ML20094Q002
| ML20094Q002 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/15/1995 |
| From: | Crane K DUKE POWER CO. |
| To: | |
| References | |
| PROC-951115-01, PROC-951115-1, NUDOCS 9511300311 | |
| Download: ML20094Q002 (106) | |
Text
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'l 0085 G A COPP EC050 DATE:
11/15/95
'l4189 WAYNE M H0YLE, MG010P DOCUMENTTRANSMITTALFORM ooCUMENTTRANSMITTAL *
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REFERENCE:
hYES 41896 J S MURANSKY EC08H oneen AcstuL-neousnee 110794 NSRB STAFF EC05N HCGUIRE NUCLEAR STATION F GA OR OTHER ACKNOWLEDGEMENT REQUIRED PLEASE 03609 L K CRIMINGER RP SUPV MG01RP SELECTED LICENSEE SuT}NRECEM BY N MS N OR W 1113744 MCG OIR SIM (LINDSAY) MG030T COMMITMENTS MANUAL McGuke Nuchmar StaNon 1213044 MCG DOC CNTRL MISC MAN MG02DM P.
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1310422 MCG SAFETY REVIEW GROUP MG01SR nag.,s reevy noad
- 1815312 Z L TAYLOR-CNOIRC Hurnemosormcam m7s 05)6593 D E HOLDEN MG03A2
~ 0812257 R A HARRIS MG02ME Recd ay osi.
H773759 U S' NUCLEAR REG WASH,.DC 0816299 J. SPENCER HACKNEY MG010P PAGF 1
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DOCUMENT NO.
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QUAUTY CH ECKE0 B C REMARKS:
T C MCMEEKIN VICE PRESIDENT j
9511300311 951115
~
MCGUIRE NUCLEAR STATION 0
DR ADOCK 05 9
BY v^v L CP^MC MGe1RC KLC/CJe
/N 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:
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.
'Kay L. Crane, i
'McGuire Regulatory Compliance i
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i 4
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Selected Licensee Comunitments List of Effective Pages.
Page Revision Date LOEP Tab List of Effective Pages 7
1 through 7 Tib~ 16. 0 16.0-1 16.0-2 Tab 16.1
- 16.1-1 Tab 16.2 16.2-1 3/91' 16.2-2 5/91 16.2-3 16.2-4 Tab 16.3
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16.3-1 Tab 16.4
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l'6. 9 L AUXILIARY SYSTEMS I
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FIRE PROTECTION SYSTEMS
'16.9-5
-FIRE RATED ASSEMBLIES
. i 3
i COMMITMENT; q
- a
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1All fire" rated assemblies-(walls, floors / cell'ings, cable tray' enclosures t
and other fire barriers)-separating l
- redundant analyzed Post Fire safe shutdown Equipment or,
[
-
- Control Complex (i.e., control Room, Cable Rooms and ~ Battery Rooms) from the remainder of the plant or,
-* safety from non-safety related areas or,.
- containment from non-containment areas, l
.and all sealing devices'(fire doors, fire windows, fire dampe'rs,, cable, l
piping and ventilation duct penetration seals) in-fire rated assembly l
-penetrations shall be OPERABLE.
. APPLICABILITY: At all times.
6 i
REMEDIAL ACTION:
With one or more of the above required fire rated assemblies a.
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 establish a continuous fire watch on at least one side of
.the affected assembly, or verify the OPERABILITY of fire j
detectors on at least one side of the inoperable assembly
' ~
and establish an hourly fire watch patrol.
j TESTING REQUIREMENTS:
l
,At least once per 18 months the.Sbove required fire rated a.
. assemblies and penetration sealing devices shall be verified
~
OPERABLE, by performing a visual' inspection of
- D.
The. exposed surfaces of each fire rated assembly, -
11.
Each fire window / fire damper /and associated hardware, and 111. At least 10% of each type of sealed penetration. If a seal I
is found degraded to inoperable status, a visual inspection o'
additional 10% of each type of sealed penetration mL be made.' This inspection process shall continue until i
a los sample with no inoperable seals is.found. Samples shall be selected such that each penetration seal will be inspected every '15. years.
i b.
. Each of the above required fire doors shall be verified OPERABLE
.by inspecting the automatic hold-open, release and closing i
mechanisms and latches at least once_.per 6 months, and by i
verifying i
i L.'
That each unlocked fire door without electrical supervisione is' clos'ed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
-11.
That doors with automatic hold-open and release mechanisms
.are free to obstructions at least once per 24'houre and, perfo in t*
- a functional test at least once per 18 %onths, s
~
16.9-10 I
yy/95 ~
""'~~.*2.L..
111.
Thateachlockedclosedfiredoorishlosedat least once
' ~ ~
per 7 days, and
[)
iv.
\\ _/
The OPERABILITY of the Fire Door Supervision System for each 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 - HC-1108-01, HC-1208-01-01, -02,
-03,
-04,
-05 and
-06, 8)
Fire Plan Drawings - HC-1384-07 series BASES:
[m] 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,
- Fire will not spread from non-safety related areas to safety related areas.
Fire will not spread from non-containment areas to containment areas.
The, fire related assemblies and associated penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
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 questionable, an evaluation shall be performed to determine the cause of cny identified abnormal change in appearance or abnormal degradation and the effect of this change on the ability of the fire rated assembly to perform its function.
During periods of time when a fire rated assembly is not operable, eithers (1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or (2) the fire detectors on at leas,t one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established until the barrier is restored to operable ctatus.
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'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) [Udit 2].*
16.9-11
t t :
16.11 RADIOLOGICAL EFFLUENT MONITORING l
L RADIOLOGICAL ENVIRONMENTAL MONITORING a,
f l16/11-13 MONITORING PROGRAM i
COMMITMENT The Radioactive Environmental Monitoring Program shall be conducted as spect-e fled.in Table 16.11-7.
APPLICABILITY:.At all times.-
i
' REMEDIAL ACTION:
With the Radiological Environmental Monitoring Program not being l
a.
conducted as specified in Table 16.11-7, in lieu of a Licensee Event Report, prepare and submit to the Consiission, in the Annual Radio-logical Environmental Operating Report, a description of the reasons
~
l
.for not conducting the program as required and the plans for pre-l I
+
venting a recurrence.
4 i
With the level of radioactivity.in an environmental sampling medium l\\'
-b.
at a specified location exceeding the reporting levels of Table 4
16.11-8 when averaged over any calendar quarter, in lieu of a e
Licensee Event Report, prepare and submit to the Commission within i
30 days a Special Report that defines the corrective actions to be l
taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year i
limits of SLCs 16.11-6, 16.11-8, and 16.11-9. When more than one of l
the radionuclides'in Table 16.11-8 are detected in the sampling l
medium, this report shall be submitted if:
concentration (1), concentration (2) + ***> 1.0 1,imit level (1) limit level (2)
When radionuclides other than' those in Table 16.11-8 are detected-and are the result of plant effluents, this report shall be sub-
~
l mi tted 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, 1
16.11-8 and 16.11-9. This report is not required if the measured level of radioactivity was not! the result of plant effluents; how-j 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'.
11/95-
'~
16.11-48
l l
TABLE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
NUMBER OF l
REPRESENTATIVE SAMPLING AND
. TYPE AND FREQUENCY SAMPLES AND l
EXPOSURE PATHWAY SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE 2.
Airborne e
Radiciodine and Samples from five locations:
Continuous sampler Radiciodine Canister:-
Particulates Three samples from close to the
~ operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or I
in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
average groundlevel D/Q.
loading.
Gross beta radio-activity analysis followi filter f
Gamma change; l
One sample from the vicinity of isotG :c analysis (5) a community hcving the highest calculated annual average of composite (by location) quarterly.
groundlevel D/Q.
1 One sample from a control location, as for example 15-30 km distant and in the direction.gntwind least prev I
3.
Waterborne I
f Surface (6)
One sample upstream.
Compositesamplgver Gammaisgpic-a.
One sample downstream.
1-month period.
analysis monthly.
Composite for tritium analysis quarterly.
i l
~
16.11-52 11/95 i
_.. _ _. _.. ~ _. _.... _
TABLE 16.11-7 (Page 3 of 7)
RADIOLOGICAL ENVIR0letENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS {g)
COLLECTION FREQUENCY OF ANALYSIS Samples from one or two sourc Quarterly.
Gamma isotopic (5)-
b.
Ground onlyiflikelytobeaffectedg) and tritium analysis quarterly.
j c.
Drinking One sample of each of one to Composite s over I-131 analysis on each 2-weekperiogd three of the nearest water 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.
year.19)than 1 arem per greater One sample from a control Composite for l
location.
grossbetaandgag-i isotopic analyses monthly. Composite for-tritium analysis quarterly.
1 d.
Sediment One sample f. rom downstream area Semiannually.
Gammaisgpic from with existing or potential
' analysis i
shoreline recreational value.
semiannually.
i l
1 16.11-53 11/95 j
O O
O TABLE 16.11-7 (Page 5 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE I
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS c.
Food One sample of each principal At time of harvest (10)
Gamma isotopic i
Products class of food products from any analysesW on edible area that is irrigated by water portion.
in which liquid plant wastes have been discharged.
i Samples of three different kir.us Monthly when available.
Gama isotopic (5) and of broad leaf vegetation g own 1-131 analysis.
nearest each of two difierent offsite locations, of highest predicted annual average i
groundlevel D/Q if milk i
sampling is not performed.
One sample of each of the Menthly when available.
Gama isotopicIS) 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.
i 11/95 16.11-55
-m
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TABLE 16.11-7 (Pags 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 i
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," October 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 locatica 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.
4 16.11-56 1I/95
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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:
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.
f 7KIy L. Crane,
'McGuire Regulatory Compliance 9
a D
4 McGuire Nuclear Station selected Licensee commitments List of Effective Pages 2
Page.
Revision'Date LOEP Tab List of Effective Pages 7
3 1 through 7 l
Tab 16.0.
16.0-1 I
16.0-2 I
Tab 16.1 16.1-1 i
Tab 16.2 1
l 16.2-1 3/91 l
i-16.2-2 5/91 1
1 16.2-3 l
16.2-4 Tab 16.3 16.3-1 e
1 Tab 16.4 i
Tab 16.5 1
16.5-1 01/94 16.5-2 01/94 16.5-3 3/93
]
16.5-4 3/93 16.5-5 3/93 4
16.5-6 3/93
]
16.5-7 3/93 16.5-8 3/93
[
l i
16.5-9 3/93 16.5-10 3/93 Tab 16.6 i O Tah 16.*7 16.7-1 8/95 16.7-2 8/95 Revision 7
i r
2 Page
' Revision Date j
16.7-3 8/95 s
1 16.7-4s B/95 16.7-5 8/95 t
l 16.7-6 8/95 16.7-7 B /.95
.16.7-8 8/95 16.7-9 8/95 16.7-101 8/95 16.7-11 8/95
~ 16.7-12 8/95 16.7-13 8/95 1
16.7-14 8/95
' Tab 16.8 i
16.8-1 10/90 l
}
Table 16.8-la 1 of 28 10/94
~
Table 16.8-la 2 of 28 10/94 Table 16.8-la 3 of 28 10/94 r
1 Table 16.8-la 4 of 28 10/94 1
4 Table 16.8-la 5 of 28 10/94 i
Table'16.8-la 6 of 28 10/94 i
Table 16.8-la 7 of 28 10/94
{
Table 16.8-la 8 of 28 10/94 1
Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28 10/94 1
Table 16.8-la 11 of 28 10/94 i
Table 16.8-la 12 of 28 10/94
-Table 16.8-la 13 of 28 10/94 4
Table 16.8-la 14 of 28 10/94 i
Table 16.8-la 15 of 28 10/94 3
Table 16.8-la 16 of 28-10/94 l
O Table'16.8-la 17 of 28 10/94 i
Table 16.8-la 18 of'2B 10/94 i
. Table 16.8-la 19 of 28 10/94
'l l
Revision 7 t
2 i
T
' ymq
'?ays Revision Date
. C/!
