IR 05000317/1990027
| ML20028H169 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/22/1990 |
| From: | Bores R, Jang J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028H168 | List: |
| References | |
| 50-317-90-27, 50-318-90-27, NUDOCS 9011150088 | |
| Download: ML20028H169 (12) | |
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U. S. NUCLEAR RDAH.A'IORY COMISSICN REDION I 50-317/90-27 Report Nos. 50-318/90-27 50-317 Docket Nos. 50-318 DPR-53 License Nos. DPR-69 Priority Category C
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Licensee:
Baltimore Gas aM Electric Company P.O. Box 1475 Baltimore, MarylaM 21203 Facility Nam: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection at:
Lusby, Marylard Inspection CoMucted: October 1-5, 1990 I
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Inspector:
J4 C. Jarg, Senior RadiatiorVSpecialist, date fluents Radiation Protection Section, acilities Radiation Safety a M Safeguards Branch, (FRSSB), Division of Radiation Safety and Safeguards (DRSS)
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4 R. J. Dores, 011ef, Effluents Radiation date Protection Section, FRSSB, DRSS Inspection Summary: Inspection of October 1-5,1990 (Otznbined Inspection Report Nos. 50-317/90-27 and 50-318/90-27)
Areas Inspected: Routine, unanncu d inspection of the gaseous and liquid
effluent control g.vpuns including management controls, calibration of effluent
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aM process nonitors, ventilation systems, ODCM, aM implementation of the above programs.
Results: Within the areas inspected, % violations were identified. These violations were identified relative to the failure to report the inoperable effluent unnitors in the Semiannual Effluent Reports (Section 4.3 of this report) and the failure to maintain records for effluent nonitor calibrations
.(Section 8.0-of this report). The latter item met the criteria for a non-cited violation.
90111!iOO88 polo 2p PDR sDOCK 05000j17 O
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DETAILS 1.0 Irdividuals contacted 1.1 Principal _ Licensee Personnel
- A. Anuje, QL.slity Assurance
- P. Crinigan, General Supervisor-<hemistry
- R. Denton, Plar.t General Manager, Calvert Cliffs Nuclear Power Plant
- G. Detter, Nuclo.? Regulatory Matters
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C. Dunkerly, Surveillance %st Program Manager
- C. Earls, 0)cmistry Supervisor
- P. Katz, Technical Support Superinterdent
- L. Ianagoite, Caapliance Ergineer D. Innkor, Work Group Imader, System Ergineerirg Group S. Hutson, Supervisor, Radiological Cbntrol Operations S. Moore, Primary System Ergineer (Contractor)
- D. Huth, Licensing Ergineer M. Polak, Primary System Engineer D. Ross, Test Bauipnent Supervisor J. Sites, E&C Functional Surveillance Test Coordinator J. Snyder, isor, Procedures ard Support-E&C Pr ipal Engineer
- R. Sydnor,iak, 01emistry Services
- J.
Szymkow
- S. Welp, Performance Engineer
- R. Werderlich, Nuclear Operations Superintendent 1.2 NRC Personnel
- L. Nicholson,. Senior Resident Inspector
- Denotes those individuals present at the exit meetirg on 1990. '1he inspector also interviewed other licensee Och 5,inc1tdirg rembers of the Electric & Controls (E&C) staff, employees engineering staff, and chemistry staff durirg this inspection.
2.0 Purpose
'1he purpose of this routine inspection was to review the licensee's ability to control ard quantify radioactive liquids, gases, ard particulates during normal ard emenJency operations.
3.0 Review of Previously Identiflod Items
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Unresolved Item (50-317/89-29-01 and 50-318/89-31-01) Retrieval of (Closed)ibration results for gaseous ard liquid effluent Ironitors.
'Ihe 1988 cal licensee was not able to retrieve the calibration results for those effluent monitors. 'Ihis item is closed administratively.
(See Section 8.0 of this inspection report for detail.)
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4.0 Management Controls 4.1 Program Changes Since the licensee reorganized on October 1,1990, the inspector reviewed the new organization for administration of effluent control programs. Changes made during this reorganization were discussed with the licensee.
The inspector determined that the effluent controls program had not changed because of this reorganization.
Responsibilities remained the same as during the last inspection, conducted in November 1989.
