ML20010A190
| ML20010A190 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/03/1981 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20010A183 | List: |
| References | |
| NUDOCS 8108110161 | |
| Download: ML20010A190 (16) | |
Text
~
PSAPG
'd? ORT LEVELS (Continued)
MONITORING REOUIREMENTS (Continued) 4.3 Radiological 5.3 Radiological Objective Objective The purpose of this specification is hhcpurposeofthismonitoringre-to =onitor radiological cficces of quirement is to measure the radio-station operation on the environment. activity levels in the environment The design objective for radioisotopes as a result of the operation of except halogens and particulates with PBAPS.
half lives greaccr than eight days is a .
Jose rate at the site boundary of less chan 10 mrem per year to the whole body or any organ. The design objective for I-131 is a dose race of less than 15 mrem l per year to the thyroid of a child through the grass-cow-milk chain; and for I-131 and other particulate radioisotopes with half lives grcacer Clan eight days is a dose race at the site boundary of less
~
chan 5 mrem per year by breaching.
Specification Specification If a measured level'of radioactivity An environmental monitoring program in critical pathway environmental, shall be conducted as detailed in medium samples indicates that the re- Section 6.4.
sultant annual dose to an individual s s' rom those levels could equal or ux- -
ceed four times the design objective, suitable action will be c ken as per Section 7.2.
If samples of critical pathway en- -
vironmental cedia collected over a calendar quarter show total levels of radioactivity that could result la accumulated plant related doses ,
to an individual over that quarter of one-half the annual dose objective the results shall be reported and a l P l an submitted and implemented within ,
l 30 days so that the annual dose to an .
individual vill not exceed the deaign -
objective.
i Bases Bases l
Yearly dose levels to an individual To assure that man and his environment within the design objectives trum are not adversely affected by the opern-I
- uAPS releases =cet the requirecents tion of PEAPS, it is necessary to coni-of 10 CFR 20 and will result tu cor the radioactivity icvols in the nefligible effcCCs to Can or hiJ environment.
environ;ent.
8100110161 g h 7 . .
I
, PBAPS 7.4 Plcnt Reporting R~quiremento 7.4.1 Routin7 RSporta In addition to the environmental monitoring information required by Section 6.9.3.h. of Appendix A to the Operating License, the following information shall be submitted in an annual report:
A. Records of special study programs data and analysis thereof.
B. Records of changes to the plant which affect the environmental impact of the facility.
C. Records of changes to environmental permits and certificates.
7.4.2 Non-Routine Reports A. In the event of an environmental deviation as defined in the environmental technical specifications, notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to the Director of the NRC Regional Inspection and Enforcement Office. A written report shall follow within 10 working days l to the Director, Office of Nuclear Reactor Regulation (copy to the Director of Regional Inspection and Enforcement Office).
The written report on an environmental deviation, and to the extent possible, the preliminary telephone and telegraph notification, should: (a) describe, analyze, and evaluate imr~ications, (b) determine the cause of the occurrence and,
'v; indicate the corrective action (including any significant
<1anges made in procedures) taken to preclude repetition of j .he occurrence and to prevent similar components or syst1ms.
l B. Reporting of Changes to the Plant or Permits l
A written report, including an evaluation of the environmental impact resulting from a change, shall be forwarded to the Director, Office of Nuclear Reactor Regulation (copy to the Director of the Regional Inspection and Enforcement Office) in the event ef:,
- 1. Changes to tha plant that affecc rhe environment-1 impact evaluation contained in the Environmental Report l or the Environmental Statement. This requirement does
! not preclude making changes on short notice that are l minor in terms of environmental impact.
l
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2.D. ' Cont'd) 4.2.D (Cunt'd) b) From and after the date that one of the two steam air ejector radiation monitors is made or found to be inoperable, continued reactor power operation is permissible, provided that l the inoperable monitor is tripped in the downscale position.
c) Upon the loss of both steam air ejector radiation monitors, either temporary radiation monitors shall ce used to monitor radiation levels, or grab samples shall be obtained at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, initiate an orderly shutdown and have the main steam isolation valves closed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 2. Reactor Building Isolation 2. Reactor Building Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall for operation are given in be functionally tested, cali-Table 3.2.D. brated and checked as indicated in Table 4.2.D.
System logic shall be func-tionally tested as indicated in Table 4.2.D.