. Table 16.8-la 20 of 28 10/94 4
- Tabiti16.8-la'21 of 28 10/94
. Table 16,8-la 22 of'28 10/94 l
Table 16.8-la 23 of 28' 10/94 l
Table 16.8-la 24 of 28-10/94 Table 16.8-la 25 of 28 10/94 Table 16.8-la 26 of 28 10/94 Table'16.8-la 27 of 28 10/94 Table 16.8-la 28 ofl28 10/94 f
' Table 16.8-1b 1 of 30-10/94 f
. Table 16.8-1b 2 of 30 10/94 Table 16.8-1b 3 of 30 10/94
. Table 16.8-1b 4 of 30-10/94 Table 16.8-1b 5 of 30 10/94 Table 16.8-1b 6 of 30 10/94 Table 16.8-1b' 7 of 30 10/94 Table 16.8-1b 8 of 30 10/94 Table 16.8-1b 9 of 30 10/94 i
Table 16.8-1b 10 of 30 10/94 Table 16.8-1b 11 of 30 10/94 Table 16.8-1b 12 of 30 10/94 Table 16.8-1b 13 of 30 10/94 Table 16.8-1b 14 of 30 10/94 Table 16.8-1b 15 of 30 10/94 Table.16.8-1b 16 of 30 10/94 r
Table 16.8-1b 17 of 30 10/94 4-Table 16.8-lb 18 of 30 10/94 Table 16.8-1b 19 of 30 10/94 l
Table 16.8-1b 20 of 30-10/94 i
- Table 16.8-1b 21 of 30 10/94 l
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Table.16.8-lb 22 of 30 10/94
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Table 16.8-1b 23 of 30 10/94 Table 16.8-1b 24'of 30 10/94 Revision 7 3
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Table 16.8-1b 25 of 30:
10/94 l
4 Table 16.8-1b 26 of 30' 10/94' i,
i
. Table 16.8-1b'27 of 30
'10/94 f
Table 16.8-1b 28 of 30 10/94:
-Table-16.8-lb 29 of 30 10/94 i
Table 16.8-lb 30 of 30' 10/94 Tab ~16.9 T
16.9-1 2/91 I
j_
- 16.9-2 i
~16.9,
3.
'16.9-4 f
~16.9-5 s-i Table 16.9-1 j
16.9-6 l
16.9-7 i
16.9-8.
- 16.9-9 5
2 Table 16.9-2 8/90 i
Table 16.9-2 (cont'd) 1 16.9 11/95
~16.9-11~
11/95 i
[.
16.9-12 12/90 I
1- '
16.9-13 i
l 16.9-14 i
Table 16.9-3 12/90 f
Table 16.9-3 (cont'd).
12/90-I i
Table 16.9-3 (cont'd) 12/90
(
f Table 16.9-3 (cont'd) 2/95-Table 16.9-3-(cont'd) 2/95 4
t Table 16.9-3.(cont'd) i j-as' 16.9-15 ~
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i 16.9-18
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Table 16.9-4 Table 16.9-5 l
16.'9-20 08/93 16.'9-21' 08/93 16.9-22 Tab 16.10 s
. Tab 16.11 f16.11 9/93 1
16.11-2 9/93
.16.11-3
!.~
9/93 i
16.11-4' 9/94 16.11-5 9/93 16.11-6 9/93 16.11-7 9/93
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16.11-13 9/93 16.11-14 9/93 1
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Page-Revision Date-16.11-24 9/93 16.11-25 9/93 16.11-26
- 9/93
'16.11-27, 9/93 16'11-28 9/93
'16.11-29 9/93
'16.11-30 9/93 l
16.11-31 9/93-16.11-32
- 9/93 16.11-33 9/93 16.11-34 1. 12/93 16.11-35 12/93 16.11-36 12/93 -
-16.11-37 12/93 16.11-38 9/93 16.11 9/93 16.11-40 9/93 16.11-41 9/93 16.11-42 9/93 16.11-43 9/93 16.11-44 9/93 16.11-45 9/93 16.11-46 9/93 16.11-47 9/93 16.11-48 11/95 16.11-49 9/93 16.11-50 9/93 16.11-51 9/93 16.11-52_
11/95 16.11-53 11/95
-*s 15.11-54' 9/93 j
16.11-55.
11/95
'16.11-56' 11/95
-1
- Revision 7 r
6=
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r Page Revision Date tl V 16.11-57 9/93 16.11-58 9/93 16.11-59 9/93 16.11-60 9/93 16.11-61 9/93 16.11-62 9/93, 16.11-63 9/93 16.11-64 9/93 16.11-65 9/93 16.11-66 9/93
'16.11-67 9/93 16.11-68 9/93 Tab 16.12 Tab 16.13 16.13-1
/
Tab 16.14 Tab 16.15 Appendix Tab 1
2 3
4 5
6 7
O Revision 7 7
~
r 4
5 L
i s
16.9 AUXILIARY SYSTEMS I
FIRE PROTECTION SYSTEMS i
16.9-5 FIRE RATED ASSEMBLIES COMMITMENT 4
_---__-~~------------_,---_--------_
All fire rated assemblies (walls, floors / ceilings, cable tray enclosures j
and other fire barriers) separatit.g i
b i
i
- - redundant analyzed Post Fire Safe Shutdown Equipment or, l
'* Control complex'(i.e., Control Room, Cable Rooms and Battery Rooms) from.the remainder of the plant or, i
- safety from non-safety related areas or, l.
- containment from non-containment areas,
.and all sealing devices-(fire doors, fire windows, fire dampe'rs,. cable, piping and' ventilation duct penetration seals) in fire rated assembly-5 1
penetrations shall be OPER&BLE.
?
1 APPLICABILITY: 'At all times.
l REMEDIAL ACTION:
1-With one or more of the above required fire rated assemblies l
a.
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 establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire 2
i detectors on at least one side of the inoperable assembly i (_f and establish an hourly fire watch patrol.
TESTING REQUIREMENTS:
1 i
,At least once per 18 months the above required fire rated i
c.
' assemblies and penetration sealing devices shall be verified 0,PERABLE, by performing a visual inspection oft
)
(
i SG The exposed surfaces of each fire rated assembly, -
11.
Each fire window / fire damper /and associated hardware, and l
111.
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
- l' shall be selected such that each penetration seal will be inspected every '15 years.
j b.
. Each of the above required fire doors shall be verified OPERABLE by inspecting the automatic hold-open, release and closing i
mechanisms and latches at least once..per 6 months, and by verifying:
1.-
That each. unlocked fire door without electrical supervisione i
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 />, 11.-
That doors with automatic hold-open and release mechanisms t
.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, O'
performing a functional test at least once per 18 honths, 16.9-10; 11 _h95 ~
^**
w,39;.
J V
r,, -
+
r
~, - -
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t i
a 111. That each locked closed fire door is closed at least once
~ ' -
j; per 7 days, and.
[
iv.
\\s_s
.The OPERABILITY of the Fire Door Supervision System for each electrically supervised fire door by performing a TRIP 4
J
)
}
ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days.
REFERENCES:
4 1)
,FOGuire FSAR, Chapter 9.5.1 i
i 2)
McGuire SER Supplement 2, Chapter 9.5.1 and Appendix D.
3)~
.McGuire SER Supplement 5, Chapter 9.5.1 and Appendix B l
4);
McGuire Fire Protection Review, as revised 5)
McGuire SER Supplement 6, Chapter 9.5.1. and Appendix C 6)
McGuire Facility Operation Licentes, Unit'l License Condition C.(4) and Unit 2 License Condition C.(7)
[
j
- 7).
. Door Schedules - MC-1108-01, MC-1208-01-01, -02, -03, -04, -05 and
-06.
4
-e B)
Fire Plan Drawings - MC-1384-07 series J
i 4
4 BASES:
I 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,
[
L
- Fire will not spread from the balance of plant to,the Control Complex,
~
l
- Fire will not spread from non-safety related areas to safety related I
areas.
- Fire will not spread from non-containment areas to containment areas.
-)
The fire related assemblies and associated penetration seals are a 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 i
penetration seals) are considered operable when the visually observed condition is not degraded to a point that the assembly cannot perform i
the function that is intended.
For fire rated assemblies that are
+
1 i
questionable, an evaluation shall be performed to determine the cause of any identified abnormal change in appearance or abnormal degradation and i
the effect of this change on the ability of the fire rated assembly to perform its function.
-During periods of time when a fire rated assembly is not operable, eithers (1) a continuous fire watch is required to be maintained in the 5
vicinity of the affected barrier, or (2) the fire detectors on'at least one side of.the affected bsrrier must be verified OPERABLE and an hour'ly I
fire watch patrol established until the barrier is restored to operable otatus.
l N /,This' Selected Licensee Commitment is part'of the McGuire Fire Protection l
t s
Program and therefore subject to the' provisions of McGuire Facility l
Operating License Conditions C.(4) (Unit 1] and C.(7) (Unit 2]T'
?
16.9-11 11/95 tr
= " ' '
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- - * ' + -
- s-
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i' 16.11
' RADIOLOGICAL EFFLUENT MONITORING RADIOLOGICAL ENVIRONMENTAL MONITORING ~
16i11-13 MONITORING PROGRAM l
COMMITMENT i
The Radioactive Environmental Monitoring Program shall be conducted as speci-fied in Table 16.11-7.
APPLICABILITY: At all times.
REMEDIAL ACTION:
With the Radiological Environmental Monitoring Program not being I
a.
i 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.
2 With the level of radioactivity in an environmental sampling medium b.
^
at a specified location exceeding the reporting levels of Table j g' 16.11-8 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within L
l 30 days a Special Report that defines the corrective actions to be l
taken to reduce radioactive effluents so that the potential annual i.
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 1,imit level (1) limit level (2)
When radionuclides other thari those in Table 16.11-8 are detected-1 and are the result of plant effluents, this report shall be sub-
)
r mitted if the potential annual dose
- to a MEMBER OF THE PUBLIC is equal.to or greater than the calendar year ifaits of SLCs 16.11-6, 16.11-8 and 16.11-9. This report is'not required if the measured i
i level of radioactivity was not! 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.
