisconsin Electric (WE) Power Company (the licensee) requested amendments to the Technical Specifications (TS) appended to Facility Operating License No. DPR 24 for Point Beach Nuclear Plant, Unit 1, and Facility Operating License No. DPR-27 for Point Beach Nuclear Plant, Unit 2. The proposed amendments (TSCR-172) would revise Table 15.4.1-1, " Minimum Frequencies For Checks, Calibrations, and Tests Of Instrument Channels," to change the test frequency of the containment high range radiation monitor, revise note 7, and revise item 36 to clarify which monitors in the radiation monitoring system (RMS)
. support current TS or meet the requirements of 10 CFR 50.36.
The May 27,1998, submittal provided additional clarifying information and updated TS pages.
i This information was within the scope of the original FederalRegisternotics and did not change the staff's initial no significant hazards considerations determination.
2.0 BACKGROUND
2.1 Relocation of TS l
Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to include TS as part of the license. The Commission's regulatory requirements related to the content of TS are set forth in 10 CFR 50.36. That regulation requires that the TS include items in five specific categories, including (1) safety limits, !imiting l
L safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) l surveillance requirements; (4) design features; and (5) administrative contro!s. However, the regulation does not specify the particular requirements to be included in a plant's TS.
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. Section 50.36 also specifies four criteria to be utilized in order to determine whether a limiting condition for operation, its surveillance requirements, and actions shall be included in the TS.
These are:
1.
Installed instrumentation that is used to detect, and mdicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; 2.
a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; 3.
a structure, system, or component that is part of the primary success path and which i
I functions or actuates to mitigate a design-basis accident or transient that either l
assumes the failure of or presents a challenge to the integrity of a fission product barrier; and 4.
a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The following TS that address radiation monitors are included in NUREG-1431, " Standard Technical Specifications Westinghouse Plants." The need to include radiation monitors in the TS is established by the consequences of the limiting DBA analysis and whether the control functions performed by the radiation monitor are credited in the accident analysis. If the radiatiori monitor is not relied upon in the analysis, the consequences must not exceed the consequences of a DBA.
TS 3.3.3 Post Accident Monitoring (PAM) Instrumentation includes containment area radiation monitors (High Range)
TS 3.3.5 Containment Ventilation isolation instrumentation includes containment radiation gaseous and particulate monitors TS 3.3.6 Control Room Emergency Air Treatment System Actuation instrumentation includes control room intake iodine, noble gas, and particulate radiation monitors i
TS 3.4.15 RCS Leakage Detection Instrumentation Includes containment atmosphere radioactivity monitors relied upon to detect leakage of reactor co61 ant into the containment. Plant vent gaseous or particulate radiation monitors need to be addressed if they perform a leakage detection function.
TS 3.7.7 Component Cooling Water System
(
Radioactivity monitor may need to be included if the system is not a normally l
closed system outside of containment and the radiation monitor provides a signal to ensure system closure.
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, TS 3.7.8 Service Water System Radioactivity monitors may need to be included in TS if the radiation monitors provide control input to isolate valves that prevent discharges.-
TS 3.7.g Control Room Emergency Air Treatment System includes gaseous, particulate, and iodine radiation monitors which result in actuation.
TS 3.7.10 Auxiliary Building Ventilation System includes noble gas, particulate, and iodine monitors for the plant vent stock which result in actuation of equipment.
2.2 Reduced Surveillance Requirements for Testino Durino Power Ooaration Generic Letter (GL) 93-05, "Line item Technical Specifications improvements to Reduce Surveillance Requirements for Testing During Power Operation," was issued to provide guidance to assist licensees in preparing a license amendment request to implement the recommendations for line-item TS improvements discussed in NUREG-1366, " improvements to Technical Specifications Surveillance Requirements." As discussed in NUREG-1366, the staff found that while the majority of the testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by reducing the amount of testing that the TS require during power operation.
Licensees can propose changes to extend surveillance intervals if the recommendations of NUREG-1366 are compatible with plant operating experience. Specifically, the GL recommends, "In order to decrease licensee burden and increase the availability of radiation monitors, change the monthly channel functional test to quarterly."