4.2 Audits The inspector reviewed the results of a quality assurance audit documented in Audit Report Number 90-11.
This audit covered the areas of the Offsite Dose Calculation Manual (00CM), gaseous release permits li radiological environmental monitoring,quidrelersepermitsmeteorological moniforing program, and Technica S)ecification compliance and surveillance of unmonitored effluents.
T1e inspector noted that the audit was performed by qualified auditors and appeared to be a thorough assessment of the effluent controls.
The audit identified six (6) ding to these findings. findings; none of sa program.
The licensee was respon The significance.
inspector also noted that the licensee was using a tracking system for the open items.
No violations were identified.
4.3 Review of Semiannual Reports -
The inspector reviewed the Semiannual Effluent Reports for the second half of 1989 and the first half of 1990.
These reports released-radioactivity for liquid and gaseous effluents,provided. total including projected radiation dose to the public as required.
Through review of these reports,-the inspector noted that the licensee did not report inoperable effluent monitors in the Semiannual Effluent Release Reports. The inoperable effluent monitors were Unit 2 Steam Generator Blowdown Effluent Monitor (inoperable since August 26, 1990), anc Waste Gas Holdup System Monitor (te gas holdup system 1989, Licuid_ Radwaste Effluent Monitor (inoperable since March 12, inoperable since March 12, 1990)
The liquid radwaste effluent and was l
moniho.rs-are common for-both units.
Sections 3.3.3.9 and 3.3.3.10 of the Technical Specifications,which discuss, respectively, radioactive gas ous and liquid -effluent monitoring instrumentation require, in part in the event the monitoring instruments become inoperable, that the licensee "... exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain'in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner." Contrary to the above, the licensee did not report or explain the reasons of the above
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inoperab1A effluent nonitors:in the Senniannual Effluent Release Ihe-inspector stated that the failure to rard. the above Repoacts. ' ' status in the Semiannual Radioactive Effluent Release Reports is
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W lan violation of Sections 3.3.3.4 and 3.3.3.10 of the 'IW::hnical
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ications (50-317/90-27-01; 50-318/90-27-01).
5.0[ L_icpid Effluent Ocritrols Mtres to-determine the -
'Ibe-inspector reviewed the-licensee's gl Specification (TS) requirements inplementaticm of the following 'IW:hnica for-both units.
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o TS,3/4.11.1.1,'"
d Effluents, Or su h ation" i
- o TS 3/4.11.1.2,."Li Effluents,-Dose".
o TS 3/4.11'.1=.3, "Li id Radwaste Treatment System"
o-TS 3/4.11.4, "'Ibtal Dose" l
o TS. 6.17, "Offaite Dose Calculation Manual (ODCM)"
- 'Ihe inspector also reviewed selected liquid discharge permits, including.
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1sanpling frequencies, analytica11 data, and: dose assessment results.. ;'Ibe inag=+- determined.that the. licensee met Technical Specification f '.
requir m ents in this' area.
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.6.0L Gaseous Effluent controls:
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'Iho. inspector reviewed the licensee's h to determine thel
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tion of the follcuing 'IW:hnical Specifications (TS) for. both a
o-TS 3/4.11~ 2.1',c "namarnia Effluents, Dose Rate" t!
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. o tTS :3/4.'11'.2.2, '" Dose-Noble daaaa" t
io TS(3/4.11.2.3,L" Dose-Iodine-131:and Radionuclidesiin Particulate -
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i o TS 3/4.11.2.4,,"canama Radwaste Treatment > System" '
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i o TS 3/4.11'.2.5, "Ikplosive Gas Mixturu"'
F o?TS 3/4'.11.2.6 r." Gas' Storage Tanks"-
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- o TS 3/4'.11.4.
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o TS.6.17,i"Offaite Dose Calculation Manual l(ODCM)"
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h!1nspector! reviewed selected gaseous discharge permits including.,..
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m eanalytical data, Land dose aaaaaamant results.: h inspector found that the-
J-licensee followed rvc dures to ocuply with the Technical Specification
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requirements.= No violations were identified in this: area'.
m yw 17LO lInplementation of the'0DCM and: Effluent Ocritrols.
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W Iinspector reviewed the-licensee's alarm / trip.setpoint calculation--
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.~ methodology-ocntainedlin the ODCM for. the liquid and rJaaama; effluent
L monitors.- Sections 1.1 ard 1.2 of the ODCM.hibe the.setpoint.