C
'*The methodology and parameters used to estimate the potential annual dose to j
j a MEMBER OF THE PUBLIC shall be indicated in this report'.
l 11/95 16.11-48 i-
_.. -. -.. -. -. -. -. -....- -.. -. -.. -... -. -.. -.. ~
TABLE 16.11-7 (Page 2 of 7) l 1
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
NUMBER OF l
REPRESENTATIVE TYPE AND FREQUENCY SAMPLING AND SAMPLES AND i
EXPOSURE PATHWAY SAMPLE LOCATIONS (1)
COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE i
2.
A1rborne t
Radiciodine and Samples from five locations:
Continuous sampler Radiciodine Canister:
7 l
Particulates.
Three samples from close to the operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
l average groundlevel D/Q.
loading.
Gross beta radio-i activity analysis filter followigGamma change; One sample from the vicinity of isotopic analysis (5) a community having the highest of composite (by calculated annual average l
location) quarterly.
groundlevel D/Q.
l One sample from a control location, as for example 15-30 km distant and in the direction.gpt wind least prev 3.
Waterborne Surface (6)
One sample upstream.
Compositesampigver Gammaisgpic One sample downstream.
1-month period.
analysis monthly.
a.
Composite for tritium analysis quarterly.
i 16.11-52 11/95.
L t
m
-i
,c...:we-m m
-m
-r-m.
.m
TABLE 16.11-7 (Pace 3 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY l
AND/OR SAMPLE SAMPLE LOCATIONS (1) i COLLECTION FREQUENCY OF ANALYSIS b.
Ground Samples from one or two sourc Quarterly.
Gammaisotopic(5) i only if likely to be affected and tritium analysis quarterly.
l c.
Drinking One sample of each of one to Compositesagd over I-131 analysis on each three of the nearest water 2-week perio 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 l
composite otherwise.
year.gthan1mremper great One sample from a control 7
Composite for l
l location.
l grossbetaandgag isotopic analyses monthly. Composite for-tritium analysis l
quarterly.
i l
d.
Sediment One sample f. rom dowpstream area Semiannually.
l from with existing or potential Gammaisgpic analysis shoreline recreational value.
semiannually.
l l
16.11-53 11/95
O O
O 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 One sample of each principal At time of harvest (10) c.
Food Gama isgpic analyses on edible Products class of food products from any area that is irrigated by water portion.
in which liquid plant wastes have been discharged.
Samples of three different kinds Monthly when available.
Gama isotopic (S) 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 (0) and similar broad leaf vegetation I-131 analysis.
grown 15-30 km distant in the 4
least prevalent wind direction if milk sampling is not i
performed.
i i
11/95 16.11-55
.=
- --r-e w
7 T
-A p%-'w m-e
s_ '
x,-
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," October 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.,
i 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.
l 16.11-56 11/95 l
es
-l 3
November 13, 1995 V
To: All Holders of the Selected Licensee Commitments Manual i
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:
Remove these pages:
Insert these pages:
List of Effective Pages List of Effective Pages Revision 6 Revision 7 e
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.
(
'. Kay L. Crane,
'McGuire Regulatory Compliance O
a
~.
m._
I 4
r 6
i McGuire Nuclear Station
'(
Selected Licensee Cosmaitments List of Effoctive Pages Page Revision Date LQEP Tab List of Effective Pages 7
1 through 7 Tab 16.0 1
.16.0 -
16.0-2 j-Tab 16.1 16.1-1 Tab 16.2
'16.2-1 3/91-16.2-2 5/91
'16.2-3 I
16.2-4 Tab 16.3 1 G 16.3-1 Tab 16.4 i'
Tab 16.5 16.5-1 01/94 16.5-2 01/94 16.5-3 3/93 16.5-4 3/93 16.5-5 3/93 16.5-6 3/93 16.5-7 3/93 16.5-8 3/93 16.5-9 3/93 16.5 3/93 Tab 16.6' Tab 16.7' 16.7 8/95 8
16.7-2 8/95 Revision 7
.... ~
. r, Page Revision Date I
(
16.7-3 8/95' 16.7-4 8/95.
?
i 16.7-5 8/95 16.7-6.
8/95 16.7-7 8/95 16.7-8.
8/95 16.7-9' 8/95 16.7-10' 8/95 16.7-11 8/95
.16.7-12 8/95 16.7-13 8/95 l
'16.7-14 8/95 Tab 16.8 16.8-l' 10/90 Table 16.8-la 1 of 28 10/94 Table 16.8-la 2 of 28 10/94 Table 16.8-la 3 of 28 10/94 i
Table 16.8-la 4 of 28 10/94 Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94 Table 16.8-la 7 of 28 10/94 1
Table 16.8-la 8 of 28 10/94 Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28 10/94 Table 16.8-la 11 of 28 10/94 Table 16.8-la 12 of 28 10/94 i
Table 16.8-la 13 of 28 10/94 7
Table 16.8-la 14 of 28 10/94 f
Table 16.8-la 15 of 28 10/94 i-Table 16.8-la 16 of 28 10/94-t
?
Table 16.8-la 17 of 28 10/94
\\
- Table 16.8-la 18 of 28 10/94 Table'16.8-la 19 of 28-10/94 Revision 7 n
1,.
2
.-~
Page Revision Date
'_/
Table 16.8-la 20 of 28 10/94 Table 16.8-la 21 of 28 10/94 Table 16.8-la 22 of 28 10/94 Table 16.8-la 23 of 28 10/94 Table 16.8-la 24 of 28 10/94 Table 16.8-la 25 of 28 10/94 Table 16.8-la 26 of 28 10/94 Table 16.8-la 27 of 28 10/94 Table 16.8-la 28 of 28 10/94 Table 16.8-1b 1 of 30 10/94 Table 16.8-1b 2 of 30 10/94 Table 16.8-1b 3 of 30 10/94 Table 16.8-1b 4 of 30 10/94 Table 16.8-1b 5 of 30 10/94 Table 16.8-1b 6 of 30 10/94
,r8 i
i Table 16.8-1b 7 of 30 10/94 G'
Table 16.8-1b 8 of 30 10/94 Table 16.8-1b 9 of 30 10/94 Table 16.8-1b 10 of 30 10/94 Table 16.8-1b 11 of 30 10/94 Table 16.8-1b 12 of 30 10/94 Table 16.8-lb 13 of 30 10/94 Table 16.8-1b 14 of 30 10/94 Table 16.8-1b 15 of 30 10/94 i
Table 16.8-1b 16 of 30 10/94 Table 16.8-lb 17 of 30 10/94 Table 16.8-1b 18'of 30 10/94 Table 16.8-1b 19 of 30 10/94 Table 16.8-1b 20'of 30 10/94 Table 16.8-1b 21 of 30 10/94
. r ~N Table 16.8-1b 22 of 30 10/94 t
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Revision 7 3
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Revision Date i
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' Table.16.8-1b 25 of 30 10/94'
}
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- Table 16,8-1b 26 of'30 10/94-
?
Table:16.8-1b 27 of 30
,10/94 t-
. Table'16.8-1b 28 of'30 10/94 l
2
~ Table'16.8-lb 29'of 30~
10/94-l t
I
, Table 16.8-1b 30 of 30 10/94 l
Tab 1629 s
t 16.9-l' 2/91.
16.9-2 e
i i-16.9-3 716.9-4 l
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16.9-5 1
Table 16.9 !
a l
1-16.9-6
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(
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.i 16.9-9 A
i Table 16.9-2 8/90 j
Table'16.9-2 (cont'd) l 1
16.9-10 11/95
[
i~
16.9-11.
11/95
[
_ 16.9-12 12/90 1
l 16.9-13 i
16.9-14 4
}
Table'16.9-3
~ 12/90
. Table 16.9-3 (cont'd) 12/90 j
Table'16.9-3 (cont'd) 12/90 I
LTable 16.9-3 (cont'd)-
2/95 LTable 16.9-3 (cont'd) 2/95 Table 16.9-3.
i (cont *d) l 1
1 1
16.9-15 11/94 16.9-15m 2/91
-16.9-16 Revision 7
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16.9-19
' Table 16.9-4 i
4 LTable 16.9-5 16.9-20 08/93' i
6 16.9-21 08/93 s
I 16.9-22 Tab 16.10
' Tab 16.11 i'
16.11-1 9/93 l}
' 16.11-2 9/93
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16.11-3 9/93 16.11-4 9/94 i
i 16.11-5 9/93 5
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16.11-16 9/93 t
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' 16.11-23 9/93 t
Revision 7.
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- Pays' Revision Date l
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4 16.11-25' 9/93 i
E16i11-26 9/93
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%y 9/93 j
t 9/93 16.11 !
16.11-301 9/93
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.16.11-31' 9/93
'f 16.11-32
.9/93 1
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-16.11-37 12/93 5
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!15.11-54 9/93 l
i 16.11 11/95 t
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'16.11-56.-
11/95 j
Revision 7 '
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,s Page Revision Date
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16.11-57 9/93 s
16.11-58 9/93 16.11-59 9/93 16.11-60 9/93 16.11-61 9/93 4
16.11-62 9/93, 16.11-63 9/93 16.11-64 9/93 l
16.11-65 9/93 16.11-66 9/93
'16.11-67 9/93 16.11-68 9/93 1
Tab 16.12 Tab 16.13 16.13-1
/
Tab 16.14 Tab 16.15 Appendix Tab 1
2 3
4 5
6 7
~-)
Revision 7 7
~ _.. _ _.
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. ' 16. 9 '
AUXILIARY SYSTEMS
.FIREJPROTECTION SYSTEMS l
16.9-5:
. FIRE' RATED ASSEMBLIES COMMITMENT p
s i
All. fire' rated assemblies
)
.and other fire barriers);se(walls, floors /oeilings, table tray enclosures-parating
- redundant analyzed Post Fire Safe Shutdown Equipment or, i
i
- Control Complex (i.e., control Room, Cable Rooms and Battery Rooms)'
4
. from the remainder of the plant or,
[
- safety from non-safety related areas or,-
i.
- containment from non-containment areas, '
i.
cnd ' all sealing devices (fire doore
".re windows, fire dampers,. cable, F
. piping and' ventilation duct penetrat.,a seals) in fire rated assembly j.
- penetrations shall be OPERABLE.
APPLICABILITY: At all times.
REMEDIAL ACTION:
\\
With one or more of the above required fire rated assemblies a.
'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 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 V
and establish an hourly fire watch patrol.
4 TESTING REQUIREMENTS:
[
a.
,At least once per 18 months the above' required fire rated j
assemblies and penetration sealing devices shall be verified 0,PERABLE, by performing a visual inspection of 17.
The exposed surfaces of each fire rated assembly, -
i' i
e 11.
Each fire window / fire damper /and associated hardware, and iii. At least 10% of each type of sealed penetration.
[
If a= seal is found degraded to inoperable status, a. visual inspection 4
of an additional 10% of each type of sealed penetration j
shall be made. This inspect' ion process shall continue until i
a los sample with no inoperable seals is found.