3.0 EVALUATION
' The licensee proposes to modify TS Table 15.4.1-1, " Minimum Frequencies For Checks, i
l Calibrations, and Tests of Instrument Channels," to change the frequencies for item 25, containment high range radiation monitors; revise item 36, " Radiation Monitoring System," to
. identify only those monitors that need to be in the TS and change frequencies; correct the reference to the definition of low power operation from 15.1.n to 15.1.m; and revise the i_
language for the overpressure mitigation system to the low temperature overpressure
' protection system.
3.1 Description of TS Raouirements TS 15.1.f defines the following terms used for instrumentation surveillance:
i Channel Check - Channel check is a qualitative determination of acceptable operability by observation of channel behavior during operation. This determination shall include comparison of the channel with other independent channels measuring the same variable.
. 1 Channel Functional Test - A channel functional test consists of injecting a simulated i
signal into the channel to verify that it is operable, including alarm and/or trip initiating
{
action.
j Channel Calibration - Channel calibration consists of the adjustment of channel output such that it responds, with acceptable range and accuracy, to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment action, alarm, or trip, and shall be deemed to include the channel functional test.
3.2 Description of Radiation Monitorina Svstem All radiation monitors listed on Tables 1 and 2 are connected through eight data acquisition modules to the RMS control terminal (CT). The CT continuously scans the associated RMS channels. If a channel changes from the " normal status," this would be readily apparent based on a status change on the RMS CT. This information is also relayed to the plant process computer system (PPCS.) The channel status indications include the following: NORMAL, FAILURE, UNINITIALIZED, MAINTENANCE / CALIBRATE, STANDBY, ALERT, HIGH ALARM AND Fall HIGH. A status change also causes a control room alarm on the C-20 auxiliary system instrument panel. The automatic monitoring of the associated channels by the RMS CT and PPCS assist in the rapid detection of channelinoperability. The performance of channel checks and channel calibration will ensure that the monitors themselves are functioning prcperly. The design of the RMS CT and the presence of alarms on the PPCS obviates the l
need to perform monthly testing. Additionally, the RMS at Point Beach is within the scope of the Maintenance Rule as provided for in 10 CFR 50.65, which requires trending of failure data.
l Currently, the radiation system monitors, based on plant operating data, are considered h!ghly reliable.
J Effluent monitors generally have an associated background monitor. The readings associated with the background monitor are subtracted from the radiation monitor reading displayed at the CT. At Point Beach the operability of the effluent monitor includes the operability ofits associated background monitor. Therefore, the background monitors are not included in the TS as separate monitors. The staff finds this to be acceptable.
3.3 _ Containment Hiah Ranae Radiation Monitors Table 15.4.1-1, item 25 for the containment high range radiation monitors,1(2)RE-126, 1(2)RE-127, and 1(2)RE-128, currently requires a check be performed each shift, calibration each refueling interval, and testing monthly. The licensee proposes to perform the check on a L
monthly basis during plant conditions when the monitors are required to be operable and to l
eliminate the table entry requiring a test on a monthly frequency. There is no proposed change to the calibration frequency. Based on the design of the RMS and its ability to alarm if the monitors fail, the licensee proposes to extend the interval for checking the monitors from each
. shift to monthly. Additionally, the licensee proposes to eliminate the testing requirement since these monitors are post-accident monitoring instrumentation that does not perform any trip or actuation function. The staff finds the changes to the surveillance requirements acceptable.
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3.4 RMS Changes t-i The RMS is a system of monitors that includes area monitors (Table 1), process monitors (Table 2), and special particulate, iodine, and noble gas monitors (Table 3). Since many of these monitors do not meet 50.36 requirements for inclusion in the TS, WE submitted TSCR-172 to retain only those monitors required to be in TS. The radiation monitors retained in the TS include: waste disposal system (WDS) liquid monitor (RE-218), waste distillate -
overboard monitor (RE-223), "A" main steam line release monitor (RE-231), "B" main steam line i
release monitor (RE-232), control room monitor (RE-101), control room noble gas monitor t
(RE-235), and air ejector monitor (RE-215).
i 3.4.1 Deletion of Area Radiation Monitors The area radiation monitors provide readings of radioactivity at various locations in the plant.
