ML20216D693
| ML20216D693 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/23/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20216D698 | List: |
| References | |
| DPR-66-A-110 NUDOCS 8706300575 | |
| Download: ML20216D693 (49) | |
Text
p pn ato,#'o v
i UNITED STATES l'
'i NUCLEAR REGULATORY COMMISSION al WASHINGTON, D. C. 20555 l
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY j
PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Comission) has found that:
l l
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated January 15, 1986 and revised by letters-dated May 8 and June 30, 1986, January 15, March 5, March 17 and April 6,1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; R.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment.is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
e706300575 B70623 ADOCKOSOOg4 PDR P
l
u v:.,
,e-
_p.
(2) Technical Specifications f
The Technical Specifications contained in Appendix A, i
as revised through Ameniment No.110, are.hereby incorporated in the license. The licensee shall i
operate the facility in accordance with the Technical Specifications.
)
3.
.This amendment is effective on issuance, to be implemented no later' than 30 days after issuance.
i FOR THE NUCLEAR REGULATOR COMMISSION L,.
J h 'F.
Stolz, Director 1
ro ect Directorate I-4 iv sion of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: June 23,1987 s
l i
m 1
p 4
4 m
ATTACHMENT 'TO LICENSE AMENDMENT N0.110 '
FACILITY OPERATING LICENSE NO. DPR DOCKET N0. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages Comments I thru XVIIa I'thru XXVI Retyped Index Deleted blank page 3/4 1-26 3/4 4-29 Deleted. blank page 3/4 4-30 Deleted blank page 3/4 4-31 3/4 4-29' Renumbered 3/4 5-8 Deleted blank page 3/4.7-23
'3/4 7-23 Added (next pg is 3/4.,7-26)..
'3/4'7-24 Deleted blank page 3/4 7-25 Deleted blank page 3/4 11-16' 3/4 11-16 Added (next pg.is 3/4 : 11'-18).
3/4 11-17 Deleted blank page.
3/4 11-18 3/4 11-18 Added.(nextpg.is 3/4 11-20)i.
3/4 11-19.,
-Deleted blank page-6-15 6-15:
- Added info.'from pages 16/6-17. 6-18,~6-19 and-Added.(next.page is 6-20) 6-16/6-17 Deleted; blank page-6-18 Deleted blank 'page1 6-19
. Deleted blank page
'6-1 6-1
. Reorganization; 6-la 6-la-
. Reorganization" 6-2 6-2 Reorganization 6-3 6 Reorganization:
6-4 6-4
- Reorganization:
6-5 6-5 ReorganizationL 6-6 6-6<
Reorganization 6-7 6-74
~ Reorganization; 6-8 6-8 Reorganization-6 6-9 Reorganization 6 6-11_
LReorganization 6-12 6-12 Reorganization.
6 6-13
' Reorganization-6-30' 6-30
' Corrected aLtypographical?
error a s
~6-31 6-31l 4
Reorganization)
B3/4 11-2 B3/4 11-2,
LCorrected a typographical;<
error -
- v c
1
+
t-l
---y-
---q
.4'
+
INDEX-DEFINITIONS J
'SECTION' 1
~PAGE 1.0 : DEFINITIONS
-i Defined Terms.................'......
1-1 l
. Thermal Power.....................~..
1 -l' 1
Rated The rmal Powe r................... '..
1 1-1 Operational Mode Action...............,......-......
1-1
- 1-1 Operable'- Operability Reportable Event 1-2 Containment Integrity................,...
1-2.
Channel Calibration..........
........... 2
]
1 Channel Check............................-
1-2 1 j Channel Functional Test
.t...........,......
Core Alteration.......................
. 1-3 1
1 j
Shutdown Margin..............
1-3 Identified Leakage
...........s.......'..-.
1-3, j
1 Unidentified Leakage........:.......
1 3 Pressure' Boundary. Leakage '...... :.... -.>........ ;...
1 j Controll ed Leallage.................... :....
1-4
~
Quadrant Power Til t Ra tio............. :-......
1-4' Ti Dose Equivalent I-131...............-.-....
. -l-4 ?
y j
Staggered Test Basis....'........c.
-.1 -41 i
. Frequency Notation.........'.-...-...<....
1-4;
.....n..
l-5 j
f Reacto'rl Trip System Response'. Time 3
.1 l
- Engineered Safety Feature Response Time
.7.~..
11-5.
1
.v
- l
..j 2-BEAVER VALLEY - UNIT.1:-
li
/ Amendment No'.1101 1
l t
i
.ZO i
t
s.,
f
- 4 -
3 u
'.1'
-DEFINITIONS l
SECTION PAGE i
1 Axi al -. Fl ux Di ffe rence.......................
1-5 Physics Tests 1-5 E-Average Disintegration Energy.......'.........
. 1-5 Source Check'-
1-6
]
1 Proces s ' Control Program.....................
' l l 1
Solidification.........-..-................
1-6' Off-Site Dose Calculation. Manual (0DCM)......... '... --
1-6 i
. Gaseous Radwaste Treatment System................
1 ]
Ventilation Exhaust. Treatment System............. '
1-6 i
Purge Purging....__....................
1-7!
1 Venting
' 1'-7 J
Major Changes.........,.......
.-r 1-7~
'4 Member (s) of the Public....................
. 1-8L I
Operational Modes (Table 1.1).............
' l-9' l
Frequency Notation (Table 1.2)
. 1-10 9
i 5
l d
4
.l f
<j.
j i
l 1
1 Y
r y
' BEAVER VALLEY - UNIT 1-
'II IAmendment'No.)115
'l ?(
(
,4,.
-k
/ g INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 Reactor Core......................
2-1 2.1.2 Reactor Coolant System Pressure 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip System Instrumentation Setpoints......
2-5 BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 Reactor Core.......................
B 2 )
2.1.2 Reactor Coolant System Pressure.............
B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip Setpoints B 2-3 i
a BEAVER VALLEY - UNIT 1 III Amendment No.110
,1 5,
a INDEX LIMITING CONDITIONS FOR OPERATION.AND SURVEILLANCE REQUIREMENTS-SECTION PAGE' 3/4.0 APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 1
3/4.1.1 BORATION CONTROL 3/4.1.1.1 Shutdown Margin - T
> 200 F 3/4 1............
avg 3/4.1-3 I
3/4.1.1.2 Shutdown Margin - Tavg 200*F 3/4.1.1.3 Boron Dilution 3/4 1-4 3/4.1.1.4 Moderator Temperature Coefficient..........
3/4 1-5.
3/4.1.1.5-Minimum Temperature for Criticality..........
3/4 176 i
3/4.1.2 B0 RATION SYSTEMS 3/4.1.2.1
. Flow Paths - Shutdown.................
3/4 1-7
]
3/4.1.2.2 Flow Paths - Operating 3/4 1................
3/4.1.2.3 Charging Pump - Shutdown 3/4 1-11 3/4.1.2.4 Charging Pumps - Operating 3/4 1-12 3/4.1.2.5 Boric Acid Transfer Pumps - Shutdown..........
'3/4 1-13 3/4.1.2.6 Boric Acid Transfer Pumps - Operating.........-
3/4 1-14 3/4.1.2.7 Borated Water Sources - Shutdown 3/4 1-15 l
3/4.1.2.8 Borated Water Sources - Operating.............
3/4 1.
c i 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 3/4.1.3.1 Group Height S/4.1-18 3/4.1.3.2 Position Indication Systems.-' Operating.........
3/4 1-20 3/4.1.3.3 Position Indication System - Shutdown......'.....
3/4 1-21~
~
3/4.1.3.4 Rod Drop Time................~........