Samples i
shall.be selected such that each penetration seal will be I
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 i
mechanisms and latches at least once..per 6 months,
}
verifying:
and by
+
i.-
That each unlocked fire door without electrical supervision-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 />,
~
11.
.. ~.
~That doors with automatic hold-open and release mechanisms 2
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
- p performing a functional test at least once per 181 months,
~
16.9-10 I
11/95'~
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That each locked closed fire door is closed at least once
~~
per 7 days, and
[
)
iv.
The OPERABILITY of the Fire Door Supervision System for each (m,/
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)
McGh!re 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:
[}
The functional integrity of the fire rated assemblies, including
(,,f 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,
- Fire will not spread from non-safety related areas to safety related areas.
l
- Fire will not spread from non-containment areas to containment areas.
The fire related assemblies and associated penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
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 questionable, an evaluation shall be performed to determine the cause of cny identified abnormal change in appearance or abnormal degradation and the effect of this change on the ability of'the fire rated assembly to perform its function.
During periods of time when a fire rated assembly is not operable, oithers (1) a continuous fire watch is required to be maintained in the j
vicinity of the affected barrier, or (2) the fire detectors on 'at leas.t ene side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established until the barrier is restored to operable status.
, -~g This Selected Licensee commitment is part of the McGuire Fire Protection s_s Program and therefore subject to the' provisions of McGuire Facility Operating License Conditions C.(4) [ Unit 1) and C.(7) [Uhit 2].
16.9-11 l
i 11/95
16.11 RADIOLOGICAL EFFLUENT MONITORING RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-13 MONITORING PROGRAM COMMITMENT
.I The Radioactive Environmental Monitoring Program shall be conducted as spect-
'fied in Table 16.11-7.
APPLICABILITY: At all times.
l REMEDIAL ACTION:
With the Radiological Environmental Monitoring Program not being a.
conducted as specified in' Table 16.11-7, in lieu of a Licensee Event j
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.
With the level of radioactivity in an environmental sampling medium-b.
O-at a specified location exceeding the reporting levels of Table t
16.11-8 when averaged over any calendar quarter, in lieu of a l
Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be i-taken to reduce radioactive effluents so that the potential annual j
dose
- to a MEMBER OF THE PUBLIC is less than the calendar year l-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 l
medium, this report shall be submitted if:
i i
concentration (1), concentration (2) + ***> 1.0 l, --
1,imit level (1) limit level (2) r f-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 l
equal to or greater than the calendar year limits of SLCs 16.11-6, l
16.11-8 and 16.11-9. This report is not required if the measured 1
-level _of radioactivity was not! the result of plant effluents; how-l i
ever, in such an event, the condition shall be reported and des-cribed in the-Annual Radiological Environmental Operating Report.
[
y.
- The methodology-and parameters used to estimate the potential annual dose to s
a MEMBER OF THE ~PUBLIC shall-be indicated in this report'.
11/95 16.'11-48 L
~
9
,0 Q
V TABLE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY SAMPLES AND EXPOSURE PATHWAY SAMPLE LOCATIONS (1)
COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE 2.
Airborne Radioiodine and Samples from five locations:
Continuous sampler Radioiodine Canister:
Particulates Three samples from close to the operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
average groundlevel D/Q.
loading.
Gross beta radio-activity analysis change;pa filter followi
'I Gamma One sample from the vicinity of isotopic analysis (5,;
a community having the highest of composite (by calculated annual average location) quarterly.
groundlevel D/Q.
One sample from a control location, as for example 15-30'km distant and in the direction.gntwind least prev 3.
Waterborne Surface (6)
One sample upstream.
Compositesamplgver Gammaisgpic a.
One sample downstream.
1-month period.
analysis monthly.
Composite for tritium analysis quarterly.
16.11-52 11/95
_._m.
TABLE 16.11-7 (Pace 3 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE l
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY h
AND/0R SAMPLE SAMPLE LOCATIONS (3)
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.
{
i c.
Drinking One sample of each of one to Composite sa over 2-weekperiogd I-131 analysis on each three of the nearest water when composite when the. dose supplies that could be affected I-131 analysis is calculated for the con-e l
by its discharge.
performed, monthly sumption of the water is l
composite otherwise, great than 1 arem per One sample from a control year.
Composite for l
location.
grossbetaandgag isotopic analyses monthly. Composite for tritium analysis quarterly.
d.
Sediment One sample f. rom dowpstream area Semiannually.
from with existing or potential Gannaisgpic analysis shoreline recreational value.
semiannually.
i r
16.11-53 11/95
O O
O TABLE 16.11-7 (Pace 5 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE i
EXPOSURE PATHWAY SAMPLES ANO SAMPLING AND TYPE AND FREQUENCY
~AN0/0R 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.
-l in which liquid plant wastes have been discharged.
Samples of three different kinds Monthly when available.
Gamma isotopic (5) and l'
i of broad leaf vegetation grown 1-131 analysis.
nearest each of two different offsite locations of highest predicted annual average groundlevel D/Q if milk.
sampling is not performed.
i One sample of each of the Monthly when available.
Gamma isotopic (5) and similer broad leaf vegetation I-131 analysis.
grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed.
l i
1 I
l l
11/95
}
16.11-55 l
l I
E
__._.,u.
(
TABLE 16.11-7 (Page 6 of 7) i 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 i
Effluent Technical Specifications for Nuclear Power Plants," October 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 eqaipment 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.
1
?
16.11-56 11/95
- - ~~ ~
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 crrors and adds references.
Your copy of the manual should be revised as follows:
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 direc;6d to Kay Crane,
/%
McGuire Regulatory Compliance at extension 4306.
O Ojvside-)
..KahrL. Crane,
'McGuire Regulatory Compliance j
^
1
.-.m m...
1 l
l
~
i
-[
McGuire Nuclear station I
4 selected Licensee comunitments l
F \\ss/
List of Effective Pages
.Page' Revision Date-i LOEP Tab-I List of Effective Pages-7 1 through 7 Tab 16.0 16.0-1 i
i 16.0-2 l
Tab 16.1 16.1-1 l
3 1
_. Tab 16.2 1
1 1
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16.2-1 3/91 I
16.2-2 5/91 i
16.2-3
{
a 16.2-4 Tab 16.3 i
16.3 i Tab 16.4
{
Tab 16.5 I
16.5-1 01/94 16.5-2 01/94 16.5-3 3/93 16.5-4 3/93 16.5-5 3/93 i
16.5-6 3/93 16.5-7 3/93 3
16.5-8 3/93 4
16.5-9 3/93 16.5-10 3/93 Tab 16. 6
/'~*j Tab 16.7 n,l l
16.7-1 8/95 16.7-2 8/95 I
Revision 7 l
,a mi.ie....
)g Q
. 16. 7 - 3.'
8/95 16.7 8/95 216~.7-5 8/95-
-16.7-6 8/95 16.7-7 8/95 l
16.7-8 8/95
-16.7-9 8/95
=16.7 8/95 16.7-11
-8/95 t
16.7 8/95
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f Tab'16.8
.16.8-1 10/90 Table 16.8-la 1 of 28 10/94 Table 16.8-la 2 of 28 10/94
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Table 16.8-la 3 of 28 10/94
.)
Table 16.8-la 4 of 28 10/94 I
Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94
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Table 16.8-la 7 of 28 10/94 6
5 Table 16.8-la 8 of 28 10/94 Table 16.8-la 9 of 28 10/94 i
Table 16.8-la 10 of 28 10/94 Table 16.8-la 11 of 28 10/94 5
Table 16.8-la,12 of 28 10/94 l
Table 16.8-la 13 of 28 10/94
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Table 16.8-la 14 of 28 10/94 Table 16.8-la 15 of 28' 10/94 Table 16.8-la 16 of.28 10/94 l
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Table 16~8-la-17 of 28 10/94 i
k Table'16.B-la 18 of 2'8' 10/94
-Table 16.8-la 19 of 28
'10/94 l
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~Page iRevision Date Table 16.8-la.20 of 28 10/94' Table 16.8-la 21 of 28 10/94 Table 16.8-la 22 of 28.
'10/94-Table 16.8-la 23 of 28
.10/94 Table 16.8-la.24 of 28-10/94 Table 16.8-la 25 of 28 10/94 Table 16.8-la 26 of 28 10/94 Table.16.8-la 27 of 28 10/94 Table 16.8-la 28 of'28 10/94 Table 16.8-1b 1 of 30 10/94
. Table 16.8-1b 2 of 30 10/94 j
' Table 16.8-lb 3 of 30 10/94 Table 16.8-1b 4 of 30 10/94 l
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-Table 16.8-1b 5 of 30
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Table 16.8-1b 6 of 30 10/94 l
Table 16.8-1b 7 of 30
.10/94 Table 16.8-1b 8 of 30 10/94 Table 16.8-1b 9 of 30 10/94 i
I Table 16.8-1b 10 of 30 10/94 Table 16.8-1b 11 of 30 10/94 Table 16.8-1b 12 of 30 10/94 Table 16.8-1b 13 of 30 10/94 i
Table 16.8-1b 14.of 30 10/94 Table 16.8-1b 15 of 30 10/94 Table 16.8-lb 16 of 30 10/94 Table 16.8-1b 17 of 30 10/94 Table 16,8-1b 18 of 30 10/94 Table 16.8-1b 19 of 30 10/94 Table 16.8-1b 20'of 30 10/94
)
Table 16.8-1b 21 of 30 10/94 f,^.
Table 16.8-1b 22 of 30 10/94 Table 16.8-1b 23 of 30 10/94 Table 16.8-1b 24 of 30 10/94 Revision 7.
3
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,cw Page Revision Date j
'(, h Table 16.8-1b 25 of 30 10/94
)
Table 16.8-1b 26 of 30 10/94 Table 16.8-1b 27 of 30 10/94 Table 16.8-1b 28 of 30 10/94 Table 16.8-1b 29 of 30 10/94 Table 16.8-1b 30 of 30 10/94 Tab 16.9 16.9-1 2/91 16.9-2 16.9-3 16.9-4 16.9-5 Table 16.9-1 16.9-6 16.9-7 l
16.9-8 16.9-9 Table 16.9-2 8/90 Table 16.9-2 (cont'd) 16.9-10 11/95 16.9-11 11/95 16.9-12 12/90 16.9-13 16.9-14 Table 16.9-3 12/90 Table 16.9-3 (cont'd) 12/90 Table 16.9-3 (cont'd) 12/90 Table 16.9-3 (cont'd) 2/95 Table 16.9-3 (cont'd) 2/95 Table 16.9-3 (cont'd) rN 16.9-15 11/94
\\~
16.9-15a 2/91 16.9-16 Revision 7 4
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Page Revision Date i
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16.9-17 6/95 16.9-18 16.9-19 Table 16.9-4 Table 16.9-5 16.9-20 08/93 16.9-21 08/93 16.9-22 Tab 16.10 Igb 16.11 16.11-1 9/93 16.11-2 9/93 16.11-3 9/93 16.11-4 9/94 16.11-5 9/93 r~ss
(
)
16.11-6 9/93 N. )'
16.11-7 9/93 16.11-8 9/93 16.11-9 9/93 16.11-10 9/93 16.11-11 9/95 16.11-12 9/93 16.11-13 9/93 16.11-14 9/93 16.11-15 9/93 16.11-16 9/93 16.11-17 9/93 16.11-18 9/93 16.11-19 9/93 16.11-20 9/93 Cg 16.11-21 9/93 l
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16.11-22 9/93 16.11-23 9/93 Revision 7 5
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~16.11-55 711/95 J
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- Revision 7J j
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- -. -... _ _ _ _ _. _.. _ _ _ _. _. ~. _ _,, _. _ _
JPage M ision Date h'
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'16.11-66 9/93 16.11-67 9/93 16.11-68' 9/93 Tab 16.12 I
-Tab 16.13 16.13 p Tab 16.14 Tab 16.15 l
-Annandiw Tab t
1 2
I i
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i 4
l 5
6 7
.l
. Attachment 3' I
i i
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s.