The area radiation monitors are used by the health physics department to ensere doses are i
l kept as low as reasonably achievable (ALARA). The Al. ARA program is included n TS 15.6.11,
" Radiation Monitoring Program.". The purpose of these monitors is to detect local mdiation levels, not to detect a significant abnormal degradation of the reactor coolant pressure boundary or to provide information that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The area monitors are not part of the primary success path which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Neither are the area monitors a component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. These monitors are not credited in any accident analyses. Since the area monitors do not meet any of the 10 CFR 50.36 requirements for inclusion in the TS and are controlled by plant procedures, the staff finds the deletion of the area monitors from the TS acceptable.
3.4.2 Evaluation of Process Monitors Radiation monitor 1(2)RE-211, containment air particulate monitor, indicates particulate activity inside containment or purge exhaust stack. Radiation monitor 1(2)RE-212, containment noble gas monitor, provides indication of containment or purge exhaust stack noble gas activity.
Radiation monitor 1(2)RE-211B provides background data for both RE-211 and RE-212.
The function of RE-212 is to provide containment ventilation isolation that closes purge valves, secures forced vent, and puts the monitor in recirculation. Normally, a radiation monitor that causes an automatic actuation would be required to be included in the TS. As discussed in the staff's safety evaluation for NUREG-0737, " Clarification of TMi Action Plan Requirements," Item II.E.4.2(7), the containment purge / vent isolation valves must close on a high radiation signal, and this provides the bases for the inclusion of these monitors in NUREG-1431, TS 3.3.5,
" Containment Ventilation isolation Instrumentation." However, the staff determined that Point Beach Units 1 and 2 satisfied the requirements of NUREG-0737 by maintaining the purge / vent isolation valves sealed closed during plant operation (hot shutdown through power operation).
These monitors are not credited in any accident analyses and do not meet any of the 10 CFR
,50.36 requirements forinclusion in the TS. Therefore, the staff finds the removal of the
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. containment air particulate monitors and the containment noble gas monitors from the TS acceptable.
RE-214 is provided to indicate high gaseous activity release from a gas decay tank or potential protected ares boundary (PAB) airbome activity. Final Safety Analysis Report (FSAR)
Section 14.2.3, " Accidental Release - Waste Gas," assumes that the activity is discharged to the atmosphere at ground level and is dispersed as a plume. Even though high readings on the monitor result in closure of the vent gas release valve and switching of the PAB vent discharge to the charcoal filters, no credit is taken for these actions in the accident analyses. This monitor is included in the Radiological Effluent Control Program Manual (RECM) and the Offsite Dose Calculation Manual (ODCM.) The monitor does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. Therefore, the staff finds the relocation of this monitor to the licensee-controlled documents acceptable.
1(2)RE-215 air ejector noble gas monitor is provided to indicate a steam generator primary-to-secondary leak. These radiation monitors are also sensitive to potential airbome radiation in the turbine hall. TS 15.3.1.D.8 requires that " Secondary coolant gross radioactivity shall be monitored continuously by an air ejector gas monitor." Therefore, the licensee has proposed retaining these monitors in the TS. The frequency for performing the check has been 3
revised to daily and footnoted to state that the check is not required during periods of refueling shutdown, but must be performed prior to reactor criticality if it has not been performed during the previous surveillance period. The licensee proposes to calibrate each monitor during the 1
respective refueling outage for its assigned unit which is consistent with the current calibration frequency. The test frequency for all monitors in the RMS is monthly. The licensee proposes to eliminate the testing requirement for the air ejector monitors. The elimination of the testing is
' based on the design of the RMS. The staff agrees that these monitors shall be retained in TS l
and that the changes associated with the check and calibration function are adequate. The j
staff further finds that additional testing is not required since the RMS has a self-checking i
function. Therefore, the staff finds the proposed changes acceptable.
