ML20094P963
| ML20094P963 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/15/1995 |
| From: | Crane K DUKE POWER CO. |
| To: | |
| References | |
| PROC-951115, NUDOCS 9511300273 | |
| Download: ML20094P963 (16) | |
Text
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ML";Tu .
ilORITY NORMAL N AL stess47 Usee pel-LEss nEceriEarf is omEnunes DUKE POWER COMPANY .'
2756 J B JONES MG01WC DATE; 11/1";/05 m3759 U' S' NUCLEAR ' REG' WASH ,- DC DOCUMENTTRANSMITTAL FORM ooCuMENT TRANSMITTAL
- 9A ~1? A 0297 NRC REGION II LIRRARY ATL ^
9665 VIC NERSES,USNRC, WASHINGTON,0C 2532 MCG NRC INSP G F MAXWELL MG01A 35194 GARY M BARKER, MG01CH aAconomON [YES hNO 11137 MARK W BELL, MG010P
REFERENCE:
o En AcunoWWEoOEREEIETnEQUNIED hYES
'l3016 ROBIN J BELL MG010P 15599 RICHARD F MORRIS, MG010P MCGUIRE NUCLEAR STATION F GA OR OmER ACKNOWLEDGEMENT REQUtRED PLEASE
'M2665 GEORGE A COOK, MG010P SELECTED LICENSEE $*ES$REN W RETURN NWM OR E
'l5248 HUBERT C. DAMERON, MG030T COMMITMENTS MANUAL McGuh Nudear StaNon P 7m 6057 JIMMY H DIAL MG010P Hagers Ferry Road II Hursersyme,NorthCaronna 20078 il 33 Rec'd ey 0.t.
' 7) 81 PACF A nr A DOCUMENT NO. QA
" *C 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 TOTAL SLC 16.9 NA 11/15/95 MADM-03 V1 V1 V1 V1 V1 V1 V1 V1 V1 V1 V1 V1 74 SLC 16.11 NA 11/15/95 1
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49 REMARKS:
T C MCMEEKIN g\t VICE PRESIDENT MCGUIRE NUCLEAR STATION Dg 9511300273 951115 \
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() November 13, 1995 To: All Holders of the Selected Licensee Commitments Manual Please find attached a revision to the Selected Licensee Commitments Manual. This revision corrects typographical errors and adds references.
Your copy of the manual should be revised as follows:
i Remove these pages: Insert these pages:
List of Effective Pages List of Effective Pages Revision 6 Revision 7 Page 16.9-10, -11 Page 16.9-10, -11 Page 16.11-48, -52, -53, Page 16.11-48, -52, -53
-55, -56 -55, -56 Questions or problems should be directed to Kay Crane, McGuire Regulatory Compliance at extension 4306.
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'McGuire Regulatory Compliance O
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McGuire Nuclear Station O Selected Licensee Comunitments List of Effective Pages Page Revision Date LOEP Tab List of Effective Pages 7 1 through 7 '
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) 16.9 AUXILIARY SYSTEMS FIRE PROTECTION SYSTEMS 16.9-5 4 FIRE RATED ASSEMBLIES COMMITMENT
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.All. fire' rated assemblies and other fire barriers) separating (walls, floors / ceilings, cable tray enclosures -
l' 1
- redundant analyzed Post Fire Safe Shutdown Equipment or,
- Control Complex (i.e.,of Control Room, f from the remainder the plant or, Cable Rooms and Battery Rooms) safety from non-safety related areas or, 2
i j
- containment from non-containment areas, .
)
! 1 and all sealing devices (fire doors, fire windows , fire dampe'rs,. cable, piping penetrations and ventilation shall be OPERABLE. duct penetration seals) in fire rated assembly APPLICABILITY: At all times.
! l REMEDIAL ACTION: l l
- a. . With one or more of the above required fire rated assemblies l
- and/or sealing devices inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either I establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly )
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. [- and establish an hourly fire watch patrol. .
j j TESTING REQUIREMENTS:
a.
,At least once per 18 months the above required fire rated ,
assemblies and penetration sealing devices shall be verified !
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, 0,PERABLE,'by performing a visual inspection ofs i F. , The exposed surfaces of each fire rated assembly, -
i 11.
i Each fire window / fire damper /and associated hardware, and Lit. At least 10% of each type of sealed penetration. If a seal is found degraded to inoperable status, a. visual inspection of an additional 10% of each type of sealed penetration shall be made. This inspection process shall continue until a 10% sample with no inoperable seals is found. Samples
- shall be selected such that each penetration seal will be inspected every '15 . years.
b.
Each of the above required fire doors shall be verified OPERABLE
- by inspecting the automatic hold-open, release and closing mechanisms verifying:
and latches at least once..per 6 months, and by i.
That each unlocked fire door without electrical supervisione r is closed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, e
- 11. That doors with automatic hold-open and release mechanisms
, /-'S are free to obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> _and ,
performing a functional test at least once per 18 honths, .
s, 16.9-10 I
-~ 11292:: -
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iii. That each locked closed fire door is hlosed at least once per 7 days, and
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( ) iv. The OPERADILITY of the Fire Door Supervision System for each
's,
/ electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days.
REFERENCES:
- 1) McGuire FSAR, Chapter 9.5.1 ~ ~
- 2) McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D
- 3) McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B
- 4) McGuire Fire Protection Review, as revised
- 5) McGuire SER Supplement 6, Chapter 9.5.1. and Appendix C
- 6) McGuire Facility Operation Licenses, Unit 1 License Condition C.(4) and Unit 2 License Condition C.(7)
- 7) Door Schedules - MC-1108-01, MC-1208-01-01, -02, -03, -04, -05 and
-06.