E. Drywell Leak Detection E. Drywell Leak Detection The limiting conditions of Insicurantation shall be operation for the instru- calibrated and checked as mentation that monitors indicated in Table 4.2.E.
drywell leak detection are given in Table 3.2.E.
PDAPS l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.B Containment Cooling' 4.5.B Containment Cooling subsystem (cont'd.) , Subsystem (cont'd.)
- 3. From and after the date that- 3. When it is determined that any 3 HPSW pumps are made or any 3 HPSW pumps are in-found to be inoperable for operable, the remaining any reason, continued reactor components of both contain-operation is permissible only ment cooling subsystems during the succeeding fifteen shall be demonstrated to be days unless such pumps are operable immediately and sooner made operable provided weekly thereafter.
all remaining components of the containment cooling sys-tem are operable.
- 4. From and after the date that 4. When 3 containment cooling 3 containment coolinc subsys- subsystem loops become in-tem loops are made og found ~
operable, the operable sub-to be inope'rable for any rea- system loop and its associ-son, continued reactor opera ' ated diesel generator shall tion is permissible only dur- be demonstrated to be oper-ing the succeeding seven days able immediately and the unless such subsystem loop is operable containment cool-sooner made operable, provi- ing subsystem loop deily ded that all active compo- -
thereafter.
nents of the other contain-ment cooling subsystem' loop, including its associated die-sel generators, are opereble.
- 5. If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated
- and the reactor shall be in a Cold Shutdown Condition with-in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. I C. IIPCI Subsystem C. IIPCI Subsystem
- 1. The HPCI Subsystem shall be 1. HPCI Subsystem testing operable whenever there is shall be performed as fol-irradiated fuel in the reac- lows:
tor vessel, reactor pressure is greater than 105 psig, and Item Frequency prior to reactor startup from a Cold Condition, except as (a) Simulated Once/ opera- '
specified in 3.5.C.2 and Automatic ting cycle 3.5.C.3 below. Actuation Test
-128-
P15APJ 7 " rm ':0 cm:DITIONS FOR OPERATION GURVE1LLWCE REQUIR W.ENTS 3.7.A Prir.ary Contain~.ent 3 7.A Primary Containment mined to be not more operability is required, than 3 ' open su indica- all other vacuum brcoker ted by the position valves shall be exer-lichts or by a verification cised immedictcly and test confiraing the ability every 15 days thereafter to uaintain a positive dry- until the inoperable valve well to torus differeni,lal ,
han been returneil to j pressure. i normal service.
- c. Two drysell-suppresJion e. Once each operating chamber vacuum breakern cycle', each vacuum breaker-may be determined to be valve shall be visually inoperable for opening. inspected to insure proper maintenance and operation.
- d. If specifications 3.7. A d. A leak test of the dryvell to
.k.a. .b, or .e cannot ,'
suppression chamber structure be met, the situation shall be conducted at each re-shall be corrected within '
fueling to assure no bypass-2h hours or the unit will larger than or equivalent to one be placed in a cold shut- inch diameter hole exists between down condition in an the dryvell and suppression orderly manner. chamber.
- a. After completion of the startup The primary containmer.: oxygen test program and demonstration concentration shall be measured of plant electrical output, the and recorded at least twice weekly.
primary containment atmosphere shall be reduced to less than h% oxygen with nitroden cas during reactor power operation with reactor coolant pressure above 100 psig, except as 2
specified in 3.7.A.5.b.
- b. Within the 24-hour period subsequent to placing the reactor in the Run mode following a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than h%
by volume and maintained in this condition. De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
-171 -
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.C (Cont'd) 4.8.C (Cont'd)
- 6. The gross activity of all 6. At least annually, automatic gaseous wastes released to initiation and closure of the environment shall be waste gas system shall be monitored and recorded con- verified.
tinuously.
7a. An instrument check.of the operating hydrogen monitors shall be performed daily.
- b. The hydrogen monitors down-stream of the recombiner and alarm shall be calibrated once/ month.
- 7. During release of gaseous wastes the following conditions shall be met:
- b. The main off-gas stack minimum dilution flow of 10,000 cfm shall be maintained.
- c. Isolation devices capable of limiting gaseous release rate to within the values specified in 3.8.C.1 above shall be operable.
Ba. One reactor bui ding exhaust vent monitoring system shall be operable. If this requirement can not be satisfied, a normal orderly ;
shutdown shall be initiated [
within one hour, and the t reactor shall be in the hot shutdown condition within 10 days.