I 1(2)RE-216 containment fan coolers service water liquid process monitor provides indication of potential contamination of cooling water (service water retum). This monitor is on the service I
water system that is considered a closed system inside of containment. The monitor is for indication only and provides no control function. 1(2)RE-216 and its associated background monitor,1(2)RE-216B, are included in Final Safety Analysis Report (FSAR) Section 11.2, the RECM, and the ODCM. The monitor does not meet any of the 10 CFR 50.36 requirements for
. inclusion in the TS. Therefore, the staff finds the relocation of this monitor to the licensee-controlled documents acceptable.
1(2)RE-217 component cooling water (CCW) liquid process monitor provides indication of CCW i
i contamination closes the CCW surge tank vent. The licensee does not credit this monitor in j
any accident analyses. The surge tank vent is isolated during power operation. The monitor i
does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. Therefore, the staff finds the removal of this monitor from the TS acceptable.
t Liquid process monitor, RE-218, monitors waste condensate activity being discharged. RE-218 and it associated background monitor, RE-2188, are used to detect radioactivityin the waste
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disposal system discharge. The monitor will cause discharge valve, RCV-18, to close. WE proposes to retain this monitor in the TS. WE proposes to extend the interval for the channel functional test from monthly to quarterly. The decreased frequency from monthly to quarterly for the channel functional test is justified based on plant operating experience. The l
performance of a source check prior to start of a release provides assurance that the channelis i
responding properly to a source of radiation. The continuous automatic monitoring of the l
associated channels by the RME CT and the PPCS assist the rapid detection of channel inoperability during a release. The quarterly channel functional test is consistent with the l
- channel functional test requirements for other channels that cause trip or initiation actions, such l
as, steam generator pressure and containment pressure. The proposed surveillance for l
RE-218 and RE-223 will continue to include channel checks each shift when a waste liquid release (discharge) is occurring. The staff concludes that the inclusion of these monitors in the TS based on WE's assessment of operating experience and the potential of releases to be l
significant to public health and safety, the changes in checking and calibration frequency, and the elimination of the testing frequency based on the design of the RMS CT and PPCS alarm functions are acceptable.
1(2)RE-219, steam generator blowdown liquid process monitor, provides indication of steam generator blowdown activity and steam generator tube leak rates. The monitor functions to shut blowdown valves, blowdown tank outlet valve, and steam generator sample valves. These l
monitors are set to prevent releases inside the plant, but the licensee does not credit these monitors for any accident analyses and the monitors do not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. The steam generator blowdown liquid process monitors are controlled by plant procedures. Changes to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds the deletion of the steam generator blowdown liquid process monitors from the TS acceptable.
RE-220 spent fuel pit heat exchanger service water liquid process monitor provides indication of service water contamination from a spent fuel pool heat exchanger tube leak. RE-220B provides background data for RE-220. This monitor provides intermediate radiation monitoring indication to assist in locating potential leakage sources. The monitor is not credited in any accident analyses and does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. Therefore, the staff finds the removal of this monitor from the TS acceptable.
RE-221 drumming area vent stack noble gas monitor indicates noble gas activity released from spent fuel pit and drumming area, which may be indicative of a potential PAB airbome release.
This monitor indicates activity from gaseous releases from the drumming area. The monitor i
has no control function. This effluent monitor does not meet any of the 10 CFR 50.36 l
requirements for inclusion in the TS. The licensee will control the monitor in accordance with the RECM and ODCM. Changes to plant documents and procedures are controlled in j
accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds the relocation of j
the effluent monitor to the licensee-controlled documents acceptable.
1(2)RE-222 steam generator blowdown tank outlet liquid process monitor shuts the blowdown i
valves and blowdown tank outlet valve upon receipt of a high radiation signal. These monitors are set to prevent releases inside the plant, but the licensee does not credit these monitors for i
i
. any accident analyses and the monitors do not meet any of the 10 CFR 50.36 requirements for inclusion iri the TS. The staff finds that the steam generator blowdown liquid process monitors are described in the FSAR and any changes are controlled in accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds the removal of these monitors from the TS acceptable.