3/4.1-22 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4 1-23 3/4.1.3.6 Control Rod Insertion Limits 3/4 1-23A BEAVER VALLEY.- UNIT'1-IV
. Amendment No.110 r
7, a
-INDEX I
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
-a SECTION PAGE a
1 3/4.2 POWER DISTRIBUTION LIMITS I
3/4.2.1
- AXIAL FLUX DIFFERENCE.................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4 2-5
)
j 3/4.2.3 NUCLEAR ENTHALPY HOT. CHANNEL FACTOR..........
3/4 2-8 3/4.2.4 QUADRANT POWER TILT RADIO...............
3/4 2-10 j
3/4.2.5 DNB PARAMETERS 3/4 2-12 3/4.3 ~ INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM I'NSTRUMENTATION,..........
3/4 3 1 l
3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION-SYSTEM INSTRU-MENTATION.........................
3/4 3-14' 3/4.3.3.
MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring..................
3/4 3-33' q
q 3/4.3.3.2 Movable Incore Detectors........-.......;...
3/4:3-37 j
3/4.3.3.3 Seismic Instrumentation................:..
3/4 3 3/4.3.3.4 Meteorological. Instrumentation.............:.
3/4-3 (
3/4.3.3.5 Remote Shutdown Instrumentation.......'....
.z.-
3/4 3-44' 3/4.3.3.6 Fire Detection Instrumentation........ -....
3/4 3-47 3/4.3.3.7 Chlorine Detection-Systems...:..........;..e.
3/4 3-49/
3/4.3.3.8 Accident Monitoring Instrumentation.......... :
3/4 3-50' 1,
3/4.3.3.9 Radioactive Liquid Effluent honitoring Instrumentation.
.3/4 3 3/4.3.3.10 Radioactive Gaseous Effluent Monitoring-Instrumentation' 3/4 3-59 BEAVER VALLEY.- UNIT 1 V
Amendment Nc. 1101
/
INDEX LIMIT 7NG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS 3/4.4.1.1 Normal Operation 3/4 4-1 3/4.'. 1.2 Hot Standby......................'
3/4 4-2b 3/4.4.1.3 Shutdown 3/4 4-2c 3/4.4.1.4 Isolated Loop.....................
3/4 4-3 3/4.4.1.5 Isolated Loop Startup.................
3/4 4-4 3/4.4.1.6 Reactor Coolant Pump Startup 3/4 4-4a 3/4.4.2 SAFETY VALVES SHUTDOWN 3/4 4-5 j
i 3/4.4.3 SAFETY VALVES - OPERATIhG...............
3/4 4-6
)
l 3/4.4.4 PRESSURIZER......................
3/4 4-7 1
1 3/4.4.5 STEAM GENERATORS...............'....
3/4 4-8 i
i
]
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 Leakage Detection Systems...............
3/4 4-11 3/4.4.6.2 Operational Leakage.........,........
3/4 4-13 j
3/4.4.6.3 Pressure Isolation Valves...............
3/4 4-14a 3/4.4.7 CHEMISTRY.......................
3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY...................
3/4 4-18' 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 3/4.4.9.1 Reactor Coolant System 3/4 4-22 BEAVER VALLEY - UNIT 1 VI Amendment No.110
i INDEX
.1 LIti1 TING CONDITIONS FOR OPERATION At:0 SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9.2
. Pressurizer.......................
3/4 4-27 3/4.4.9.3 Overpressure Protection Systems............
3/4 4-27a-3/4.4.10 STRUCTURAL. INTEGRITY - ASME Code Class 1,.2 and 3 E
Components 3/4 4-28 3/4.4.11 RELIEF VALVES.....................
3/4 4-29 3/4.5 EMERGENCY CORE C0OLING SYSTEMS (ECCS)'
3/4.5.1 ACCUMULATORS 3/4 5 l 3/4.5.2 ECCS SUBSYSTEMS - T 3 350 F 3/4 5-3' avg 3/4.5.3 ECCS SUBSYSTEMS - T
< 350 F 3/4'5-6' avg 3/4.5.4 BORON INJECTION SYSTEM 3/4.5.4.1.1 Boron Injection Tank 3 350 F..
3/4 5-7!
3.4.5.4.1.2 Boron Injection Tank < 350 F.........
3/4 5-7a, 1
3/4.5.5' Deleted.by Amendment No. 75' 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3
3/4.6.1.1 Containment Integrity....................
3/4 6-1 3/4.6.1.2 Containment Leakage................
.f.
.3/4 6-2 3/4.6.1.3. Contai nment Ai r Lo c k s....,,...............
3/4 6 3/4.6.1.4-Internal Pressure.......-........;.
3/4 6-6L 3/4.6.1.5 Ai r Tempe ratu re.....................
3/4 6'-8.
-i 3/4.6.1.6 - Containment Structural Integrity 3/4 6-101-
.:..7.
BEAVER VALLEY'- UNIT 1
.VII
. Amen'dment No.110; i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE w ion 1
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 Containment Quench Spray System............
3/4 6-11 3/4.6.2.2 Containment Recirculation Spray System 3/4 6-13 3/4 6-15 3/4.6.2.3 Chemical Addition System 3/4 6-17 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL f
3/4 6-20 3/4.6.4.1 Hydrogen Analyzers 3/4.6.4.2 Electric Hydrogen Recombiners.............
3/4 6-21 3/4.6.4.3 Hydrogen Purge System.................
3/4 6-23
)
3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 Steam Jet Ai r Ejector.................
3/4'6-25 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves.
3/4 7-1 3/4 7-5 1
3/4.7.1.2 Auxiliary Feedwater System 3/4.7.1.3 Primary Plant Domineralized Water (PPDW):
3/4 7-7 3/4 7-8 3/4.7.1.4 Activity 3/4 7-10 3/4.7.1.5 Main Steam Line Isolation Valves
?/A.'.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...
3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-12 3/4.7.4 RIVER WATER SYSTEM 3/4.7-13~
3/ 4'. 7. 5 ULTIMATE HEAT SINK - OHIO RIVER....
3/4 7-14
^!
BEAVER VALLEY - UNIT 1 VIII Arrendment No.110
INDEX LIMITING. CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.6 FLOOD PROTECTION 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS.......
3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM....
3/4 7-19 3/4.7.9 SEALED SOURCE CONTAMINATION..............
3/4 7-22 3/4.7.10 Deleted by Amendment No. 43 3/4.7.11 Deleted by Amendment No. 43 3/4.7.12 SNUBBERS 3/4 7-26 3/4.7.13 AUXILIARY RIVER WATER SYSTEM 3/4 7-34 3/4.7.14 FIRE SUPPRESSION SYSTEMS 3/4.7.14.1 Fire Suppression Water System.............
3/4 7-35 3/4.7.14.2 Spray and/or Sprinkler System.............
3/4'7-39 3/4.7.14.3 Low Pressure C0 System......
3/4 7-41 2
3/4.7.14.4 Fire Hose Stations
'3/4 7-42 3/4.7.14.5 Halon Systems...............;......
3/4 7-43 3/4.7.15 FIRE RATED ASSEMBLIES.................
_3/4 7-4a 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES.
3/4.8.1.1 Operating.......................
3/4 8-1 3/4.8.1.2 Shutdown 3/4 8-5 3/4.8.2.
ONSITE POWER DISTRIBUTION SYSTEMS 3/4.8.2.1 A.C. Distribution - Operating.............
3/4 8-6 BEAVER VALLEY - UNIT 1 IX
. Amendment ik). 110 6
INDEX s
LIMITIrlG CONDITIONS'FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8.2.2 A.C. Distribution ~- Shutdown 3/4 8-7 3/4.8.2.3 D.C. Distribution - Operating.............
'3/4 8-8 3/4.8.2.4 D.C. Distribution - Shutdown 3/4 8-10 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION..................
3/4 9-l' 3/4.9.2 INSTRUMENTATION....................