- 8) Fire Plan Drawings - MC-1384-07 series BASES:
/ h The functional integrity of the fire rated assemblies, including
(,,) associated penetration seals, ensures that fires will be confined or adequately retarde'd so that the following criteria is achieved:
Fire will not damage redundant analyzed Post Fire Safe Shutdown equipment, Fire will not spread from the balance of plant to the control Complex, l
- Fire areas.
will not spread from non-safety related areas to safety related i
- Fire will not spread from non-containment areas to containment areas. l The. fire related assemblies and associated penetration seals are a l passive element in the facility fire protection program and are subject to periodic inspections.
i Fire rated assemblies, including associated penetration seals (fire .
doors, fire windows, fire dampers, cable, piping and ventilation duct penetration seals) are considered operable when the visually observed condition is not degraded to a point that the assembly cannot perform the function that is intended. For fire rated assemblies that are j I
questionable, an evaluation shall be performed to determine the cause of any identified abnormal change in appearance or abnormal degradation and the effect perform itsoffunction.
thi's change on the ability of the fire rated assembly to During periods of time when a fire rated assembly is not operable, either: (1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or (2) the fire detectors on 'at least one side of the affected barrier must be verified OPERABLE and an hourly g-~g fire watch patrol established until the barrier is restored to operable status.
i l
w_/ This Selected Licensee Commitment is part of the McGuire Fire Protection Program and therefore subject to the' provisions of McGuire Facility Operating License conditions C.(4) (Unit 1) and C.(7) (Unit 2). ,
16.9-11 Q
11/95 ..
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16.11 RADIOLOGICAL EFFLUENT MONITORING
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RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-13 MONITORING PROGRAM COMMITMENT The Radioactive Environmental Monitoring Program shall be conducted as speci-fled in Table 16.11-7.
APPLICABILITY: At all times.
REMEDIAL ACTION:
- a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 16.11-7, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radio- ' '
logical Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for pre-venting a recurrence.
- b. With the level of radioactivity in an environmental sampling medium g
( at a specified location exceeding the reporting levels of Table 16.11-8 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLCs 16.11-6, 16.11-8, and 16.11-9. When more than one of the radionuclides in Table 16.11-8 are detected in the sampling medium, this report shall be submitted if:
concentration (1) , concentration (2) + ***> 1.0 limit 1cvel (2) 1,imit level (1)
When radionuclides other than those in Table 16.11-8 are detected-and are the result of plant effluents, this report shall be sub-mitted if the potential annual dose
- to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of SLCs 16.11-6, 16.11-8 and 16.11-9. This report is not required if the measured
' level of radioactivity was nof. the result of plant effluents; how-ever, in such an event, the condition shall be reported and des-
' cribed in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report'.
1 l- 11/95
' 16.11-48
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TABLE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATHWAY OF ANALYSIS AND/0R SAMPLE SAMPLE LOCATIONS (1) COLLECTION FREQUENCY
- 2. Airborne Samples from five locations: Continuous sampler Radiciodine Canister:
Radiciodine and I-131 analysis weekly.
Particulates Three samples from close to the operation with sample thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if required by dust Particulate Sampler:
highest calculated annual average groundlevel D/Q. loading. Gross beta radio-activity analysis followi filter change;gGamma One sample from the vicinity of isotopic analysis (5) a community having the highest calculated annual average of composite (by groundlovel D/Q.
location) quarterly.
One sample from a control location, as for example 15-30 km distant and in the .;
least prev direction.gntwind
- 3. Waterborne i
- a. Surface (0) One sample upstream. Compositesamplgver , Gammaisgpic .
1-month period. analysis monthly.
One sample downstream.
Composite for tritium -
analysis quarterly.
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16.11-52 11/95
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TABLE 16.11-7 (Page 3 of 7) ,
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE '
EXPOSURE PATHWAY SAMPLES AND . SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS (1) COLLECTION FREQUENCY OF ANALYSIS
- b. Ground Samples from one or two sourc Quarterly. Gamma isotopic (5) only if likely to be affected and tritium analysis quarterly.
- c. Drinking One sample of each of one to Composite san I-131 analysis on each three of the nearest water 2-weekperiodgover when composite when_the. dose supplies that could be affected I-131 analysis is calculated for the con- -;
by its discharge. performed, monthly sumption of the water is '
composite otherwise. greater One sample from a control -
year.L9)than 1 aremforper Composite location. l .
grossbetaandgag isotopic analyses monthly. Composite for t
. tritium analysis quarterly. i
- d. Sediment One sample f. rom dowpstream area Semiannually.
from with existing or potential Gammaisgpic !
analysis shoreline recreational value. semiannually.
16.11-53 11/95 l
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TABLE 16.11-7 (Page 5 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS (g) COLLECTION FREQUENCY OF ANALYSIS
- c. Food -
One sample of each principal At time of harvest (10) . Gamma is pic Products class of food products from any analyses on edible area that is irrigated by water portion. ,
in which liquid plant wastes have been discharged. -
Samples of three different kinds Monthl'y when available. Gamma isotopic (5) and of broad leaf vegetation grown I-131 analysis, nearest each of two different offsite locations of highest predicted annual average groundlevel D/Q if milk sampling is not performed.
One sample of each of the Monthly when available. Gamma isotopic (5) and similar broad leaf vegetation I-131 analysis.
grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed.
11/95 16.11-55
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(v) V V TABLE 16.11-7 (Page 6 of 7)
TABLE NOTATION (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 16.11-7 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," Octcber 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of an Licensee Event Report, identify the cause of the unavailability of samples for that pathway and identify the new locations (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The forty stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g.,
at an ocean site, some sections will be over water s'o that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
(3) The purpose of this sample is to obtain background information. ~
If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
16.11-56 11/95