RE-223 waste distillate discharge liquid process monitor monitors activity of waste distillate being discharged. If high radiation levels are detected, the monitor closes the discharge valve.
WE has determined that this monitor should be retained in the TS. The frequency for checking and calibrating the monitor remains the same as the current TS. The proposed frequency for testing is quarterly rather than monthly. As stated in GL 93-05, the staff found that while the majority of the testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by reducing the amount of testing that the TS require during power operation. WE's basis for extending the testing interval is based on the design of the RMS and the systems ability to assess faults and annunciate off normal conditions. The operability of the background monitor (RE-223B)is inherent in the operability of RE-223.The staff finds the retention of RE-223 in the TS and the extension of the testing interval acceptable.
RE-224 is the gas stripper building exhaust noble gas monitor. This monitor indicates activity from gaseous releases from letdown gas stripper building. The monitor has no control function.
This effluent monitor does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. The licensee will control the monitor in accordance with the RECM and ODCM. Changes l
to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds the relocation of the effluent monitor to the licensee-controlled documents acceptable.
RE-225 is the combined air ejector low range noble gas monitor. The purpose of this monitor is to monitor for potential indications of primary-to-secondary leaks in the steam generators. This monitor is redundant to monitors 1(2)RE-215. Therefore, the staff agrees that this redundant monitor does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS and can be controlled adequately by the RECM and ODCM. Changes to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds the relocation of this monitor to the licensee-controlled documents acceptable.
1(2)RE-229 service water discharge liquid process monitor monitort activity of service water discharge and provides no actuation function to isolate the discharge.1(2)RE-229B provides i
background data for RE-229. Operability of the background monitor is inherent in the definition
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l of operability of 1(2)RE-229. The staff concludes that the check, calibration, and testing I
requirements for this effluent monitor can be relocated from the TS since its function is
~ dequately described in the FSAR and the surveillance requirements included in the RECM and l
a the ODCM. Changes to plant documents and procedures are controlled in accordance with the l
requirements of 10 CFR 50.59. The monitor does not meet any of the 10 CFR 50.36 l
requirements for inclusion in the TS. Therefore, the staff finds the relocation of this monitor to the licensee-controlled documents acceptable.
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RE-230 retention pond discharge liquid process monitor monitors activity level in retention pond effluent and provides no actuation function to isolate the discharge. RE-2308 provides background data for RE-230. The staff concludes that the check, calibration, and testing requirements for this effluent monitor and its associated background monitor can be relocated from the TS since the monitor's function is adequately described in the FSAR and the surveillance requirements included in the RECM and the ODCM. Changes to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. The monitor does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS.
Therefore, the staff finds the relocation of this monitor to the licensee-controlled documents acceptable.
1(2)RE-231 for the "A" steam line atmospheric release monitors and 1(2)RE-232 for the "B" steam line atmospheric release monitors are being retained in the TS. These monitors were installed to meet the requirements of NUREG-0737 to provide the capability to assess releases via the main steam lines. WE proposes to decrease the frequency for checking the monitors from daily to monthly when the monitors are required to be operable. Additionally, the licensee proposes to delete the requirement to test monthly since these monitors are post-accident monitoring instrumentation that does not perform any trip or actuation function. The staff finds the retention of the monitors and the changes to the surveillance requirements e::aptable.
J RE-234, control room iodine monitor, monitors iodine activity in control room. RE-2348 provides background data for RE-234. Monitor RE-234 provides no control function and the monitor is not relied upon to provide protective actions. The monitor is not credited in any accident analyses and does not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. Therefore, the staff finds the removal of this monitor from the TS acceptable.