3/4 9-2 3/4.9.3 DECAY TIME 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS...........
3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9....................-
3/4.9.6 MANIPULATOR CRANE OPERABILITY.............-
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L BUILDING....
3/4 9-7 3/4.9.8.1 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION
~....
3/4 9-8 3/4.9.8.2 LOW WATER LEVEL....................
3/4'9-8a 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM 3/4 9....
3/4.9.10 WATER LEVEL-REACTOR VESSEL 3/4 9-10 3/4.9.11 STORAGE P0OL WATER LEVEL.
3/4 9-11 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM - FUEL MOVEMENT 3/4 9-12 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM - FUEL STORAGE....
3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS i
3/4.10.1 SHUTDOWN MARGIN.....................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.
3/4 10-2 BEAVER VALLEY - UNIT 1 X
Amendment' No.110 m
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE' REQUIREMENTS i
SECTION PAGE I
3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS - REACTOR' CRITICALITY.
3/4 10 i 3/4.10.4 PHYSICS TESTS.....................
3/4 10-6 3/4.10.5 N0 FLOW TESTS.....................
3/4 10-7
)
W
'3/4.11 RADI0 ACTIVE EFFLUENTS.
3/4.11.1 LIQUID EFFLUENTS 1
3/4.11.1.1 Concentration.....................
3/4 11-1 3/4.11.1.2 Dose 3/4 11-6 3/4.11.1.3 Liquid Waste Treatment 3/4 11-8 3/4.11.1.4 Liquid Holdup Tanks..................
3/4 11-10
'l 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 Dose Rate.......................
3/4 11-11 3/4.11.2.2 Dose - Noble Gases 3/4 11-15 3/4. ':.1. 2. 3 Dose - Radiciodines, Particulates, and Radionuclides Other than Noble Gases.....................
.3/4 11-16 3/4.11.2.4 Gaseous Radwaste Treatment 3/4 11-18 I
3/4.11.2.5 Gas Storage Tanks...................
3/4 11-20 3/4.11.2.6 Explosive Gas Mixture..................
3/4 11-21 3/4.11.3 SOLID RADI0 ACTIVE WASTE................
3/4 11-22 3/4.11.4 TOTAL DOSE 3/4 11-23 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4 12-1 3/4.12.2 LAND USE CENSUS....................
3/4 12-10
.3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM 3/4 12-12 Amendment No.110 BEAVER VALLEY - UNIT 1 XI
-INDEX BASES SECTION PAGE 1
3/4.0 APPLICABILITY B 3/4 0-1 1
3/4.1 REACTIVITY CONTROL SYSTEMS i
3/4.1.1 B0 RATION CONTROL B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-3 j
i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE.................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY H0T CHANNEL FACTORS........................
B 3/4 2-4 3/4.2.4 QUARDRANT POWER TILT RATIO...............
B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-6 q
3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION....................
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-2 3/4.3.3.1 Radiation Monitoring Instrumentation B 3/4 3-2 3/4.3.3.2 Movable Incore Detectors B 3/4 3-2 3/4.3.3.3 Seismic Instrumentation B 3/4 3-2 3/4.3.3.4 Meteorological Instrumentation B 3/4 3-2 3/4.3.3.5 Remote Shutdown Instrumentation............
B 3/4 3-3 3/4.3.3.6 - Fire Detection Instrumentation B 3/4 3-3 BEAVER VALLEY - UNIT 1 XII Amendment No.110 r
Q 1
]
INDEX 1
a
. BASES i
q U
.J SECTION
,PAGE-j 3/4.3.3.7 Chlorine Detection Systems
'B 3/4'3-3
's 1
3/4.3.3.8 Accident Monitoring In'strumentation...........
B 3/4 3 3
~
3/4.3.3.9 Radioactive Liquid Effluent Monitoring Instrumentation.
' B 3/4 3-4
)
h 3/4.3.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation B 3/4 3-4 y
.J 3/4.4-REACTOR COOLANT SYSTEM 3/4.4.1' REACTOR COOLANT LOOP 5'.
B 3/4 4-11 3/4.4.2 and 3/4.4.3 SAFETY VALVES...............>.... B 3/4 4-la:
. B 3/4 4-2 3/4.4.4 PRESSURIZER.......
3/4.4.5-STEAM GENERATORS............,.:...-.....
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE'.....=....
..;.'.g:.
.B.3/4 4-3 3/4.4.6.1 Leakage; Detection System'..........-. ;..
.-s
- B.3/4 4-3~
j 3/4.4.6.2 Operational Leakage......-,...,,.g.g.-
lB 3/4'4 3.
1 3/4.4.7 CHEMISTRY..........................~.
- B3/4I4-4 ci 3/4.'4.8 SPECIFIC ACTIVITY.,.......-...... '..<....-.-
B 3/4-4A4i
'i 3/4.4.9
. PRESSURE / TEMPERATURE LIMITS...-..........:.
- B 3/4.4-St 3/4.4.10 STRUCTURAL. INTEGRITY
............;..:.....:.=
B 3/4 4-10.
)
3/4.4.11 RELIEF VALVES..........'..........>.
.1 B 3/4 A-10l 1
n i
r 3/4.5 -EMERGENCY CORE COOLING SYSTEMS (ECCS)
.#B[3/4i5-1_.
- .3/4. 5.1 ACCUMULATORS....
..1
...;....;...:.;....s.7 3/4.5.2:
and.3/4.5.3.ECCS SUBSYSTEMS................j _... :-:. 4.B'3/4(5-1?
.. BEAVER VALLEY.-:UNITel.
XIII AmendmentL No.110 t
W' s >
INDEX
-]
BASES 1
S PAGE
. EC.T_IO. N -
3/4.5.4-BORON INJECTION SYSTEM B 3/4 5-1 3/4.5.5 (Moved to Bases Section 3/4.1.2) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 Containment Integrity................
B 3/4 6-1 3/4.6.1.2 Containment Leakage.................
B 3/4 6-1 i
3/4.6 1.3 Containment Airlocks B 3/4 6-1 3/4.6.1.4
. and 3/4.6.1.5 Internal Pressure and Air Temperature.
B 3/4 6-2 j
3/4.6.1.6 Containment Structural Integrity B 3/4 6-2 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 and 3/4.6.2.2 Containment Quench and Recirculation.
Spray Systems....................
B 3/4 6-2 3/4.6.2.2 Chemical Addition System B 3/4.6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL.............,.-
B 3/4 6-3 i
i 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/A.6.5.1 Steam Jet Ai r Ejector.................
B 3/4 6-3 3/4.6.5.2 Deleted by Amendment No. 78.
j 3/~.7 FLANT SYSTEMS i
3/4.7.1 TURBINE, CYCLE 3/4.7.1.1 S af e ty Val ve s........... _.........
B 3/4 7-1
'l BEAVER VALLEY - UNIT 1 XIV Amendment No. 11D i
l T
INDEX
- BASES, x
\\
SECTION PAGE s
.' s 3/4.7.1.2 Auxilia y Feedwater Pumps.......'.......
E 3/4 7-2 3/4.7.1.3 Primary Plant Demineralized Water...........
B 3/4 7-2 B 3/4 7-3 3/4.7-1.A Activity 3/4.63.5 Main Steam Line Isolation Valves B 3/4 7-3 3/4./.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...
B 3/4'7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-4 3/4.7.4 RIVER WATER SYSTEM'..................
B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK.................
B 3/4 7-4 3/4.7.6
-FLOOD PROTECTION B 3/4 7-4.
3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM B 3/4 7-5 3/4.7.B SUPPLEMENTAL. LEAK COLLECTION AND RELEASE SYSTEM..,.
B 3/4 7-5 3/4 7.9 SEALED SOURCE CONTAMINATION.............