,s.
E p
i Revision 7
.-7
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I I16.95
~
AUXILIARY SYSTEMS-e-
A..
).-
FIRE PROTECTION SYSTEMS
'16E9-5i l
. FIRE RATED ASSEMBLIES l i -
COMMITMENT:
l b
. ~
i; 1All fire rated assemblies (walls, floors / ceilings,. cable tray enclosures l
1
-and other' fire barriers) separating s
4g,
,
- redundant analysed Post Fire Safe shutdown Equipment or, -
i 1
- Control' Complex (i.e., Control Room, Cable Rooms and Battery' Rooms) l
. from the. remainder of the plant or, 3
- ' safety from non-safety related areas or, j
- containment from non-containment areas,
,i I
I i-
. and all sealing devices (fire doors, fire windows, fire dampe'rs,. cable,.
piping and ventilation duct penetration seals) in fire rated assembly
.m penetrations shall be OPERABLE.
j
! APPLICABILITY: At all times.
t Le
{;
REMEDIAL ACTION:
.i t
.With one or more of the above required fire rated assemblies 1
1-a.
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 j
i establish a continuous fire watch on at least one side of i
the affected assembly, or. verify the OPERABILITY of fire
,~
detectors on at least one side of the inoperable assembly and establish an hourly fire watch patrol.
[
~ TESTING REQUIREMENTS-I
,At least once per 18 months the above required fire rated a.
assemblies and penetration sealing devices shall be verified
[
OPERABLE, by. performing a visual' inspection oft
{
c
$1. -
The exposed surfaces of each fire rated assembly,.
o 11.
Each fire window / fire damper /and associated hardware, and I
111. At least 10% of each type of sealed penetration.
If a seal I
[
.is found degraded to inoperable status, a visual inspection of an additional 10% of each type of sealed penetration shall be made. This inspect' ion process shall continue until 1
t at10% sample with no inoperable seals is found.
samples I
shall be selected such that each penetration seal will be inspected every'15, years.'
i.
t-b.
Each of the above required fire doors shall be verified OPERABLE by inspecting the automatic. hold-open, release and closing h.
-mechanisms and latches at-least once..per'6 months, and by verifyingt i
That each unlocked fire door without electrical supervision.-
. 1.
j is closied'at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
~
ii.-
That doors with automatic hold-open and release mechanisms fare 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, l performing a functional. test at least once per 18 Donths, b
16.9 I yg/95 ~
+
g I
111.. That each locked closed fire door is closed at least once
[
"~
per 7 days, and I
C iv.
The OPERABILITY of the Fire Door Supervision System for each 1
electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days.
REFERENCES:
i
. 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)
McGuitv eM :.lity Operation Licenses, Unit 1 License Condit.'e ;. (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 l
t l
i BASES 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:
i
- Fire will not damage redundant analyzed Post Fire Safe Shutdown f
equipment, e
- Fire will not spread from the balance of plant to,the Control Complex, l
- Fire will not spread from non-safety related areas to safety related i
areas.
l
- Fire will not spread from non-containment areas to containment areas.
I The. fire related assemblies and associated penetration seals are a passive element in-the facility fire protection program and are subject 4
to periodic inspect:lons.
Fire rated assemblies, including associated penetration seals (fire I
i doors, fire windows, fire dampers, cable, piping and ventilation duct j
penetration seals) are considered operable when the visually observed condition is not degraded to a point that the assembly cannot perform lI the function that is intended.
For fire rated assemblies that are questionable, an evaluation shall be performed to determine the cause of any identified abnormal change in appearance or abnormal degradation and the effect of this change on the ability of'the fire rated assembly to'
{
perform its function.
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 s
vicinity of the affected barrier, or (2) the fire detectors on at least i
one side of the affected barrier must be verified OPERABLE and an hour'ly l
fire watch patrol established until the barrier is restored to operable i
i status.
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]?
i i
16.9-11 11/95
16.11 RADIOLOGICAL EFFLUENT MONITORING
- p)
,'p
. RADIOLOGICAL ENVIRONMENTAL MONITORING
^
16.11-13 MONITORING PROGRAM
?,.
COMMITMENT The Radioactive Environmental Monitoring Program shall be conducted as spect-I, fled in Table 16.11-7.
APPLICABILITY: At all times.
i REMEDIAL ACTION:
With the Radiological Environmental Monitoring Program not being i
a.
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-j venting a recurrence.
4 With the level of radioactivity in an environmental sampling medium b.
- fn) -
at a specified location exceeding the reporting levels of Table l
- (,
16.11-8 when averaged over any calendar quarter, in lieu of a l'
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 i
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 J
medium, this report shall be submitted if:
concentration (1), concentration (2) + > 1.0 i
1,imit level (1) limit level (2)
When radionuclides other than' those in Table 16.11-8 are detected-j 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 not 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.
h
- The methodology and parameters used to estimate the potential annual dose to I
a MEMBER OF THE PUBLIC shall be indicated in this report'.
11/95 16.11-48
L 0--.
0 l
TABLE 16.11-7 (Page 2 of 7) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATHWAY SAMPLE LOCATIONS [g)
COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE 2.
Airborne Radioiodine and Samples from five locations:
Continuous sampler Radiciodine Canister:
Particulates Three samples from close to the operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
average groundlevel D/Q.
loading.
Gross beta radio-activity analysis following filter One sample from the vicinity of change;W Gamma
~
isotopic analysis (5) a community having the highest calculated annual average of composite (by groundlevel D/Q.
location) quarterly.
One sample from a control location, as for example 15-30 km distant and in the direction.gntwind least prev 3.
Waterborne Surface (0)
One sample upstream.
Compositesampigver Gammaisgpic a.
One sample downstream.
1-month period.
analysis monthly.
Composite for tritium analysis quarterly.
16.11-52 11/95
TABLE 16.11-7 (Page 3 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
NUMBER OF REPRESENTATIVE '
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLELOCATIONS(g)
COLLECTION FREQUENCY OF ANALYSIS b.
Ground onlyiflikelytobeaffectedgI.
Quarterly.
Gamma; isotopic (5)
Samples from one or two sourc and tritium analysis quarterly.
i c.
Drinking One sample of each of one to Compositesagd over I-131 analysis on each three of the nearest water 2-week perio 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.
great One sample from a control year.gthan1mremper Composite for l
location.
grossbetaandgag isotopic analyses monthly. Composite for tritium analysis quarterly.
[
d.
Sediment One sample f. rom downstream area Semiannually.
from with existing or potential Gammaisgpic i
analysis shoreline recreational value.
semiannually.
l l
~
r 16.11-53 11/95
...... ~
=...-.
0 0
O TABLE 16.11-7 (Pace 5 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS One sample of each principal At time of harvest (10)
Gamma isotopic c.
Food Products class of food products from any analyses 9)on edible area that is irrigated by water portion.
in which liquid plant wastes have been discharged.
i Samples of three different kinds Monthly 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 1
similar broad leaf vegetation I-131 analysis.
grown 15-30 km distant in the least prevalent wind direction c
l if milk sampling is not performed.
j l
l i
t l
16.11-55 11/95 l
.~.
i TABLE 16.11-7 (Page 6 of 7)
TABLE NOTATION i
(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 Plc.nts," October 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 i
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 continuo 1 sly 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 e
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.
t i
i
- 16. I I-56 11/95 i
A--
u w
m A
a--u w
- (ir w--*
n+-,g-
D)
(
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:
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,
/N McGuire Regulatory Compliance at extension 4306.
2jskIstG4-)
' Kay L.
- Crane, McGuire Regulatory Compliance 0
. -... ~. ~- -
- -. - ~. -.......
r' McGuire shaclear station
.h.'
selected Licensee commaitments
' hs,/ --
List of Effective Pages
)
Page Revision Date i
LOEP Tab List of Effective Pages 7
1 through 7 3
Tab 16.0 16.0-1 16.0-2 Tab 16.1 16.1-1 Tab 16.2 16.2-1 3/91 16.2-2 5/91 16.2-3 16.2-4 Tab 16.3 g-+
Nl us 16.3-1 1
Tab 16.4 Tab 16.5
.16.5-1 01/94 16.5-2 01/94 16.5-3 3/93 16.5-4 3/93 16.5-5 3/93 16.5-6 3/93 i
16.5-7 3/93 j
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.16.5-8 3/93 l
t 16.5-9 3/93 16.5-10 3/93 Tab 16.6 O
Tab 16.7 i*-
-16.7-1 8/95 16.7-2 8/95 Revision 7
t y
Page Revision Date 16.7-3 8/95 m
16.7-4 8/95 16.7-5 8/95 16.7-6 8/95 16.7-7 8/95 16.7-8 8/95 16.7-9 8/95 16.7-10 8/95 16.7-11 8/95 16.7-12 8/95 16.7-13 8/95 16.7-14 8/95 Tab 16.8 16.8-1 10/90 Table 16.8-la 1 of 28 10/94
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Table 16.8-la 2 of 28 10/94
' '~l Table 16.8-la 3 of 28 10/94 Table 16.8-la 4 of 28 10/94 Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94 Table 16.8-la 7 of 28 10/94 Table 16.8-la 8 of 28 10/94 Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28 10/94 Table 16.8-la 11 of 28 10/94 Table 16.8-la 12 of 28 10/94 Table 16.8-la 13 of 28 10/94 Table 16.8-la 14 of 28 10/94 Table 16.8-la 15 of 28 10/94 Table 16.8-la 16 of 28 10/94 tN Table 16.8-la 17 of 28 10/94
(
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Table 16.8-la 18 of 28 10/94 Table 16.8-la 19 of 28 10/94 Revision 7 2
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10/94 Table 16.8-1b 5 of.30-10/94 f
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Table 16.8-lb 22 of 30' 10/94
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' Table 16,8-lb 24 ' of 30 10/94 Revision 7 3
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Table 16.8-lb-28 of 30 10/94
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i 16.9-2 16.9 i i
16;.9-4
-. j 16.9-5
- j Table'16.9-1 16.9-6 16.9-7 16.9-8 16.9-9 Table.16.9-2 8/90-l Table 16.9-2 (cont'd) t i
16.9-10 11/95 q
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{
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16.9-14 Table 16.9-3 12/90 Table 16.9-3 (cont'd) 12/90 i.,
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12/90 t
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Table 16.9-3'(cont'd) 2/95 I
Table 16.9-3 (cont'd) 2/95 j
j Table 16.9-3'(cont'd) 3 1
16.9-15 11/94 I '
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2/91
.16.9-16 j
Revision'7 I
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\\d L16;9-17:
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i
'16,9-18 16.9-19'
! Table 16.9-4 i
-Table 16.9-5 l
-16.9-20 08/93 16.9-21; 08/93 l
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16.9-22~
e Tab 16.10
.i
. Tab 16.11-
- 16.11-1
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16.11-3 9/93 i
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.11/95 Revision 7 6
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Page Revision Date rs
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16.11-57 9/93 16.11-58 9/93 16.11-59 9/93 16.11-60 9/93 16.11-61 9/93 16.11-62 9/93, 16.11-63 9/93 16.11-64 9/93 16.11-65 9/93 16.11-66 9/93 16.11-67 9/93 16.11-68 9/93 Tab 16.12 Tab 16.13 16.13-1
[
Tab 16.14 Tab 16.15 Anoendix Tab 1
2 3
4 5
6 7
v Revision 7 7
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. - _ _.- _. _ _ _. - _ _. _ _ _ _ _ ~_...... _ _._._
.e i
i 1
l. -.