RE-235 is the control room noble gas monitor. It monitors noble gas activity in the control room and will cause a shift in the control room ventilation to the recirculation mode. The licensee proposes to retain this monitor in the TS. The monitor will be checked each shift, calibrated on a refueling interval frequency, and tested quarterly. The basis for increasing the testing from l
monthly to each shift is based on the design of the RMS to detect and annunciate monitor failure. The staff finds the proposed changes to be acceptable.
3.4.3 Evaluation of System-Level Particulate, lodine and Noble Gas (SPING) Monitors There are four SPING monitors (Unit 1 containment purge exhaust stack, Unit 2 containment l
purge exhaust stack, auxiliary building exhaust stack, and the radwaste packaging (drumming) l area exhaust stack. The sample points for each of these SPING units is downstream of the exhaust stack filters. Each SPING monitor has a data acquisition monitor (DAM) built into it, and each DAM is capable of serving nine detector inputs. Each DAM has a microcomputer that performs the task of data acquisition, history file management, operational status check, alarm determination, and interface with the input / output terminals.
Any of the following monitors can initiate a containment purge isolation:
1(2)RE-301 containment purge exhaust monitor'(beta particulate) 1(2)RE-303 containment purge exhaust morjitor (iodine)
. 1(2)RE-305 containment purge exhaust monitor (Iow range gas) indicates activity in containment purge exhaust 1(2)RE-306 (area monitor) t l
1(2)RE-307 (mid range exhaust) l 1(2)RE-309 (high range gas) i However, as discussed in the response to NUREG-0737, item II.E.4.2(7), the requirement that the containment purge and vent valves must close on a high radiation signal was resolved by keeping the valves sealed closed during plant operating modes including hot shutdown, hot standby, startup, and power operation. Therefore, these monitors do not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. The monitors are described in the FSAR, and are controlled using plant procedures. Changes to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. Therefore the staff finds these changes to be acceptable.
The following auxiliary building and drumming area exhaust monitors do not have a control function:
RE-311 beta particulate RE-313 iodine RE-315 low range gas (ODCM Table 2-2)
RE-316 area RE-317 mid range gas RE-319 high range gas RE-321 beta / particulate RE-323 iodine RE-325 low range gas (ODCM Table 2-2)
RE-326 area RE-327 mid range gas As discussed in the FSAR, Section 11.2.3, these isokinetic stack sampling system monitors provide the capability to sample both the auxiliary building vent stack and the drumming area vent stack for !odines and particulate during normal operations and accident conditions.
These monitors do not provide any automatic isolation signals and do not meet any of the 10 CFR 50.36 requirements for inclusion in the TS. The staff finds that the SPING monitors can be adequately controlled by plant procedures and by retaining the monitor description in the FSAR. Changes to plant documents and procedures are controlled in accordance with the requirements of 10 CFR 50.59. Therefore, the staff finds these changes to be acceptable.
3.4.4 Miscellaneous Chanaes The licensee submitted changes to correct the definition of low power operation from 15.1.n to i
15.1.m; and revise the language for the overpressure mitigation system (OMS) to the low temperature overpressure protection (LTOP) system. The definition included in 15.1.n is for the fire water suppression system whereas the definition included in 15.1.m is for low power operation. The change in the designation of the OMS to the LTOP system was included in TS
. Amendments 172/176. The failure to change the note in Table 15.4.1-1 was an administrative oversight. The staff finds the proposed administrative changes acceptable.
4.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Wisconsin State official was notified of the proposed ;ssuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
These ainendments change requirements with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (63 FR 25122). Accordingly, these 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 environment! impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
6.0 C.Q,NCLUSION 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 compllance with ths 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: Linda Gundrum Date: July 17, 1998 l
TABLE 1 RADIATION MONI's ORING SYSTEM - AREA MONITORS DETECTOR NO.