8b. One plant stack gross gaseous activity monitor shall be op3rable. If both plant j stack gross gaseous activity i monitors are j -. . -- - _ . - -
- 208 -
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS inoperable, stack effluent releases may continue for 30 days if grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
8c. One plant stack iodine and particulate sampler shall be operable. If all 4> dine samplers or all particulate samelers are inoperable, stack effluent releases may continue for 30 days, if
?,dmples are Continuously collected with auxiliary sampling equipment for periods of 5 to 9 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
i Such auxiliary sampling equipment must be placed in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the determination of '
inoperability. J 8d. One plant stack flow rate
, monitor shall be operable.
j If both plant '? tack flow rtte monitors are inoperable, stack efflueni releases may continue for 30 days, if at least or;e stack dilution fan is operating and the number of dilution fans operating is logged at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1 i
P l
- 208a - --
PDAPS Unit 2 TABLE 3.11.D.1 l
~
Safety Related Shock Suppressors (S n ub b e r s.)
' III Gil (1) ,
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEM DURING DI FFI CU LT DURING NORMAL NUMBER LOCATION AND ELEVATION SilUTDOWN TO REMOVE OPERATION TYPE (2)
See 4.11.D.4.b.
5-DDNL-S-12 Feedwater Drywell 155 "
Y Y 11 6-3DNL-S-13 Feedwater Drywell 155 Y Y 11 6-DDNL-S-14 Feedwater Drywell 155 "
Y Y H
?
9 -11B-1151 Torus Vac. Bkr. 116 "
N N M 9-!!B-Il54 Torus Vac. B". 116 "
N N M 10-HB-S-1 RilR Torus Room 93 ~
N N H l 10-GB-S-2 RilR Torus Room 93 N N 11 10-IIB-S-7 RHR B RilR Room 124 N N 11 10-HB-S-8 RHR Torus Room 93 "
N N H 10-GB-S-12 RHR C RHR Room 98 "
N N H j 10-CB-S-43-1 RHR Torus Room 130 Y N 11 10-CB-S-43-7 RHR Torus Room 130 Y N H 10-CB-S-44 RIIR Torus Room 128 "
Y N H 10-CB-S-48 RilR B RilR Room 124 "
N N H 10-GB-S-49 RHR B RilR Room 124 "
N N H 10-GB-S-50 RHR B RilR Room 98 ~
N N H
~
10-CB-S-51 RilR C RliR Room 98 N N H
-RD80-
PBAPS Unit 3 TABLE 3.11.D.1 Safety Related Shock Suppressore (Suubbers)
!!IGil (1) .
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEM DURING DI F FI CU LT DURING NORMAL ITUMBER LO C AT I O ?.' AND ELEVATION S il U T D O W N TO REMOVE OPERATION TYPE (2)
See 4.11.D.4.b.
1-GG-S-31 MSRV Drywell 155 Y Y H 1-GG-S-32 MSRV Drywell 155 Y Y H 1-GC-S-33 MSRV Drywell 155 Y Y 11 1-GG-S-34 MSRV Drywell 155 Y Y 11 1-GG-S-35 MSRV Drywell 155 Y Y H 1-GG-S-36 MSRV Drywell 155 Y Y H 1-GG-S-49 MSRV Drywell 155 Y Y H 1-GG-S-50 MSRV Drywell 155 Y Y 11 1-GG-S-51 MSRV Drywell 155 Y Y H 1-GG-S-52 MSRV Drywell 155 Y Y H 1-GG-S-53 MSRV Drywell 155 Y Y 11 1-GC-S-54 MSRV Drywell 155 Y Y 11 1 '
1-GG-S-55 MSRV Drywell 155 "
Y Y 11
-234h -
PBAPS Unit 3 s .
TABLE 3.11.D.1 Safety Related Shoc k Suppre ssorn (Snubbers)
HIGH (1) .
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER S YS TE!! DURING DI F FI CU LT DUP.ING NORMAL NUMBER LOCATION AND ELEVATION SHUTDOWN TO REMOVE OPERATION TYPE (2 )
See 4.11.D.4.o.