B 3/4 7-5 3/4.7.10 and 3/4.7.11 Deleted by Amendment No. 43 3/4.7.12 SNUBBERS B 3/4 7-6 3/4.7.13 AUXILIARY RIVER WATER SYSTEM B 3/4 7-7 3/4.7.14 FIRE SUPPRESSION SYSTEMS B 3/4 7-7 3/4.7.15 FIRE RATED ASSEMBLIES ~................
B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.B.1 and 3/4.8.2 A.C. SOURCES, D. C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 1
BEAVER VALLEY.- UNIT 1 XV Amendment No.110
INDEX BASES SECTION
- PAGE, 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION...............
B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE OPERABILITY............
B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4'9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.....
B 3/4.9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL B 3/4 9-3 3/4.9.12 and 3/4.9.13. FUEL BUILDING VENTILATION SYSTEM.....
B 3/4.9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................
B 3/4 10 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS-B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY.
.B 3/4 10-1 3/4.10.4 PHYSICS TESTS......................
B'3/4 10-1 3/4.10.5 NO FLOW TESTS....................
B 3/4 10-1 BEAVER VALLEY. UNIT 1 XVI Amendment No.110. '
s
~..
INDEX 1
BASES' SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS
'3/4.11.1.1 Conceritration B 3/4 11-1
)
i 3/4.11.1.2 Dose B 3/4 11-1.
3/4.11.1.3 fliquidWasteTreatment B 3/4 11-2' l
. 3/4.11.1.4 Liquid Holdup Tanks................<..
B 3/4 11' - !
(
1 3/4.11.2 GASE0US EFFLUENTS ~
3/4.11.2.1-Dose Rate.:.....................
B 3/4 11-2
'3/4.11.2.2 Dose, Noble Gases...................
B 3/4 11-3<
3/4.11'.2.3 Dose, Radioiodines, Radioactive Material in Particulate Form and Radionuclides other than Noble Gases..
B 3/4'11-4 3/4.11.2.4 Gaseous Radwaste Treatment
'B 3/4 11-5 1
1 3/4.11.2.S Gas Storage Tanks.....
.-.,.x.
-B 3/4 11-5 i
3/4.11.2.'6. Ex pl os i ve Ga s Mi xtu re............... =.. -
B 3/4 11-5.
d 3/4.11.3 SOLID RADIDACTIVE WASTE................
B'3/4 11-6 1
3/4.11.4 TOTAL DOSE
......7......,.......
B 3/4'11-6' a
4 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.........;...:..-.....
B'3/4L.12-1 l
l 3/4.12.2' LAND USE CENSUS.........-.....o.. r. :.
B 3/4.12 j
~
i 3 / 4.12. 3.-
INTERLABORATORY COMPARISON PROGRAM LB 3/4 12-1.
~
........1 i;
1 BEAVER VALLEY. UNIT'1' XVII:
Amendment' No.110 -
~
.ia i
w 1
' i.;
~
,i.
)
.t
.'i u
INDEX
-l
-1 A
DESIGN FEATURES' SECTION PAGE 5.1 SITE l
.5.1.1 Site' Boundary for-daseous Effluents............
5-1 A.1. 9 Site Boundary for Liquid Effluents 5-1
. 5 5.1.3-Exclusion Area
-5.1~.4
. Low Population Zone......... '............
5-1 1
5.1.5' Flood Control.................-.......
5 i 5.2 CONTAINMENT 5.2.1-Configuration.;........... '............
5-1 5.2.2 Design Pressure and Temperature............
1
'5.
5-4
- 5.2.3 Penetrations 5.3 REACTOR' CORE
)
5.3.1 Fuel. Assemblies.......................
5-4 5.3.2 Control Rod Assemblies.....
5 1 5.4 REACTOR COOLANT SYSTEMS 5.4.1 Design Pressure and Temperature...............
5-5.
5.4.2 Volume................;..........
5-5 5.5 EMERGENCY CORE. COOLING SYSTEMS...........j......<
5-5 5.6 FUEL" STORAGE
]
5;6.1
- C ri t i ca l i ty........
.5-5:
5.6.2 D ra i n a g e..... -:.............. ;........
'5-Si i
5.6.3-l Capacity.....~.....................:......
5 '!
5.7 SEISMIC CLASSIFICATION........;.......:..o.o.
5-6' q
5.8' METEOROLOGICAL' TOWER LOCATION'...... -..,.......-...
5-6 J
a BEAVER VALLEY - UNIT 1 XVIII1 Amendment ;No. !110
I 1NDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY......................
6-1 6.2 ORGANIZATION 6-1 6.2.1 Offsite 6-1 6.2.2 Facility Staff 6.3 FACILITY STAFF QUALIFICATIONS 6-5 6-5 6.4 TRAINING i
i 6.5 REVIEW AND AUDIT 6.5.1 ONSITE-SAFETY COMMITTEE (0SC) 6-5 6.5.1.1 Function......................
6.5.1.2 Composition.....................
6-5 6.5.1.3 Alternates 6-6 6.5.1.4 Meeting Frequency................ '..
6-6 6-6 6.5.1.5 Quorum 6.5.1.6 Responsibilities 6-6 6.5.1.7 Authority....................._.
6-7 6.5.1.8 Recoiis.......................
6-7 6.5.2 0FFSITEREVIEWCOMMITTEE(ORC) 6.5.2.1 Function 6-7 6.5.2.2
. Composition.....................
6-8 6.5.2.3 Alternates 6-8 BEAVE.R VALLEY - UNIT 1 XIX Amendment No.110
t..
1:
INDEX-c.
ADMINISTRATIVE CONTROLS
.-SECTION PAGE.
6.5.2.4' Consultants.....................
6-8L 6.5.2.5
. Meeting. Frequency.._...-.............-
6-9 6-9.
6.5.2.6 Quorum
.z.
6-9 6.5.2.7 Review
'6.5.2.8
' Audits.......................
6-10 6-11 6.5.2.9' Authority........
...'.c.
6.5.2.10 Records.......................'
'6-11 6.6 REPORTABLE EVENT ACTION 6-11'
~ 6.7 SAFETY LIMIT VIOLATION-..................
6-12 6.8 : PROCEDURES..-......................
6-12--
6.9 REPORTING REQUIREMENTS...................
6-13 6.9.1 Routine Reports 6-13 6.9.1,2,3 Startup Report 6-13 6-14!
6.9.1.4,5 Annual Reports 6.9.1.6 Monthly Operating Report
' 15 6.9.1.7,8,9 Deleted by Amendment No. 84 6.9.1.10,11 Annual Radiological: Environmental Report..:...
- 6-15 6.9.1.12,13 Semi-Annual. Radioactive Effluent Release Report 6-21L 6.9.1.14 Radial ~ Peaking Factor Limit Report.
.c.... _..... -
6-22.
A y
BEAVER VALLEY - UNIT.:1-X'X L Amendment No.110.
w
?'
INDEX
~ ADMINISTRATIVE CONTROLS SECTION PAGE 6.9.2 SPECIAL REPORTS
..............a......
6-22 6.10. RECORD RETENTION................ :. :...
6 6-25;
. 6.11 ' RADIATION PROTECTION PROGRAM
.7 6.12 HIGH RADIATION AREA.......................
6-25 6.13 Deleted.by Amendment;No. 95 6.14 PROCEST CONTROL PROGRAM (PCP)-
6-273 6.15 0FFSITE DOSE CALCULATION MANUAL.........-.....-
6-27; 6.16 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS'..
6-2'8 '
-6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING' PROGRAM.......
6-31'
's 1
e BEAVERVALLEY-$ UNIT 1 I
.XXI:
. Amendment' 'Ho.1101 1
/
9
TABLE INDEX TABLE TITLE PAGE.