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_ calculation methods for liquid an:1 gaseous effluent acnitors, respectively.
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5 Durirg the review of the setpoint calculation equations, the inspector noted that the licensee had used the fixed distribution percentage of radionuclides derived frun the previous release data for the alarWtrip setpoint calculations.
In another wortis, the licensee had uscd the sam alarWtrip setpoints for the liquid ard gaseous efnuent monitors. The
- inspector, therefore, reviewod the analytical results of the grab sanples (liquid ard gaseous effluent sanples prior to release) which were attached to the release pennits. The inspector noted that the distribution percentages of the radionuclides ard the numbers of radionuclides identified in the effluent samples were not sam as listed in the OD04.
The inspector dierM with the licensee alarWtrip setpoint calculation methodology contained in the OD04. Tim inspector stated that the alarWtrip setpoint calculations should be performd for each release basod on the analytical results of the grab samples ard the setpoints should b2 changed as needed, based on those calculations. The inspector also notcd that the OD04 did not describe the alarm and trip setpoint calculations separately. Currently, the licensee uses the same setpoint for the alar.n ard trip functions.
Ilowever, during the review of the liquid release permits, the inspector noted that the licensee had calculated the alana setpoints required by procedures. Based on the above review, the inspector stated that the following weaknesses should be evaluated ard corrections should be irrorporated in the OD04. Its limnsee agruod to evaluate ard update the OD04 in the futurn to reflect the actual releases ard associatcd procedures. It should be noted that this item does not impact on the environment or public health ard safety.
o Review the currunt OD04 ard associated procedures for the technical adequacy to conduct the liquid ard gaseous effluent programs.
o Define the setpoint for the alarm ard the trip, ard list
.those setpoint calculation methodologies in the 0D04.
o Describe in the OD:H ard radioactive liquid and gaseous release permits the alarm and trip setpoint techniques to be used prior to each release, o Ensure that the alarm and trip setpoint calculations are based on the analytical results of the offluent grab samples, not based on-the historical data.
The im -tr stated the above items will be reviewed during a subsequent im on (50-317/90-27-02; 50-318/90-27-02).
The inspector Memed with the licensee leak surveys for the Refueling Water Storage Tanks (RWrs) because IMrs are the potential source for an unmonitored release to the environment. In fact, the licensee identified a small leak (Unit 2 IMF) on September 7,1989 through a weekly ruxtine survey conducted by the Radiological Control-Department. The inspector reviewod the analytical results for contaminated soil / pebble and smear
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.g les collected during the licensee's response to this leakage. The
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ytical tediniques were good.
lhe licensee repaired the leak and -
packaged the contaminated soi)/ pebbles:in.55-gallon dnans to be shipped to
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the burial site.' Based on the above review,:the following. conclusions were
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made by the inspector.
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o The licensee conducted an effective routine enviim-=dal survey,
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and, consequently,-the licensee was able to identify the-
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o There was no negative:inpact on the environment and/or the public health and safety.;
8.0- Calibration ~of Effluent ~and Prmana Monitors The inspector reviewed the licensee's s M arus and-the most recent
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- oalibration results for both units to determine the inplementation of the
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74chnical Specificaticri requirements for the following monitors..
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o Wide Ranipe Hable Gas Monitoring System ' Unit 1 oMainSteamLineRadiationMonitorsiUnits1&2-
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' o Steam Generator Blowdown. Discharge Monitors,: Units 1 & 2 o Waste Gas Effluent Monitor,' n=nnr1 System for'both units:
o Liquid Effluent Monitor, Connon System for both unit
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- During the review of onlibration g-#eines and results of the above
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effluent /suc.ss monitors, the inspector noted1that the calibration results.
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were within the licensee's. acceptance criteria.
However, the inspector'
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, identified the following weaknesses and' stated that these items should be omsideredifor incorporation in the calibration prmwhires.-
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o Plateau diecks should be performed to determine the operating high;
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o At least three-(3) radionuclide sources should be used to determine
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the ilinearity. and: conversion factors.i Currently,cthe licensee.uses_
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'o StatisHeml analyses such!as: linear regression, shouldlbe performed i
toverifythelinearity..