NAME INDICATION RE-101N control room monitor indicates dose rates in control room 1(2)RE-102 containment low range monitor provides dose rates within containment around access hatch RE-103 chemistry lab area monitor provides indication of dose rates in chemistry lab and associated hallways 1(2)RE-104 charging pumps low-range area indicates dose rates in hallways east of monitor charging pump cubicles RE-105 spent fuel pit low range area provides indication of dose rates in the monitor vicinity of spent fuel pit (affected by high radiation levels in containment) 1(2)RE-106 primary side sample room low indicates dose rate inside sample room range area mon. tor when sampling system is in operation 1(2)RE-107 seal table area monitor provides an indication of general dose rate near seal table RE-108 drumming station ares monitor provides dose rate indication within the drumming station 1(2)RE-109 post-accident sample line monitor provides an indication of failed fuel by monitoring the primary coolant sample activity RE-110 Safety injection (SI) pump roca provides an indication of the dose rate in low range monitor general area of Si pumps RE-111 C59 panel area monitor provides general area dose rate near C59 panel RE-112 central PAB indicates general area dose rate on PAB El.8' RE-113 PAB Elevation (El.) -19' area provides an indication of the dese rate in monitor PAB El. -19' sump and general area RE-114 CVCS holdup tank area monitor indicates general area dose rate in cubicle RE-116 letdown system valve gallery area indicates general area dose rate in monitor letdown valve ga!Iery 1(2)RM-126 unit 1(2) containment high range indication is via readout module in the 1(2)RM-127 radiation monitors computer room and on the auxiliary 1(2)RM-128 safety instrumentation panels
J I
1 TABLE 1-continued DETECTOR NO.
NAME INDICATION 1(2)RE-134 charging pump room high range provides an indication of general area l
area monitor dose rates in the event low range I
monitor saturates RE-135 spent fuel pit h;gh range area provides an indication of general area monitor dose rates in the event low range monitor saturates 1(2)RE-136 primary side sample room high provides an indication af general area range area monitor dose rates in the event low range i
monitor saturates I
RE-140 SI pump room high range are provides an indication of general area monitor dose rates in the event low range monitor naturates W Refer to Table 4 for control function I
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TABLE 2 RADIATION MONITORING SYSTEM - PROCESS MONITORS DETECTOR NO.
NAME INDICATION 1(2)RE-211 containment air particulate monitor indicates particulate activity inside containment or purge exhaust stack 1(2)RE-2118 background monitor for RE-211 background data for both RE 211 and RE-212 1(2)RE-2120) containment noble gas monitor provides indication of containment, or purge exhaust stack noble gas activity RE-214")
PAB indicates high gaseous actMty release from gas decay tanks or potential PAB airborne activity 1(2)RE-215 condenser air ejector noble gas indicative of stean generator primary-to-monitor secondary leak. May be indicative of potential airborne radiation exposure in turbine hall.
l (2)RE-216 1
containment fan coolers liquid provides indication of potential process monitor contamination of cooling water (service water retum) 1(2)RE-216B background monitor for 1RE-216 provides background data for RE-216 1(2)RE-2170) component cooling water liquid provides indication of component cooling process monitor water contamination RE-218")
waste disposal system discharge monitors waste condensate activity liquid process monitor being discharged RE-218B background monitor for RE-220 provides background data for RE-218 1(2)RE-219")
steam generator blowdown liquid provides indication of steam generator process monitor blowdown activity and steam generator tube leak rates 1(2)RE-2198 background monitor for RE-219 provides background data for RE-219 RE-220 spent fuel pit (SFP) heat provides indication of service water exchanger service water liquid contamination from a SFP heat process monitor exchanger tube leak RE-2208 background monitor for RE-220 provides background data for RE-220 RE-221 drumming area vent stack noble indicates noble gas activity released gas monitor from spent fuel pit and drumming area, which may be indicative of a potential PAB airbome release l
TABLE 2-continued i
DETECTOR NO.