2.2-1 Reactor Trip System Instrumentation Setpoints 2-6 3.1-1 Accident Analyses Requiring Re-evaluation in the 3/4 1-19A event of an Inoperable Full or Part Length Rod 3.2-1 DNB Parameters 3/4 2-13 3.3-1 Reactor Trip System Instrumentation 3/4 3-2 3.3-2 Reactor Trip System Instrumentation Response Times-3/4 3-9 4.3-1 Reactor Trip System Instrumentation Surveillance 3/4 3-11 Requirements 3.3-3 Engineered Safety Features Actuation System 3/4 3-15 Instrumentation 3.3-4 Engineered Safety Features Actuation System 3/4 3-22 Instrumentation Trio Setpoints 3.3-5 Engineered-Safety Feature Response Times.
3/4 3 4.3-2 Engineered Safety Feature Actuation-System
~3/4 3-29 Instrumentation Surveillance Requirements 3.3-6 Radiation Monitoring Instrumentation 3/4 3-34 4.3-3 Radiation Monitoring Instrumen'tation Surveil-3/4.3-36 lance Requirements 3.3-7 Seismic Monitoring Instrumentation' 3/4 3-39 4.3-4 Seismic Monitoring Instrumentation Surveillance
_3/4 3-40 Requirements 3.3-8 Meteorological Monitoring Instrumentation 3/4 3-42 4.3-5 Meteorological Monitoring Instrumentation Sur--
3/4 3-43 veillance Requirements 3.3-9 Remote Shutdown Panel Monitoring Instrumentation 3/4 3-45 4.3-6 Remote Shutdown Monitoring Instrumentation Sur-3/413-46 veillance Requirements-3.3-10 Fire Detection. Instruments 3/4 3-48 3.3-11 Accident Monitoring Instrumentation 3/4 3-51 BEAVER' VALLEY UllIT 1 XXII Amendment No.110
- O Table Index TABLE TITLE PAGE 4.3-7 Accident Monitoring Instrumentation Surveillance 3/4 3-52 Requirements 3.3-12 Radioactive Liquid Effluent Monitoring Instru-3/4 3-54 mentation 4.3-12 Radioactive Liquid Effluent Monitoring Instru-3/4 3-57 mentation Surveillance Requirements 3.3-13 Radioactive Gaseous Effluent Monitoring Instru-3/4 3-60 mentation 4,3-13 Radioactive Gaseous Effluent Monitoring Instru-3/4 3-65 mentation Sur'veillance Requirements 4.4-1 Minimum Number of Steam Generators to be Inspected 3/4 4-10c During Inservice Inspection 4.4-2 Steam Generator Tube Inspection 3/4 4-10d 4.4-3 Reactor Coolant System Pressure Isolation Valves 3/4 4-14c 3.4-1 Reactor Coolant System Chemistry Limics 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits Sur-3/4 4-17 eillance Requirements 4.4-12 Primary Coolant Specific Activity Sample and 3/4 4-20 Analysis Program 4.4-3 Reactor Vessel Material Irradiation Surveillance 3/4 4-26 Schedule 3.6-1 Containment Penetrations 3/4 6-19a 3.7-1 Maximum Allowable Power Range Neutron Flux High 3/4 7 Setpoint With Inoperable Steamline Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Range Neutron Flux High 3/4 7-3 Setpoint with Inoperable Steamline Safety Valves During 2 Loop Operation 4.7-1 Steamline Safety Valves Per Loop
- 3/4 7-4 4.7-2 Secondary Coolant System Specif.ic Activity Sample 3/4 7-9 and Analysis System 3.8-1 Battery Surveillance Requirements 3/4 8-9a XXIII Amendment No.110 BEAVER VALLEY UNIT 1
1
! able Index T
i TABLE TITLE PAGE 4'.11-1 Radioactive Liquid Waste Sampling and Analysis 3/4'11-3 Program 4.11-2 Radioactive Gaseous Waste Sampling and Analysis 3/4 11-13 Program 3.12-1 Radiological Environmental Monitoring Program 3/4 12-3 3.12-2 Reporting Levels for Radioactivity Concentrations 3/4 12-6 in Environmental Samples 4.12-1 Maximum' Values for the Lower Limits of Detection 3/4'12-7 8 3/4.4-1 Reactor' Vessel Toughness Data-(unirradiated)-
B 3/4-4-7 6.2-1 Minimum Shift Crew Composition 6-4 6.9-1 Environmental Radiological Monitoring Program 6-20 Summary E
-)
BEAVER VALLEY UNIT 1 XXIV
' Amendment No.110-
.t
\\
Figure Index a
FIGURE TITLE PAGE.
-l 2.1-1, Reactor Core Safety Limit - Three Loops in 2-2 Operation 2.1-2 Reactor Core Safety Limit - Two Loops in. Opera-2 tion (One Loop Isolated) 4 2.1-3' Reactor Core Safety Limit - Two Loops in Opera-2-4 q
tion (No Isolated Loop) 2.1-1 Rod Group Insertion Limits Versus Thermal Power 3/4 1-24
- Three Loop-Operation 3.1-2 Rod Group Insertion Limits Versus Thermal Power 3/4 1-25
- Two Loop Operation l
I 3.2-1 Axial Flux Difference Limits as a Function of 3/4 2-4 d
Rated Thermal Power
'l
'l 3.'2-2 K(z) - Normalized Fn(z) as a function of Core 3/4 2-7 Height.
3.2-4 Rod Bow Penalty as a Function of Burnup.'
3/4 2-9a.
3.4-1 Dose Eauivalent I-131 Primary Coolant : Specific 3/4 4-21 Activity Limit Versus Percent of Rated Thermal Power with the Primary Coolant Specific Activity ). 1.0 pCi/ gram Dose Equivalent'I-131 j
3.4-2 BeaverValleyUnitNo.1ReactorCool'antiSystem 3/4.4-24 Heatup Limitations Applicable for the First 6 EFPY' 3.4-3 Beaver Valley Unit No. 1 Reactor Coolant System 3/4.4-25 Cooldown Limitations Applicable for the Firsti 6 EFPY 3.6-1 Maximum' Allowable Primary Containment Air Pressure-3/4 6-7 Versus River ~ Water Temperature.and RWST Water Temp-erature i
B 3'/4.2-1 Typical Indicated Axial Flux 0'ifference Versus B 3/4 2-3 l
Thermal Power at BOL.
-s S 3/4.4-1
' Fast Neutron Fluence (E>I Mev).as a Function of B;3/4'4-6a j
Full Power Service Life B 3/4.4-2 Effect of Fluence, Copper Content.-and Phosphorus-B 3/4-4-6b:
l Content on ARTNOT for Reacto.r Vessel Steels Per:
IBEAVER VALLEY UNIT-1 Amendment No.110--
gy I
1 Figure Index FIGURE TITLE PAGE a.1-1 Site Boundary for Gaseous Effluents for the 5-lb Beaver Valley Power Station 5.1-2 Site Boundary for Liquid Efluents for the Beaver 5-Ic Valley Power Station 5.1-3 Exclusion Area - Beaver Valley Power Station 5-1d 5.1-4 Low Population Zone - Beaver Valley Power Station 5-le 5.1-5 Gaseous Release Points - Beaver Valley Power 5-2 Station 5.1-6 Liquid Release Points - Beaver Valley Power 5-3 i
Station 6.2-1 Corporato Organization (Partial) 6-2 1
6.2-2 Facility Organization 6-3 1
i i
i
)
l XXVI BEAVER VALLEY UNIT 1 Amendment No.110-
REACTOR COOLANT SYSTEM 3/4.4.11 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.11 (Two) power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3 ACTION:
a.
With less than 2 PORV(s) operable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore two PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be i
in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 1
4.4.11.1 Each PORV shall be demonstrated OPERABLE:
1 a.