.j
\\
16.9-AUXILIARY SYSTEMS J
~
FIRE PROTECTION SYSTEMS-16.9-5 FIRE RATED ASSEMBLIES i
COMMITMENT
+
}
All fire' rated assemblies (walls, floors / ceilings,' cable tray enclosures' I
and other fire barriers). separating l
+
i
- redundant analyzed Post Fire Safe Shutdown Equipment or,
- Control Complex (i.e., control Room, Cable Rooms and Battery Rooms) f
'from the remainder of the plant or, l
- safety from non-safety related areas or,
[
- containment from non-containment areas,.
i t
}
and all sealing devices (fire doors, fire windows, fire dampe'rs,. cable, piping and ventilation duct penetration seals) in. fire rated assembly ipenetrations shall be OPERABLE.
j APPLICABILITY: At all times.
REMEDIAL ACTION:
With one or more of the above required fire rated assemblies a.
t 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 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
-t 1
.and establish an hourly fire watch patrol.
TESTING REQUIREMENTS:
,At least once per 18 months the above required fire rated a.
assemblies and penetration sealing devices shall be verified OPERABLE, by performing a visual inspection of
$7.
The exposed surfaces of each fire rated assembly, 11.
Each fire window / fire damper /and associated hardware, and 111. 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.
4 b.
Each of the above required fire doors shall be verified OPERABLE by inspecting the automatic hold-open, release and closing mechanisms and latches at least once.per 6 months, and by verifying 1.
That each unlocked' fire door without electrical supervision-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 />,
+
11.
That doors with automatic hold-open and release me hanisms 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 inonths, 16.9-10 yy
~~
-n k
e
+ - -
i E
=
.er.
i
)
i i -
.That each locked closed fire door is closed at 19ast once,
)
111.
per 7 days, and i
iv.
The OPERABILITY of the Fire Door Supervision System for each 5
electrically supervised fire door by performing a TRIP a
ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days.
REFERENCES:
i 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 1
3 4)
McGuire Fire Protection Review, as revised 5)
McGuire SER Supplement 6, Chapter 9.5.1. and Appendix C i
4
.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
~
l t
BASES:
l[ \\
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:
4 Fire will not damage redundant analyzed Post Fire safe Shutdown equipment, Fire will not spread from the balance of plant to_the Control Complex, 1
- Fire will not spread from non-safety related areas to safety related t
areas.
- Fire will not spread from non-containment areas to containment areas.
The. fire related assemblies and associated Fenetration seals are a 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 duc penetration seals) are considered operable when the visually observed condition is not degraded to a point that the assombly cannot perform the function that is intended.
For fire rated assemblies that are i
questionable, an evalhation shall be performed to determine the cause of
~
any identified abnormal change in appearance or abnormal degradation and the effect of this change on the ability of the fire rated assembly to perform its function.
During periods of. time when a fire rated assembly is not operable, either:
(1) a continuous fire watch is required to be anintained in the t
vicinity of the affected barrier, or (2) the fire detectors on 'at leas,t one side of the affected barrier must be verified OPERABLE and an hourly l
fire watch patrol established until the barrier is restored to operable status.
This selected Licensee commitment is part of the McGuire Fire Protection a
i Program and therefore subject to the' provisions of McGuire Facility Operating License Conditions C.(4) [ Unit 1] and C.(7) [Udit 2]."
16.9-11 11/95 4,
h I
i
_p 16.11 RADIOLOGICAL EFFLUENT MONITORING iV RADIOLOGICAL ENVIRONMENTAL MONITORING L
)
16c11-13 MONITORING PROGRAM COP 94ITMENT I
i The Radioactive Environmental Monitoring Program shall be conducted as speci-1 fied in Table 16.11-7.
i APPLICABILITY:' At all times.
REMEDIAL' ACTION:
With the Radiological Environmental Monitoring Program not being 4
a.
conducted as'specified in Table 16.11-7,.in lieu of a Licensee Event l
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-i j
venting a recurrence.
l b..
With the level of radioactivity in an environmental sampling medium
~
at a specified location exceeding the reporting levels of Table 16.11-8 when averaged over any calendar quarter, in lieu of a l \\.
Licensee. Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be j
taken to reduce radioactive effluents so that the potential annual j
dose
- to a MEMBER OF THE PUBLIC is less than the calendar year
{
i 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 1,imit level (1) limit level (2)
When radionuclides other than' those in Table 16.11-8 are detected-l and are the result of plant effluents, this report shall be sub-mitted if the potential annual dose
- to a MEM8ER OF THE PUBLIC is
[
equal to or greater than the calendar year limits of SLCs 16.11-6, l
16.11-8 and 16.11-9. This report is not required if the measured level of radioactivity was noti 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 cethodology and parameters used to estimate the potential annual dose to 2
a MEMBER OF THE PUBLIC shall be indicated in this report'.
11/95 1
16.11-48
.- \\
TABLE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
NUMBER OF REPRESENTATIVE SAMPLING AND
. TYPE AND FREQUENCY SAMPLES AND EXPOSURE PATHWAY SAMPLE LOCATIONS [g)
COLLECTION FREQUENCY OF ANALYSIS AND/0R SAMPLE 2.
Airborne Radiolodine and Samplas from five locations:
Continuous sampler Radiciodine Canister:
Particulates Three samples from close to the operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
3 average groundlevel D/Q.
loading.
Gross beta radio-activity analysis followi filter Gamma change; One sample from the vicinity of isotopic analysis (5) a community having the highest of composite (by calculated annual average location) quarterly.
l groundlevel D/Q.
One sample from a control location, as for example 15-30 km distant and in the direction.gntwind j
least prev
.3.
Waterborne Ganna isgpic Surface (6)-
, ample upstream.
Composite sampi ver a.
One sample downstream.
1-month period.
analysis monthly.
Composite for tritium analysis quarterly.
i 16.1'l-52 11/95 l
TABLE 16.11-7-(Page 3 of 7) i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
i i
NUMBER OF I
REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLELOCATIONS(g)
COLLECTION FREQUENCY OF ANALYSIS b.
Ground Samples from one or two sourc Quarterly.
Ganna isotopic (5) only if likely to be affected and tritium analysis quarterly.
c.
Drinking One sample of each of one to Composite sa over I-131 analysis on each 2-weekperiogd three of the nearest water 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 i:
composite otherwise.
great One sample from a control year.gthan1aremper Composite for l
location.
grossbetaandgag isotopic analyses monthly. Composite for tritium analysis quarterly.
d.
Sediment One sample f. rom downstream area Semiannually.
Gasmaisgpic from with existing or potential analysis shoreline recreational value.
semiannually.
l t
f 16.11-53 11/95
.w---
-.a
TABLE'16.11-7 (Page 5 of 7)-
i 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY i
AND/0R SAMPLE SAMPLE LOCATIONS {g)
COLLECTION FREQUENCY OF ANALYSIS
[
- c. -Food One sample of each principal At time of harvest (10)
Gammaisgpic l
p analyses on edible r
Products class of food products from any area that is irrigated by water portion.
in which liquid plant wastes i
have been discharged.
i Samples of three different kinds Monthly when available.
Gamma isot'opic(5) and of broad leaf vegetation grown I-131 analysis.
nearest each of two different offsite locations of highest
'j predicted annual' average t
groundlevel D/Q if milk.
[
sampling is not performed.
j 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 4
if milk sampling is not performed.
j i
i
[
16.11-55 11/95 I
I.
...m.
m m
t 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," October 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 tw' 3r 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 r % be reduced according to geographical limitations; e.g.,
at an ocean site, some sections will be oser 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.
I i
l 16.11 56 11/95
. ~.
c t
.l
)
November 13, 1995
'h): All Holders of the Selected Licensee Commitments Manual i
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:
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 i
Questions or problems should be directed to Kay Crane, r'*g McGuire Regulatory Compliance at extension 4306.
O
)FIy L. Crane, j
'McGuire Regulatory Compliance v
6 I i E
i I
- O 4
McGuire Nuclear Station
(
selected Licensee Cossaitments List of Effoctive Pages Page Revision Date LOEP Tab List of Effective Pages 7
[
1 through 7 Tab 16.0 16.0-1 l
16.0-2 Tab 16.1 16.1-1 Tab 16.2 16.2-1 3/91 16.2-2 5/91 16.2-3 16.2-4 Tab 16.3 16.3-1 Tab 16.4 Tab 16.5 16.5-1 01/94 16.5-2 01/94 16.5-3 3/93 16.5-4 3/93 16.5-5 3/93 16.5-6 3/93 16.5-7 3/93 16.5-8 3/93 16.5-9 3/93 16.5-10 3/93 Tab 16.6
~
Tab 16.7
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16.7-1 8/95 16.7-2 8/95 Revision 7 m
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e
page Revision Date'
.b
\\d 16.7-3 8/95 1
16.7-4 8/95 16.7-5 8/95 1
I 16.7-6:
8/95 16.7 8/95 I
16.7-8 8/95 l
16.7-9 8/95 16.7-10 8/95
- 16.7 8/95.
- 16.7-12 8/95 16.7-13 8/95
(
16.7-14 8/95 Tab 16.8
- 16.8-1
-10/90 Table 16.8-la 1 of 28 10/94 Table 16,8-la 2 of 28 10/94 Table 16.8-la 3 of 28 10/94 Table 16.8-la 4 of 28 10/94 Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94 Table 16.8-la 7 of 28 10/94 Table 16.8-la 8 of 28 10/94 Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28.