NAME INDICATION I
1(2)RE-222")
steam generator blowdown tank steam generator blowdown tank outlet outlet liquid process monitor liquid process monitor RE-223")
waste distillate discharge liquid monitors activity of waste distillate being process monitor discharged 1
RE-223B background monitor for RE-223 provides background for RE-223 j
RE-224 gas stripper building exhaust noble indicates activity of gaseous release gas monitor from letdown gas stripper building RE-225 combined air ejector low range indicative of primary-to-secondary leak noble gas monitor in steam generators. may also indicate potential radiation exposure sources within turbine building i
RE-226 combined air ejector high range indicative of primary-to-secondary leak noble gas monitor in steam generators, may also indicate potential radiation exposure sources within turbine building 1(2)RE-229 service water discharge liquid monitors activity of service water process monitor discharge 1(2)RE-229B backgmund monitor for Re-229 provides background data for RE-229 RE-230 retention pond discharge liquid mMu s activity level in retention pond process monitor efErrit RE-230B background r"onitor for RE-230 provides background data for Re-230 1(2)RE-231 steam line "A" atmospheric release monitors activity of steam released -
monitor steam line "A" 1(2)RE-232 steam line "B" atmospheric release monitors activity of steam released -
monitor steam line "B:
RE-234 control room iodine monitor monitors iodine activity in control room RE-234B control room lodine and noble gas provides background data for RE-234 sample system background monitor RE-2350) control room noble gas monitor monitors noble gas activity in control mnm C)
Refer to Table 4 for control function i
L_______.________
TABLE 3 SPECIAL PARTICULATE, IODINE, AND NOBLE GAS MONITORS DETECTOR NO.
NAME INDICATION 1(2)RE-301 containment purge exhaust indicates activity in containment purge monitor (beta particulate) exhaust 1(2)RE-303 containment purge exhaust indicates activity in containment purge monitor (iodine) exhaust 1(2)RE-305")
containment purge exhaust indicates activity in containment purge monitor (Iow range gas) exhaust 1(2)RE-306 containment purge exhaust indicates activity in containment purgs monitor (area monitor) exhaust 1(2)RE-307 containment purge exha'Jst indicates activity in containment purge monitor (mid range gas) exhaust 1(2)RE-309 containment purge exhaust indicates activity in containment purge monitor (high range gas) exhaust RE-311 auxiliary building exhaust monitor indicates activity in auxiliary building (beta particulate) exhaust RE-313 auxiliary building exnaust monitor indicates activity in auxiliary (iodine) building exhaust l
RE-315 auxiliary building exhaust monitor indicates activity in auxiliary (low range gas) building exhaust i
RE-316 auxiliary building exhaust monitor indie,ates activity in auxiliary i
(area monitor) building exhaust RE-317 auxiliary building exhaust monitor indicates activity in auxiliary (mid range gas) building exhaust RE-319 auxiliary building exhaust monitor indicates activity in auxiliary building (high range gas) exhaust RE-321 drumming ares exhaust monitor indicates activity in drumming area (beta particulate) exhaust RE-323 -
drumming area exhaust monitor indicates activity in drumming area (iodine) exhaust RE-325 drumming area exhaust monitor indicates activity in drumming area (Iow range gas) exhaust RE-326 drumming area exhaust monitor indicates ac.tivity in drumming area (area monitor) exhaust RE 327 drumming area exhaust monitor indicates activity in drumming area (mid ranae a==)
exban=*
") Refer to Table 4 for control function
I TABLE 4 RADIATION MONITOR CHANNELS WITH CONTROL FUNCTIONS DETECTOR NO.
NAME INDICATION RE-101 controlloom area shifts control room ventilation to Mode 3 (100 percent recirculation) 1(2)RE-212 containment noble gas containment ventilation isolation closes purge valves, secures forced vent and puts monitor in recirculation RE-214 PAB vent closes vent gas release valve and switches PAB vent discharge to charcoal filters RE-217 component cooling water closes CCW surge tank vent RE-218 waste condensate overboard closes waste condensate pump valve 1(2)RE-21g steam generator blowdown shuts blowdown valves, blowdown tank outlet valve, and steam generator sample valves 1(2)RE-222 blowdown tank area shuts blowdown valves and blowdown tank outlet valve RE-223 waste distillate overboard closes discharge valve RE-235 centrol room noble gas shifts centrol room ventilation to Mode 3 (100 percent recirculation) l 1(2)RE-305 containment noble gas containment ventilation isolation l
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