At least once per 31 days by performance of a CHANNEL CHECK of the position indication, excluding valve operation and j
i b.
By performance of a CHANNEL CALIBRATION in accordance with Table 4.3-7 on the operable PORV(s). Control Channel (s).
i 4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.
4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel.
i BEAVER VALLEY - UNIT 1 3/4 4-29 Amendment No. 7N,'45,110.
(.next page is 3/4 4-32)
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a.
Source in use (excluding-startup sources 'previously subiected to core flux) - At least once per six months for all sealed sources containing radioactive materials.
1.
With a
half-life greater than 30 days (excluding Hydrogen 3) and 2.
In any form other than gas, Each sealed source shall be b.
Stored sources not in use tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources transferred without a
certificate indicating the_last test date shall be tested prior to being placed into use.
c.
Startup sources - Each sealed startup source shall be tested prior to being subjected to core flux and following repair or maintenance to the source.
4.7.9.1.3 Reports - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days if source leakage tests reveal the presence of > 0.005 microcuries of l
removable contamination.
i i
BEAVER VALLEY - Unit 1 3/4 7-23 Miendment No.110 (next page is 3/4.7-26) l
RADIOACTIVE EFFLUENTS
- DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (S) OF THE PUBLIC from radiciodines and radioactive materials in particulate form (excluding C-14),
and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following:
a.
During any calendar quarter to 1 7.5 mrem to any organ, and b.
During any calendar year to 1 15 mrem to any organ.
APPLICABILITY:
At all times l
ACTION:
a.
With the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half lives greater than 8
- days, in gaseous effluents exceeding any of the above
- limits, prepare and submit to the Commission within 30 days, pursuant to Opecification 6.9.2, a
Special
- Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.
1 b.
The provisions of Specifications 13.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.
Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.
BEAVER VALLEY - UNIT 1 3/4 11-16 Amendment No, 'b(,110 (next page is 3/4 11-18) l
)
l i
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT l
LIMITING CONDITION FOR OPERATION 3.11.2.4 The Gaseous Radwaste Treatment System and the Ventilation i
Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected. doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.
APPLICABILITY:
At all times.
ACTION
.\\
a.
With gaseous waste being discharged without treatment and in excess of the above limits, prepare and ' submit to the Commission i
within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to operational status, and j
S 3.
Summary description of action (s) taken to prevent a
recurrence.
b.
The provisions of specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.
BEAVER VALLEY - UNIT 1 3/4 11-18 Amendment No. 'Fst 110 (next page is 3/4 11-20) l
1 ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.
S. Nuclear Regulatory Commission, Washington, DC
- 20555, with a copy to the Regional
- Office, submitted no later than the 15th of each month i
following the calendar month covered by the report.
6.9.1.7 DELETED oy Amendment No. 84 6.9.1.8 DELETED by Amendment No. 84 6.9.1.9 DELETED by Amendment No. 84
]
ANNUAL RADIOLOGICAL' ENVIRONMENTAL REPORT 8 6.9.1.10 Routine radiological environmental operating reports covering the operatio'n of the unit during the previous calendar year shall be submitted prior to May 1
of each year and will include reporting any deviations not reported under 6.9.2 with respect to the Radiological Effluent Technical Specifications.
6.9.1.11 The annual radiological environmental reports shall include summaries, interpretations, and statistical evaluation of the results
)
of the radiological environmental surveillance activities for the report period, including a
comparison with preoperational studies, operational controls (as appropriate),
and previous environmental surveillance
- reports, and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of the land use censuses required by Specification 3.12.2.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological ' environmental samples taken during the report period.
In the event that some results are not available for inclusion with the
- report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
8' A
single submittal may be made for a multiple unit site.
The submittal should combine these sections that are common to both units.
BEAVER VALLEY - UNIT 1 6-15 Amendment No. '%, M.,110 (next page is 6-20)
m
'4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility l
operation and shall delegate in writing the succession to this lesponsibility during his absence.
6.2 ORGANIZATION CORPORATE l
6.2.1 The corporate organization for facility management and I
technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF i
6.2.2 The facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum
)
shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor, q
c.
At least two licensed Operators shall be in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.
e.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of at least 5 members shall be maintained cn1 site at all times.
The Fire Brigade shall.not include 3 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
g.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; _ senior reactor operators, reactor operators, radiation control technicians, auxiliary operators, meter and control repairman, and all personnel actually performing work on safety related equipment.
/mendment No. )A,110 BEAVER VALLEY - UNIT 1 6-1
4 ADMINISTRATIVE CONTROLS (Continued)
The objective shall be to have operating personnel work a normal 8-hour
- day, 40-hour week. while the plant 'is operating.
- However, in the event-that unforseen problems.
require. substantial amounts of. overtime to be used, or' during extended periods of shutdown. for refueling, major i
maintenance or major plant modifications,- on a temporary _
basis, the-following guidelines shall be-followed:
a.
An individual.should not'be permitted to work.more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding-shift turnover time.
b.
An individual should not be permitted to work more than' 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24' hours'
'd in any '48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any' seven day period, all excluding shift turnover. time..
c.
A break of' at least eight: hours should be allowed between work periods, including shift turnover time..
d.
Except. during' extended, shutdown periods,_ the'use'of' j
overtim'e should be considered' on-an' individual basis and not for the entire staff'on a shift.
Any deviation from the above guidelines shall be authorized
'l by the Plant Manager or predesignated alternate; or: higher-l_
levels of management.
Authorized deviations"to the working hour guidelines shall be. documented and available'for NRC review.
BEAVER VALLEY - UNIT 1 6-la
- Amendment No.??4( 110
=
y t
i l
RR*
ni EAY obG GET iiE ALE t sS NCF ecnI AUA reo MNS it pd I
2l F osn T
an R
- rea C
ti o GS
- PR E
ici LR3 1 D J
nrt AEFR O
Uea RG O
R n r EARC y
s P
l n e NNAE t
i op EAER i
2 t co GML
+
l n
C&
R S
yi V
U U
E
.E tb B
N GNC ii AI I rs NMV un I
ADR cc MAE ep-S Ss e
+R TNE G
DR RRN I A EAI SE GEN EL ALI RC NCA PU ALR N
HNT E
C I
V
)
N O
l I
a RRT i
EAC C
GEU t
R ALR r
O NCT a
AUS HNN P
O
-(
C Y
N 1*
A O
PH I
p TT 1
T CC u NL
- A o
.T T r DR Z
2 HC H G RIG G
OS
~
SHE I
POJ 6 N r
IER I
e EPE DP e G E l S
L Nc EC r R S u CU u-O E N IN g
U V
Q i E U
F T
- ~
L i
D y
A t
R A
l l
O RCf a i P
EIL iyb R
GGO rti AOK t es O
NLT sf n C
AON uao A
HI O dS p DC n
s A
I e
R R
T LS GTN RAE AEO NGC ECC GI I AD ANV MUL NHR BE ACE U
HES F
R S
- T E
N GRO AAI NET ALA HCR UE
.NP R
O R
S TE NG C
AA S
LN O
PAH' E
RYC ETN GIA D.
ALR NT NAU AH AUS R
G HQS EGH A
GN AI E NNG ANA MATLU PO tm3<m# <
m < ' Cd 4,
N n=
<aCatot 20 a L o
,aO r
e f-
l l
l l
l F
L F
F A
R F
A GR C
O l.'