10/94 Table 16.8-la 11 of 28 10/94 Table 16.8-la'12 of 28 10/94' Table 16.8-la 13'of 28 10/94 i
Table 16.8-la 14 of 28 10/94
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Table 16.8-la 15 of 28 10/94 Table 16.8-la 16 of 28 10/94 i
e-Table 16,8-la 17 cf 28 10/94
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Tablek6.8-la'18of28 ~
10/94
- Table'16.8-la 19 of 28 10/94 Revision 7 2.
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t.
Page 1 Revision Date Table 16.8-la 20 of 28 10/94 Table 16.8-la 21-of 28 10/94
-Table 16.8-la 22 of 28 10/94 Table'16.8-la'23 of 28
'10/94'
' Table 16.8-la 24 of 28 10/94
'TableL16.8-la 25 of 28 10/94 Table 16.8-la 26 of 28 10/94 Table 16.8-la.27 of 28
.10/94
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'10/94
-Table 16.8-lb 2 of 30
'10/94 Table 16.8-1b 3 of 30 10/94 Table 16.8-lb 4 of 30.
10/94 Table 16.8-1b 5 of 30 10/94 Table 16.8-1b 6 of 30 10/94
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Table 16.8-1b 7 of 30 10/94 Table 16.8-1b 8 of 30 10/94 Table 16.8-1b 9 of 30 10/94 Table 16.8-1b 10 of 30 10/94 Table 16.8-1b 11 of 30 10/94 Table 16.8-1b 12 of 30 10/94 Table 16.8-1b 13 of 30 10/94 Table 16.8-1b 14 of 30 10/94 Table-16.8-1b 15 of 30 10/94 Table 16.8-1b 16 of 30 10/.94
. Table 16.8-1b 17 of 30 10/94 LTable 16.8-1b 18 of 30 10/94 Table 16.8-lb 19 of 30 10/94 Table 16.8-1b 20 of 30 10/94 Table 16.8-1b-21 of 30 10/94
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Table-16.8-lb 22 of 30 10/94 k _-
Table 16.8-1b 23 of 30
.10/94 s
Table 16.8-lb 24 of 30 10/94 Revision 7 3
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[
l
+
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Page.
-movision Date i
! Table 16.8-1b'25'of 30' 10/94 Table'-16.8-lb 26 of 30 10/94 l
Table 16.8-1b 27 of 30' 10/94 Table'16.8-lb 28 of 30 10/94 Table 16.8-1b 29 of 30-10/94 l-Table 16'.8-1b 30 of 30 10/94 I '-
Tab 16_9
{
16.9 2/91' 16.9-2 i
':16. 9-3 i
l -~
16.9-4 16.9-5
' Table 16.9-1 16.9-6 i16.9-7 i
. )
i ' ;v -
16.9 3 -.
4.
16.9-9 Table 16,9-2
. 8/90 i'
. Table 16.9-2-(cont'd) 4,
- 16.9-10 11/95 i
16.9-11 11/95 1
16.9-12 12/90 i
16.9-13 16.9 -
Table 16.9-3 12/90 Table 16.9-3 (cont'd) 12/90 i
Table 16.9-3 (cont'd) 12/90 Table 16.9-3 (cont'd)
.2/95 Table 16.9-3.(cont'd).
2/95 Table.16.9-3-(cont'd) 16.9 11/94
- \\
16.9-15a-2/91 l
)
Revision 7 4-t
.~,
4m,
e
. -.,... ~. -....
.- - _.. ~. -.
b
'page' Revision Date l
16.9.6/95
- 16.9-18 i
16.9-19 Table.16.9-4.
Table 16.9-5.
16.9-20 08/93 g.
f16.9-21' 08/93L 16.9-221 i-Tab 16.10.
' Tab 16.11
~
f 16.11-1 9/93
'16.11-2 9/93 16.11-3 9/93
-16.11-4 9/94
+
'16,11-5 9/93 i
16.11-6 9/93 16.11-7 9/93 16.11 9/93
)
16.11-9 9/93 4
l 16.11-10 9/93~
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16.11 9/93 16.11-13 9/93 I
16.11-14:
9/93 16.11-15 9/93 l
16.11-161 9/93 j
9/93 1
16.11-17 16.11-18 9/93' 16.11-19' 9/93 16.11-20 9/93
[:
'16.11-21' 9/93 b.'
16111'-22.
9/93 16.11-23 9/93 Revision 7 5
.. ~... _. -. ~
.. _ _ _ _.. _.. _. _ =.
N f
't L
1 I
Page Revision Date 16.11-24 9/93 16.11-25 9/93 t
16.11-27 9/93 j
16.11-27
.9/93
(
'16.11-28 9/93 116.11-29.
9/93 i
16.11-30L 9/93
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16.11-31.
9/93 16.11-32 9/93 16.11-33.
9/93 i
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'I i
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16.11-45 9/93 16.11-46 9/93 16.11-47 9/93 16.11 11/95 16.11-49 9/93 16.11 9/93 16.11 9/93 16.11-52 11/95' 16.11-53, 11/95 15.11-54 9/93
~16.11-55' 11/95 16.11-56 11/95
' Revision 7?
6
1 l
, - ~
Page Revision Date l
Ix_/
16.11-57 9/93 16.11-58 9/93 16.11-59 9/93 16.11-60 9/93 16.11-61 9/93 16.11-62 9/93 l
16.11-63 9/93 1
16.11-64 9/93 16.11-65 9/93 16.11-66 9/93
^
16.11-67 9/93 16.11-68 9/93 Tab 16.12 Tab 16.13 16.13-1
\\
Tab 16.14 1 N/
m Tab 16.15 Anoendix Tab 1
2 3
4 5
d 6
7 i
v Revision 7 7
~
~. ~
... -~.- -
~
.. ~. - - -.. _.
... - ~,
i e '
e
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. Y, i-
'16.9 AUXILIARY SYSTEMS j
FIRE PROTECTION SYSTEMS
?
16.9-S' FIRE RATED ASSEMBLIES COMMITHENT-t V
All. fire' rated-assemblies and other fire barriers) separating (walls, ficors/cellings, cable tray enclosures i'
~
- redundant analyzed' Post Fire Safe Shutdown Equipment or, i
- control complex (i.e., Control Room, Cable Rooms and Battery Rooms)
'from the remainder of the plant or, 4
- 4>
- safety.from non-safety related areas or,
- containment from non-containment areas,-
i l
and all sealing devices (fire doors, fire windows, fire dampe'rs,, cable, 6
piping and ventilation duct-penetration seals) in fire rated assembly.
j-penetrations shall be OPERABLE.
APPLICABILITY: At all times.
i e
i REMEDIAL ACTION:
I 1
a.
With one or more of the above required fire rated assemblies f
j 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 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 4
and establish an hourly fire watch patrol.
j '
TESTING REQUIREMENTS:
, At least once per 18 months the above required fire rated a.
assemblies and penetration sealing devices shall be verified i
OPERABLE, by performing a visual ~ inspection of:
17.
The exposed surfaces of each fire rated assembly, -
l 11.
Each fire window / fire damper /and associated hardware, and t
3 iii. At least 10% of each type of sealed penetration.
If a seal is found degraded to inoperable status, a visual inspection of an additional lot of each type of sealed penetration shall be made. This inspection process shall continue until a lot sample with no inoperable seals is found.
3 Samples
- =
shall be selected such-that each penetration seal will be inspected every '15, years..
e b.
Each of the above required fire doors shall be verified OPERABLE by-inspecting the automatic hold-open, release and closing a
i mechanisms and latches at least once..per 6 months, i.
verifying:
and by 1
1.
That each unlocked fire door without electrical supervision <
- 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 />, j
j 11.
'That doors with automatic hold-open and release mechanisms 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 wonths, j
i 16.9-10 g y'/95. ~<
a e canO848' 4
~
]
r
)
.- ~
lii. That each locked closed fire door is closed at least once
~ ' ~
per 7 days, and
[ ))
iv.
The OPERABILITY of the Fire Door Supervision System for each
\\,
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 i
5)
McGuire SER Supplement 6, Chapter 9.5.1. and Appendix C 6)
McGuire Facility Operation Licentes, 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 Plar. Drawings - MC-1384-07 series BASES:
[
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:
i
- Fire will not damage redundant analyzed Post Fire safe Shutdown equipment, i
- Fire will not spread from the balance of plant to the Control Complex,
)
- Fire will not spread from non-safety related areas to safety related
)
areas.
1
- Fire will not spread from non-containment areas to containment areas.
The fire related assemblies and associated penetration seals are a i
passive element in the facility fire protection program and are subject to periodic inspections.
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 questionable, an evalbation shall be performed to determine the cause of cny identified abnormal change in appearance or abnormal degradation and the effect of this change on the ability of the fire rated assembly to
~
2 perform its function.
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 fire watch patrol established until the barrier is restored to operable ctatus.
A
\\m,) 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) [Udit 2)."
16.9-11 I
11/95
I 4
16.11 RADIOLOGICAL EFFLUENT MONITORING I-
~
l RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-13 MONITORING PROGRAM i
COMITMENT i
i The Radioactive Environmental Monitoring Program shall be conducted as speci-I fied in Table'16.11-7.
l APPLICABILITY: At all times.
r REMEDIAL ACTION:
l With the Radiological Environmental Monitoring Program not being I
a.
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-l venting a recurrence.-
b.
With the level of radioactivity in an environmental sampling medium lp at a specified location exceeding the reporting levels of Table i
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-i taken to reduce radioactive effluents so that the potential annual i
dose
- to a MEMBER OF THE PUBLIC is less than the calendar year i
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:
i i
concentration (1), concentration (2) + ***> 1.0 1,imit level (1) limit level (2)
When radionuclides other than' those in' Table 16.11-8 are detected-1 and are the result of plant effluents, this report shall be sub-mitted if the potential annual dose
- to a hEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of SLCs 16.11-6, L;
16.11-8 and.16.11-9. This report is not required if the measured level of radioactivity was not the result of plant effluents; how-l ever, in such an event, the condition shall be reported and des-cribed in the Annual Radiological Environmental Operating Report, l
h
- The methodology and parameters used to estimate the potential annual dose to
{
~a MEMBER OF THE PUBLIClshall be indicated in this report'.
11/95 i
16.11-48
TA8LE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE TYPE AND FREQUENCY SAMPLING AND SAMPLES AND EXPOSURE PATHWAY SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS AND/OR SAMPLE
-2.
Airborne i
Radiciodine and Samples from five locations:
Continuous sampler Radiciodine Canister:
Particulates Three samples from close to the operation with sample I-131 analysis weekly.
thre'e SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if l
highest calculated annual required by dust Particulate Sampler:
l average groundlevel D/Q.
loading.
Gross beta radio-activity analysis l
change;gfilter followi
[
Gamma One sample from the vicinity of isotopic analysis (5) a community hav'ing the highest of composite (by j
calculated annual average l
location) quarterly.
i groundlevel D/Q.
i l
One sample from a control
[
location, as for example t
15-30 km distant and in the
[
~
direction.gntwind least prev i
t 3.