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The licensee statedLthat these items'will be. evaluated and incorporated in -
the onlibration procedures, as appropriate in conjunction with-tne system j
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upgrading in the future.= -::7he r stated that the g wtire updatel
- su will be tuviewed during sni inspections.< No violatims were g
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~ During the previous'3nspection-conducted on November 13-17, 1989, the
inspector noted that the licensee was not able to retrieve the most recent y
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calibration results for the Waste Gas lloldup System Honitor (RI-2191) aM the Licpid Radwaste Effluent Manitor (RI-2201). The licensee statM that Prt>oodure STP-M-567-0, " Radiological -
immuental 7bchnical Specifications (IEIS)", was used to calibrate the e two effluent monitors. The
- mpr stated that this was an unresolved itan perding retrieval of the calloration results and subsequent ruview by the NRC (50-317/89-29-01; 50-318/89-31-01). The licensee res to this unresolved item on Nm*ar 27,1989 including co
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've actions taken. The licensee, however, could rot retrieve the calibration results. Section 6.10.1.d of the 7bchnical Specifications requires that records of surveillance activities inspections and calibration required by these Technical Specifications shall be retained for at least five years.
Failure to keep the above monitor calibration recortls is an apparent violation of Section 6.10.1.d of the 7bchnical Specifications. Ilowever, the licensee calibrated these monitors on November 18, 1989 as part of the corrective action.
Durity this inspection, the impr tuviewed the corrective actions aM the inspector dotarinined that the corrective actions were thorough and the calibration results were within the licensee's acceptance criteria.
110 wever, failure to retain the calibration recortis is considered a non-cited violation in that (1) it was identified by the licensoe; (2) it fits into Severity level IV or V; (3) it was not reportable; (4) the licensoe took aggressive actions to correct the deficiency and to prevent futurn recurrence; and (5) this was the first occurrence of this type of event. Consequently, no notice of violation will be issued aM this issue is considered closed (50-317/90-27-03; 50-318/90-27-03).
9.0 Urgradiro Status of the Radiation Monitorirn Systems (INS)
The inspector noted that the licensee has been pursuirg the evaluation and upgrading plans of the RMS vigorously since last inspection conducted on November 13-17, 1989. A contractor perfomed an extensive evaluation of the existing INS and identified several weaknesses of the IM3, including calibration technique, lack of trurxiing analyses, numerous ur@mmnted nodifications, various stages of system deterioration, aM low operational reliability. Based on the evaluation results and IM-endations, the licensee established short term corrective actions (in pwguss), short-
. term projects, and long term projects. The inspector reviewed these projccts and determined that the licensco is pursuing these projects vigorously in the right direction, o Short-7brm Projects: Expedit short-term corrective actions.
Perform primary calibrations for effluent monitors.
o long-Term Projects: Replace or upgrade the existiry BMS.
The inspector also noted that the Plant Operations Safety Review Cmrnittee (IOSRC) was following these projects as an open item. It should be noted that the members of IOSRC are the senior managers frcm each departmen,
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G Tim inspector stated that the trackiry of these short-and long-term projects by the POSRC was an excellent management ocanitment to upgrade the INS. The inspector also stated that the progress of these projects will be reviewed during subsequent inspections.
10.0 Ventilation Systems The irbW reviewed the licensee's most remnt test results to determino the htplenentation of the followiry Technical Specification (TS)
requirements for both units.
o TS 3/4.6.3, " Containment, Iodine Ecmoval System" o TS 3/4.6.6, " Penetration Room Exhaust Air Filtration System" o TS 3/4.7.6, " Control Rom Dnergercy Ventilation System" o TS 3/4.7.7, "EOCS Punp Rom Exhaust Air Filtration System" o TS 3/4.9.12, " Spent Fuel Pool Ventilation System" The inspector reviewed the following inspection and test results.
o Visual Inspection o In-place Irak Test for HEPA o In-place Irak 7bst for Charcoal o Pressure Drop Test o Air Capacity Test o Iaboratory Tests for the Iodine collection Efficiency The above test results reviewed by the inspector were within the Technical Specification requirements. The irLW furtimr noted that the licensee had a good understanding of test purposes and current irria?.ry practicos.
No violations were identified.
11.0 Exit Interview The inspector mot with licensee representatives (denoted in Section 1.1) at the conclusion of the inspection on October 5,1990. The inspector summarized the purpose, scopo, and findings of the inspectio.w
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REPORT HOURS 1.' Operations 7. Outages-
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