1-GG-S-57 MSRV Drywell 155 "
Y Y H 1-GG-S-59 MSRV Drywell 155 "
Y Y H 1-GG-S-60 MSRV .Drywell 155 "
Y Y H 1-GG-S-61 MSRV Drywell 155 "
Y Y H 1-GG-S-62 MSRV Drywell 155 "
Y Y H 1-GG-S-63 MSRV Drywell 155 "
Y Y H 1-GG-S-64 MSFV Drywell 1.55 "
Y Y H 1-GG-S-65 MSRV Drywell 155 "
Y Y H 1-GG-h-66 MSRV Drywell 155 "
Y Y H 1-GG-S-67 MSRV Drywell 155 "
Y Y H 1-GG-S-68 HSAV Drywell 155 "
Y Y H 1-GG-S-69 MSRV Drywell 155 "
Y Y H SS-A-1 Main Stean Drywell 150 "
Y Y H SS-A-3 Main Steam Drywe:.1 150 "
Y Y_ h
-2041-
ymn . ---m_ - . . , ,. -
PBAPS Unit 3 s .
TABLE 3.11.D.1 Safety Related Shock Suppressucs (Snubbers)
HIGH (1) .
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEl! DURING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SHUTDOWN TO REMOVE OPERATION TYPE (2)
Sec 4.11.D.4.b.
6-DDNL-S-8 Feedwater Drywell 168 Y Y H 6-DDNL-S-9 Feedwater Drywell 168 ,
Y Y 11 6-DDNL-S-10 Feedwater Drywell 168 Y Y 11 6-DDNL-S-11 Feedwater Drywell 155 Y Y H 6-DDNL-S-12 Feedwater Drywell 155 Y Y H 6-DDNL-S-13 Feedwater Drywell 155 "
Y Y ll 6-DDNL-S '4 Feedwater Drywell 155 Y Y 11 9 -11 B-1151 Torus Vac. Bkr. 116 N N M 9-HB-Il53 Tores Vac. Bkr. 116 N N M 10 -II B -S - 1 RilR Torus Room 93 N N M 10-GB-S-2 Ri!R Torus Room 93
); N H
. 0 -II B -S -7 RHR B RilR Room 124 N N H 10 -II B -S -8 RilR Torus Room 93 N N 11 10-GB-S-12 RilR C RilR Room 98 Y N 11 10-GB-S-43-1 RHR Torus Room 130 Y N H 10-GB-S-43-2 RilR Torus Room 130 Y N 11 10-GB-S-44 RilR Torus Room 128 Y N M e
PBAPS Unit 3 TABLE 3.11.D.1 Safety Related Shock Suppressors (Snubbers) '
HIGH (1) ,
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEM DURING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SilUTDOWN TO REMOVE OPERATION TYPE (2 )
See 4.11.D.4.b.
10-DCN-S-73 RHR Drywell 180 "
N N H 10-DCN-S-74 RHR Drywell 130 "
Y Y 11 10-CB-S-81 RHR B RHR Room 120 "
N N M 12-DCN-S-2 RWCU Iso. Valve Rm 173.5 "
Y Y it' 12-DCN-S-5 RWCU Drywell 165 "
Y Y H 12-DCN-S-7 RWCU Drywell 165 "
Y Y H 12-DCN-S-9 RWCU Drywell 165 "
Y Y M 1,-HCR-S-4 Core Spray B/D Ccre 127.5 "
N N M Spray Roon 14-DCN-S-23 Core Spray Drywell 168 "
Y Y H 14-DCN-S-24 Core Spray Drywell 168 "
Y Y H 14-DCN-S-26 Core S pray Drywell 168 "
Y Y H 14-DCN-S-27 Core Spray- Drywell 168 "
Y Y H
-2340-
PBAPS Unit 3 s .
TABLE 3.11.D.1 Safety Related Shock Suppressors (Snubbers)
IIIGH (1) .
RADIATION AREA ESPECI ALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEM DURING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SilUTDOWN TO REMOVE OPERATION TYPE (2 )
See 4.11.D.4.b.