T LA TR T
ARIS NR TC CEE AEO IS TTT T
CORI HO EE f CG IMT R
EL AI E LT HVNE I
TV SDS HUN EGE TO LMR CRA TAR AR PEI PS CDIP D
EAGU TA TW(
TS MAD N
C M
T NS F
NE M
O E
E I
AI C
H H
LV C
S' PE.R N
O ITA 2
Z E
- E I
2 f
. TC N
fCR k
Gl NO GNN A
6 G
NAAT NAAF R
E ILMC If MF TPRA O
R TPRE 1
I S
OR S
OT U
EDFI EDFS T
G TNRD TNR T
I AE AE I
F P
L P
ICAF x
l ER N
m MR N
F O
A F
R CO A
F R
RO R
NS M
F IS M
A V
ES EF AI E
A TI E
T EE PR PT IfE F
I T
CAV R
S 1
TI TF CNV R
S ERR O
I I
IBE F
C IR ME MS fP C
IP E
OP O
lU C
LU C
I f
I D
CU C
AS I
AS S
M I
C I
R
+
TE 1
NG AA LN l
PAM O
S F
E ER E
E LER E
E N
E R
EF CR LCO LC C
A CTO CA NO ANS AN NN C
CNS AN N
I I RS NT I
IAI CAF A
CTE TTT I
r I
I l PV l
TR l
N NC I NV INF Nt N
RNV INF l
t l
A TER REA E
1 TUE NI HNP HNS f O C
ENP CNS f
C NSP NO f
t I D CIU CI l F E
LI U EI l
E I
U IP A
M EAS LA A
L A
S AP M
MM MM M
M EM M
E M
MU m
S m
l G
N f
N A
b f
I TM L
m f
s A
T T
FE O
- S I
AR FS IR R
SR SS PR RO2 IR HO rS S
R NO NR E
TI TN NA OVI I
RD RG I
LA V
g AI I
AI RV y
AI A
I AN g
RN I
I TA REU AR EI I
EU LP CA EP NP PR P0 PM SM AP EE LT AE UE ET ER E
UO O0 O
S C
US NE C
SP 0
A U
N P
U P
N O
N GU NS I
TS g
AN m
G N
RO s
N A
EI I
TM L
PT G
L TR~
T FE O
OA N
e A
r AO FS IR R
R R
I C'
r S
RS IR WO IS S
RE D
T S
ILR A
NN EI1 HO SF NR RR AP E1 AN RR COE T
RG S
II ORT I
SN EM-E1
)
UIA EI I
RV g
AN g
A LA C
g AI PE E
LA DTC I
I OfrN Ng AI RPN AR EI RR CR U
WD OR CR q
I AUU EE LT AE UE N
DR O
UE IoA OAI G
DCM C
D AC L
CU UR LO O
R0 F
.O E
C C
I C
US N. P m
RE R
U H
T U
N N
O N
S I'
s nmim"<NQ<,E~H" n'W g(agg3*r y ay D
o t
c w
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
SINGLE UNIT FACILITY
! !!!!!!!!!i!!!!! !iiiiiiii!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!ii!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!!i!I' hij LICENSE CATEGORY APPLICABLE MODES QUALIFICATIONS 1, 2, 3 and 4 5 and 6 I
SRO*
2 1**
RO 2
1 Non-Licensed Auxiliary Operator 2
1 shift Technical Advisor 1(a)
None j
Required Includes the Licensed Senior Reactor Operator serving as the Shift Supervisor.
Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel
- Handling, supervising CORE ALTERATIONS.
Shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
(a)
A single qualified person can be used to satsify the requirements of the STA position for both units.
BEAVER VALLEY - UNIT 1 6-4 Amendment No. )S,110 t
1
' ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiological Control Manager l
who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative l
who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A Training program for the Emergency Squad shall be maintained under the direction of the Nuclear Training Manager and shall meet or l
exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)
FUNCTION 1
6.5.1.1 The OSC shall function to advise the Plant Manager on all matters related to nuclear safety and shall provide review capability in the areas of:
a.
nuclear power plant operations b.
radiological safety c.
maintenance d.
nuclear engineering e.
nuclear power plant testing i
f.
technical advisory engineering g.
chemistry h.
quality control 1.
instrumentation and control 6.5.1.2 The Plant Safety Review Director is the OSC Chairman and shall appoint all members of the OSC.
The n:embership shall consist of a
minimum of one individual from each of the areas designated in 6.5.1.1.
OSC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.
The nuclear power plant opeiutions individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.
BEAVER VALLEY - UNIT 1 6-5 Amendment lR,110
[
ADMINISTRATIVELCONTROLS-ALTERNATES 6.5.1.3 All' alternate members shall be appointed in writing by the OSC Chairman to serve on a temporary basis;.however, no more than two alternates shall participate-as voting members in OSC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate.
i QUORUM i
6.5.1.5 A
quorum of the OSC shall consist of the Chairman or his designated alternate and at least one half of the. members including l alternates.
i i
RESPONSIBILITIES 6.5.1.6 The OSC shall be responsible for:
a.
Review of 1) all procedures required by Specification.618
]
~
and-changes. of intent
- thereto, 2) any.other proposed procedures or changes thereto as determined by;the plant
'l Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect j
nuclear safety.
.j c.
Review of all proposed changes'.to. thej Technical l
j Specifications.
j d.
Review of all proposed changes or modifications to plant 4
systems or equipment that affect nuclear-safety.
j e.
Investigation of all violations.
of. the. Technical i
Specifications including the' preparation and forwarding:
1 of reports covering evaluation and recommendations to prevent recurrence
'to the Senior Manager,. Nuclear i
Operations: and to the Chairman of the Offsite Review.
Committee.
l f.
Review of all REPORTABLE EVENTS.
g.
. Review :of facility operations to detect potentialisafety' d
hazards.
I h.
Performance.
of special1 creviews,-
investigations _ or of the Offsite Review Committee.
analyses and reports thereon as requested by the. Chairman
~
l 4
BEAVER VALLEY - UNIT 1 6-6
. Amendment No. h,.110 l
I
a
. ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The OSC shall:
1 a.
Recommend to the Plant Manager written approval or l
disapprovt.1 of items considered under 6.5.1.6(a) through1(d) above..
~
Render determinations in writing with regard to whether or b'.
not each item considered under 6.5.1.6(a) through.(e) abovel I
constitutes an unreviewed safety question.
c.
Provide written notification within~24 hours to the Senior Manager Nuclear Operations and~the Offsite Review Committee of. disagreement between the OSC -and the Plant Manager;
'I
- however, the Plant Manager shall have responsibility for.
resolution.of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The OSC shall maintain written minutes'of=each meeting and-
)
copies. shall be provided to the-Senior Manager Nuclear Operations and1-l Chairman of the Offsite Review Committee..
6.5.2 OFFSITE REVIEW COMMITTEE (ORC)
FUNCTION
]
6.5.2.1 The ORC shall function to provide independent review and audit of designated activities in the areas of:'
q j
a.
nuclear power plant operations b.
nuclear engineering j
c.
chemistry and radiochemistry i
d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical-engineering j
1 h.
quality assurance practices j
1 Amendment'No. )R,110-BEAVER VALLEY - UNIT 1 6-7=
t]
'l
I l
ADMINISTRATIVE CONTROLS I
COMPOSITION 6.5.2.2 The chairman and all members of the ORC shall be appointed by the Senior Vice President, Nuclear Group.
The membership shall minimum of five individuals who collectively possess a consist of a
broad based level of experience and competence enabling the committee to review and audit those activities designated in 6.5.2.1 above and to recognize when it is necessary to obtain technical advice and counsel.
An individual may possess expertise in more than one The collective competence of the committee will be speciality area.
maintained as changes to the membership are made.
I ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time.
j CONSULTANTS 6.5.2.4 consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC.
Amendment No. ll, 110 BEAVER VALLEY - UNIT 1 6-8
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 The ORC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
QUORUM 6.5.2.6 A
quorum o'f ORC shall consist of the Chairman or his, designated alternate and at least 4 members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the facility.
REVIEW 6.5.2.7 The ORC shall review:
^
a.