Waterborne t
Surface'6)
One sample upstream.
Compositesampigver Gammaisgpic One sample downstream.
1-month period, analysis monthly.
a.
Composite for tritium 4
analysis quarterly.
i t
16.11-52 11/95
...... ~... -.
~
TABLE 16.11-7 (Page 3 of 7)
RADIOLOGICAL ENVIROWlENTAL MONITORING PROGRAM i
NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS b.
Ground Samples from one or two sourc Quarterly.
Gammaisotopic(5) only if likely to be affected and tritium analysis quarterly.
i.
c.
Drinking One sample of each of one to Composite san I-131 analysis on each 2-weekperiodgover three of the nearest water when composite when the dose
- i supplies that could be affected I-131 analysis is calculated for the con-j by its discharge.
performed, monthly sumption of the water is 5
composite otherwise.
greater One sample from a control year.19)than 1 arem per Composite for l
location.
grossbetaandgag isotopic ana.7yses monthly. Composite for tritium analysis
[
quarterly.
I i
d.
Sediment One sample f. rom dowpstream area Semiannually.
Gammaisgpic from with existing or potential analysis i
shoreline recreational value.
semiannually.
'l l
t
~
F 16.11-53 L
11/95
'r e
L O
O O
l TABLE 16.11-7 (Page 5 of 7)
~-
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM b
NUMBER OF REPRESENTATIVE i
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS One sample of each principal At time of harvest (10)
Gamma is pic c.
Food 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 Monthly when available.
Gamma isotopic (5) and of broad leaf vegetation grown I-131 analysis.
l 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.
i i
11/95 16.11-55 i
m t
v TABLE 16.11-7 _.(Page 6 of 7).
TABLE NO'*ATION
-(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," October 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 dait
- Eadiological Environmental Monitoring Program.
In lieu of an Licensee Event Report, identify t.<
2use of the unavailability of samples for that pathway and identify the new locations (s) for obi ning replacement samples in the next Annual Radioactive Effluent Release Report and also include in 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 docimeters. 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
4 8
(Q November 13, 1995 j
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:
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.
d[bb)
I
.~
'Kay L. Crane,
'McGuire Regulatory Compliance e
E F
4 0
-l McGuire Nuclear Station O\\
s Selected Licensee comunitments List of Effective Pages l
Page-Revision Date-LOEP Tab List of Effective Pages 7
1 through 7 i
. Tab 16. 0 l
16.0-1 16.0-2 Tab 16.1 16.1-1 Tab 16.2 16.2-1 3/91 j
16.2-2 5/91 16.2-3 l
16.2.
i Tab 16.3 16.3-1 Tab 16.4 i
Tab 16.5 3
16.5-1 01/94 i
t 16.5-2 01/94
[
16.5-3 3/93 16.5-4 3/93 1
16.5-5 3/93 16.5-6 3/93 16.5-7 3/93 i
l.
16.5-8 3/93 16.5-9 3/93 16-5-10 3/93 1
Tab 16.6 i-Tab 16.7 I
16.7-1 8/95 l
16.7-2 8/95 Revisior. 7
-- ~. =. ~. - -
Page Revision Date
'16.7-3 8/95 16.7-4 8/95 16.7-5 8/95 l
16.7 8/95 16.7-7 8/95 4
16.7-8 8/95 16.7-9 8/95 16.7-10' 8/95 16.7-11)
' 8/95
+
>16.7-12' 8/95 16.7-13 8/95 16.7-14' 8/95
- Tab 16.8 16.8-l' 10/90 i
Table-16.8-la 1 of 28 10/94
\\
Table 16.8-la 2 of 28 10/94 Table 16.8-la 3 of 28 10/94 Table 16.8-la 4 of 28 10/94 4
Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94 Table 16.8-la 7 of 28 10/94 Table 16.8-la 8 of 28 10/94 Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28 10/94 Table 16.8-la 11 of 28 10/94-Table 16.8-la 12'of 28 10/94
- Table 16.8-la 13 of 28 10/94 Table 16.8-la 14 of 28~;
10/94 Table 16.8-la 15 of 28 10/94
- Table 16.8-la 16 of 28 10/94
'(
. Table 16.8-la 17.of 28 10/94 A
Table 16.8-la 18 of 28 10/94 I
f
. Table.16.8-la 19.of 28-10/94 i
Revision.7 2
g y
s
a e
'Page Revision Date e, (j' l
Table 16.8-la 20 of 28-10/94 Table ~16.8-la 21 of 28 10/94 i
Table 16.8-la 22 of 28 10/94 Table 16.8-la 23 of 28 10/94 Table.16.8-la 24 of 28 10/94-f
. Table 16.8-la 25 of 28.
10/94 Table 16.8-la 26 of 28 10/94 Table 16.8-la 27 of 28 10/94 1 Table 16.8-la.28 of :28 10/94
- Table 16.8-1b'1 of'30 10/94 LTable 16.8-1b 2 of 30 10/94
--Table 16.8-1b 3 of 30.
10/94 Table 16.8-1b 4 of 30' 10/94 Table 16.8-1b 5 of 30.
10/94 Table 16.8-1b 6 ot 30 10/94 Table 16.8-1b ' of 30 10/94
' Table 16.e-1b 8 of ' 30 10/94 Table 16.8-1b 9 of 30 10/94 Table 16.8-1b 10 of 30 10/94 Table 16.8-1b 11 of 30 10/94 Table 16.8-1b 12 of 30 10/94 Table 16.8-1b 13 of 30 10/94 Table 16.8-1b 14 of 30, 10/94 Table-16.8-1b 15 of 30 10/94 Table 16.8-1b 16 of 30 10/94 Table 16.8-1b 17 of 30 10/94 Table 16.8-1b 18 of 30 10/94 Table 16.8-1b 19 of 30 10/94 Table'16.8-lb 20 of 30 10/94 Table 16.8-1b 21 of 30 10/94
. Table'16.8-lb 22 of 30 10/94 i
? -
3 Table 16.8-1b 23 of 30.
10/94 s
Table'16.8-1b 24Lof 30 10/94 Revision 7 3
-- ~--.
~.
4
-6
. age Revision Date p
y -q Table 16.8-lb'25 of 30 10/94-Table 16.8-1b 26 of 30-
.10/94-
' Table'16.8-lb'27 of 30 10/94 Table 16.8-1b 28 of 30 10/94
. Table 16.8-1b 29 of 30 10/94 Table 16.8-1b 30 of 30 10/94 Tab 16.9
-16.9-1
'2/91-16.9 '16,9-3
- 16.9.
-16.9-5.
. Table 16.9-1 16.9-6.
16.9-7
-16.9-8 16.9-9
' Table 16.9-2.
8/90 Table.16.9-2 (cont'd) 16.9-10 11/95
.16.9-11 11/95 j,
16.9-12, 12/90 16.9,
16.9-14 t.
Table 16.9-3
-12/90 Table.16.9-3 (cont'd) 12/90 a
Table 16.9-3 _ (cont'd) 12/90_
Table.16.9-3 J (cont'd) 2/95 l
Table 16.9-3 (cont'd).
2/95 Table 16.9-3.,(cont'd).
?
-y%
.16.9-15 11/94
'16.9-15a-2/91
'16.9-16 Revision.7..
4
+
a
(S Page Revision Date
)
(_/
16.9-17 6/95 16.9-18 16.9-19 Table 16.9-4 Table 16.9-5 16.9-20 08/93 16.9-21 08/93 16.9-22 Tab 16.10 Tab 16.11 16.11-1 9/93 16.11-2 9/93 16.11-3 9/93 16.11-4 9/94 16.11-5 9/93 7-(
)
16.11-6 9/93
%d 16.11-7 9/93 16.11-8 9/93 16.11-9 9/93 16.11-10 9/93 16.11-11 9/95 16.11-12 9/93 16.11-13 9/93 16.11-14 9/93 16.11-15 9/93 16.11-16 9/93 16.11-17 9/93 16.11-18 9/93 16.11-19 9/93 16.11-20 9/93
/"N 16.11-21 9/93
's 16.11-22 9/93 16.11-23 9/93 Revision 7 5
1.0 i
1,imit level (1) limit level (2) j 4.
When radionuclides other than' those in Table 16.11-8 are detected-I 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, l
16.11-8 and 16.11-9. This report is not required if the measured level of radioactivity was not 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.
y
)
l
- The methodology and parameters used to estimate the potential annual dose to
.a' MEMBER OF.THE PUBLIC shall be indicated in this report'.
11/95 16.11-48
O
~
TABLE 16.11-7 (Page 2 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY SAMPLES AND EXPOSURE PATHWAY SAMPLE LOCATIONS [g)
COLLECTION FREQUENCY OF ANALYSIS AND/OR SAMPLE _
2.
Airborne Radiciodine and Samples from five locations:
Continuous sampler Radioiodine Canister:
Particulates Three samples from close to the operation with sample I-131 analysis weekly.
three SITE. BOUNDARY locations, collection weekly, or in different sectors, of the more frequently if highest calculated annual required by dust Particulate Sampler:
average groundlevel D/Q.
loading.
Gross beta radio-activity analysis followigfilter change; Gamma One sample from the vicinity of isotopic analysis (5) a community having the highest
~
of composite (by calculated annual average location) quarterly.
groundlevel D/Q.
One sample from a control location, as for example 15-30'km distant and in the direction.gntwind least prev 3.
Waterborne Surface (0)
One sample upstn am.
Composite samp1 ver Gammaisgpic One sample downstream.
1-month period.
analysis monthly.
a.
Composite for tritium analysis quarterly.
16.11-52 11/95
,- - +, + - - - - -, - -
--r-.4 e
-n
(
0 J
U TABLE 16.11-7 (Page 3 of 7)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AN0/0R SAMPLE SAMPLE LOCATIONS (g)
COLLECTION FREQUENCY OF ANALYSIS b.
Ground onlyiflikelytobeaffectedgI.
Quarterly.
Gannia isotopic (5)
Samples from one or two sourc and tritium analysis quarterly.
c.
Drinking One sample of each of one to Compositesagd over I-131 analysis on each three of the nearest water 2-week perio 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.
great One sample from a control year.gthan1aremper Composite for l
location.
grossbetaandgag isotopic analyses monthly. Composite for tritium analysis quarterly.
d.
Sediment One sample f. rom dowpstream area Semiannually.
Gammaisgpic from with existing or potential analysis shoreline recreational value, semiannually.
16.11-53 11/95 L
m
O O
O TABLE 16.11-7 (Pace 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 One sample of each principal At time of harvest (10) c.
Food Products class of food products from any Gammaisgpic analyses on edible area that is irrigated by water portion.
in which liquid plant wastes have been discharged.
Samples of three different kinds Monthly 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 l
similar broad leaf vegetation I-131 analysis.
grown 15-30 km distant in the l
least prevalent wind direction if milk sampling is not performed.
11/95-16.I1-55
O,
(
p$
e
't Q
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," October 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 malfuncticn, 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.
rg 16.11-56 11/95 s