1 3 -IIB-S -23 RCIC RCIC Room 103 Y Y H 23-DBN-S-1 HPCI Torus Room 121 Y Y 11 2 3-11B-S -1 A HPCI !!P CI Room 103 Y Y H 23-DDN-S-2A HPCI HPCI Room 103. N Y H 2 3-IIB-S -3 A HPCI HPCI Room 100 Y Y H 23-DBN-S-6-1 HPCI Torus Room 121 Y N H 23-DBN-S-6-2 HPCI Tor'as Room 121 Y E H 23-DBN-S-22 !!P CI Drywell 155 Y Y 11 2 3 -D Bli-S -2 3 IIPCI Drywell 155 Y Y H 23-DEN-S-29 HPCI IIP CI Room 117 N N H 23-UDii-S-33 HPCI HPCI Room 93 N N 11 23-DDN-S-47 IIP CI Torus Room 121 N N M 27-IICR-S-187 HPCI B/D Core 127.5. N N H Spray 2 7-IICR-S-108 !!PCI Torus Room 122.8 N N M
-234p-
PBAPS Unit 3 TABLE 3.11.D.1 Safety Related Shock Suppressors (Snutbers)
II I Gil (1)
- RADIATION AREA ESPECI ALLY (1) INACCESSIBLE (1)
SNUBBER S Y S T E!! DURING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION SilU T DOW N TO REMOVE OPERATION TYPE (2 )
Sec 4.11.D.4.b.
1-GG-S-101- A !!S R V Drywell 135 "
Y Y M 1-CG-S-101-B MSRV Drywell 135 Y Y M 1-GG-S-102-A MSRV Drywell 135 Y Y M 1-GG-S-102-B HSRV Drywell 135 Y Y M 1-GG-S-103-A MSRV Drywell 135 "
Y Y !!
1-CG-S-103-B MSRV Drywell 135 Y Y M 1-GG-S-104-A MSRV Drywell 135 Y Y M 1-GG-S-104-B MSRV Drywell 135 "
Y Y M 1-GG-S-105-A MSRV Drywell 135 Y Y !!
1-CG-S-105-B MSRV Drywell 135 "
Y Y M 1-GG-S-106-A MSRV Drywell 135 Y Y M 1-GG-S-106-B liSRV Drywell 135 ) Y M 1-GG-S-108-A MSRV Drywell 145 "
) Y M 1-CG-S-10 8 -B MS RV Drywell 145 Y Y M
-234q-
PBAPS Unit 3 TABLE 3.ll.D.1 Safety Related Shock Suppressors (Snubbers)
II I Gli (1)
- RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
SNUBBER SYSTEM DURING DIFFICULT DURING N O ItM AL N 'J l B E R LOCATION AND ELEVATION S ilU T D OWN TO REMOVE OPERATION TYPE (2)
Sec 4.11.D.4.b.
1-GG-S-109-A MSRV Drywell 145 "
Y Y M l-GG-S-109-B !!SRV Drywell 145 Y Y M l-GG-S-110-A MSRV Drywell 145 Y Y M 1-GG-S-110-8 MSRV Drywell 145 Y Y M l-GG-S-Ill-A MSRV Drywell 145 Y Y M 1-GG-S-Ill-B MSRV Drywell 145 Y Y M 1-GG-S-112-A MSRV Drywell 145 Y Y M 1-GG-S-ll2-B MSRV Drywell 145 Y Y M 1-GG-5201 MSRV Drywell 160 Y Y M 1-GG-S202 MSRV Drywell 160 Y Y M l-CG-S203-A MSRV Drywell 160 Y Y M l-GG-S203-B MSRV Drywell 140 Y Y M l-GG-S204-A HSRV Drywell 130 Y Y M l-GG-S204-B MSRV Drywell 130 "
Y Y M 1-GG-S205-A MSI.V Fcywell 160 "
Y Y M
-2 3 4r -
PBAPS Unit 3 TABLE 3.11.D.1 Safety Related Shoc k Suppressors (Snubbers)
!!I Gil (1) ,
RADIATION AREA ESPECIALLY (1) INACCESSIBLE (1)
S5UBBER SYSTEM DURING DIFFICULT DURING NORMAL NUMBER LOCATION AND ELEVATION S!!UTDOWN TO REMOVE OPERATION TYPE (2)
Sec 4.11.D.4.b.
1-GG-S205-B !!S R V Drywell 160 Y Y t!
1-CG-S206-A MSRV Drywell 160 Y Y M 1-GG-S206-B MSRV Drywell 160 "
Y Y M 1-GG-S207-A MSRV Drywell 125 Y Y M l-GG-S207-B MSRV Drywell 125 Y Y M l-GG-S208-A MSRV Drywell 125 Y Y M 1-GG-S208-B MSRV Drywell 125 Y Y M 1-GG-S209-A MSRV Drywell 125 Y Y M l-GG-S209-B MSRV Drywell 125 Y Y M Notes for Table 3.ll.D.1
- 1) Yes (Y) or No (N)
- 2) lirdraulic (H) or Mechanical (M)
-234s_ ,