Tae safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10
- CFR, to verify that such actions did not constitute an unreviewed safety question, b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section-50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or licenses.
e.
Violations of applicable
- statutes, codes, regulations, orders, Technical Specifications, license requirements, or-of internal procedures or instructions having nuclear safety significance.
f.
Significant operation abnormalities or deviations from normal and j
expected performance of plant equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS
~
h.
All recognized indications of_an unanticipated deficiency in seme aspect of design or operation of-safety-related structures, systems, or components.
i.
Reports and meeting minutes of the OSC.
j.
The results of the Radiological Environmental Monitoring _ Program annualf report provided in accordance with Specification 6.9.1.10, prior to submittal.
-BEAVER VALLEY UNIT l' 6-9 Amendment No. it 1110 H
ADMINISTRATIVE CONTROLS.
AUDITS (Continued) 6.5.2.9 The ORC shall report to and advise the Senior Vice
]
Presloent, Nuclear Group on those areas of responsibility specified j
in Section 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated by the following:
a.
Minutes of each ORC meeting shall be prepared for and approved by the ORC Chairman or Vice-Chairman within 14 days following each l q
meeting.
j i
of reviews encompassed by Section 6.5.2.7 above, shall be I b.
Reports documented in'the ORC meeting minutes.
3 b
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be.
j forwarded to the Senior Vice President, Nuclear Group and to the j
management positions responsible for the areas audited within 30 1
days after completion of the audit.
6.6 REPORTABLE EVENT ACTION q
1 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
'I a.
The Commission shall be notified in accordance~with 10.CFR 50.7c and/or a
report be submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the OSC, and results of this review shall be submitted to the ORC.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following. actions shall be taken in the. event a Safety.
Limit is ville.ted:
a.
The facility shall be placed in at least HOT STANDBY within one (1) hour.
b.
The Safety Limit violation shall be. reported to the Commission, the Senior Manager,,
Nuclear Operations and to the ORC within-24 l hours.
BEAVER VALLEY - UNIT 1
/
6-11
/Wendment No. it,110 L
.,v.
.i/
t w
l tr _
ADMINISTRATIVE CONTROLS a
SAFETY LIMIT VIOLATION (Continued)
]
i c.
A Safety Limit Violation Report shall be prepared.
The report i
shall be reviewed by the On-Site Safety Committee (OSC)..
This J
report' shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent 1
recurrence.
d.
The Safety Limit Violation Report chall be submitted to the Commission, the ORC and the Senior Manager, Nuclear Operations l
within 14 days of the violation.
i 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended-in Appendix "A"
of Regulatory Guide 1.33, Revision 2, February 1978.
l b.
Refueling operatien,.
c.
Surveillance and test activities of safety related equipment, d.
Security Plan implementation.
e.
Emergency Plan-implementation.
f.
Fire Protection Program implementation.
I g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL. implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above and changes of-intent thereto, shall be reviewed by the OSC and approved by the Plant
- Manager, predesignated alternate or a predesignated Manager to whom the-Plant Manager has. assigned in writing the responsibility for review and approval of specific subjects considered by. the: committee, as applicable.
Changes to procedures and administrative policies of_ 6.8.1 above that do'not-receive 10SC
- review, such.
as correcting typographical-e r r-o r s,. reformatting procedures and-other changes not affecting the purpose for which the procedure is performed. shall receive an independent review by a qualified
-individual and approved by.
designated manager or director.
BEAVER' VALLEY - UNIT 1 6-12 Miendment No. b% 110
1 ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered, b.
The change is approved by two (2) members of the plant management
- staff, at least one (1) of whom hold a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the OSC and approved by the Plant Manager within 14 days of implementation.
l 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
k STARTUP REPORTS 6.9.1.1 A
summary report of plant startup and power escalation f
testing will be submitted following (1) receipt of an operating
- license, (2) amendment to the license involving a planned increase in
?
power
- level, (3) installation of fuel that has a different design or L
has been manufactured by a
different fuel
- supplier, and (4)
)
modifications that may have significantly altered the
- nuclear, thermal, or hydraulic performance of the plant.
j 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a
description of the I
measured values of the operating conditions or characteristics obtained during.the test program and a comparison of these values with ' design predictions and specifications.
Any_ corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details requested in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test
- program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e.,
initial criticality, completion of startup test program, and
~~6o~mencement
'o f '
commericial power operation),
resumption ~ or m
supplementary reports shall be submitted at least every three months until all three events have been completed.
BEAVER VALLEY - UNIT 1 6-13 Amendment No.14, Ts5,110
's ADMINISTRATIVE CONTROLS 6.16.3 Background of what constitutes " MAJOR CHANGES" to radioactive l
waste systems (liquid, gasecas, and solid).
A.
Background
1.
10 CFR Part 50, Section 50.34a(a) requires that each application to construct a nuclear power reactor provide a description of the equipment installed to maintain control over radioactive material in gaseous and liquid effluents produced' during normal reactor operations including 1
I operational occurrences.
i 2.
10 CFR Part 50, Section 50.34a(b)(2) requires that each application to-construct a nuclear power reactor provide an estimate of the quantity. of radionuclides expected to be released annually to unrestricted areas in liquid and gaseous effluents produced during normal reactor operation.-
3.
10 CFR Part 50, Section 50.34a(3) requires that each I
application to construct a nuclear power reactor provide a description of the provisions for packaging, storage and f
shipment offsite of solid waste containing radioactive materials resulting from treatment of gaseous and liquid effluents and from other sources.
4.
10- CFR Part 50, Section 50.34a(3)(c) requires that each I
application to operate a nuclear power reactor shall include (1) a description of the equipment and procedures for the control of gaseous and liquid effluents and for the maintenance and use of equipment installed in radioactive i
waste systems ahd (2) a revised estimate of the information i
required in (b)(2) if the expected releases and expecures
{
differ significantly from the estimate. submitted in the i
application for a construction permit.
i 5.
The Regulatory staff's Safety Evaluation Report.and amendments thereto issued prior to-the issuance of an operating license contains a description of the radioactive waste systems installed in the nuclear power reactor and a detailed evaluation (including estimated releases of radioactive materials in liquid and. gaseous waste and quantities of solid waste produced from_ normal operation, estimated annual. maximum exposures to an individual'in the unrestricted area and estimated exposures to the general population) which shows the capability of these systems to meet the appropriate regulations.
BEAVER VALLEY - UNIT 1 6-30 Amendment No.14 110
ADMINISTRATIVE CONTROLS 6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Senior Manager Nuclear Operations delegates the responsibility for the Radiological Environmental Monitoring Program to the Radiological Control Manager (Figure 6.2-1) or his designated alternate.
The Radiological Control Manager is responsible for administering the l
offsite Radiological Environmental Monitoring Program.
He shall determine that the sampling program is being implemented as described to verify that the environment is. adequately protected under existing procedures.
He shall also have the responsibility for establishing, implementing, maintaining and approving offsite environmental program sampling, analyses and calibration procedures.
1 BEAVER VALLEY - UNIT 1 6-31 Amendment No. 66,110 l
m o
3/4.11 RADIOACTIVE EFFLUENTS BASES Revision 1,
- October, 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
This specification applies to the release of liquid effluents from Beaver Valley Power
- Station, Unit No.
1.
For units with shared radwaste treatment
- systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
i 3/4.11.1.3 LIQUID WASTE TREATMENT i
The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion-60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to i
The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a
suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,
10 CFR Part 50, for liquid effluents.
This specification applies to Beaver Valley Power i
Station, Unit No.
1.
3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column l
2, at the nearest portable water supply and the nearest surface water supply in an unrestricted area.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 BEAVER VALLEY - UNIT 1 B 3/4 11-2 Amendment No.14,110