ML20072T899
| ML20072T899 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/08/1994 |
| From: | Thadani M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072T902 | List: |
| References | |
| NUDOCS 9409160025 | |
| Download: ML20072T899 (29) | |
Text
--.
i n etcy g*
2 S
UNITED STATES i#
2!
NUCLEAR REGULATORY COMMISSION g
,/
WASHINGTON, D.C. 20555-0001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
157 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated May 25, 1994, 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; B.
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: (i) 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 set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9409160025 940908 PDR ADOCK 05000272 P
. (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 157,-are hereby incorporated in the
-license The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7A cO2%%
Mohan C. Thadani, Acting Director-L Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear. Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
September 8, 1994 t
l l
l
i i
ATTACHMENT TO LICENSE AMENDMENT NO. 157 i
FACILITY OPERATING LICENSE NO. DPR-70 i
DOCKET NO. 50-272 j
Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 3-36 3/4 3-36 3/4 3-36a 3/4 3-36a l
l 3/4 3-38 3/4 3-38 3/4 3-38a 3/4 3-38a l
3/4 3-59 3/4.3-59 3/4 3-62 3/4 3-62 3/4 3-65 3/4 3-65 3/4 3-68 3/4 3-68 B 3/4 3-1 B 3/4 3-1 i
B 3/4 3-2 B 3/4 3-2 l
B 3/4 3-3 8 3/4 3-3 B 3/4 3-3a
i a
i TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CilANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.
AREA MONITORS s15 mR/hr 10'l-10 mR/hr 19 4
a.
Fuel Storage Area 1
l 3
7
- b. Containment Area 2
1,2,3&4 510 R/hr 1-10 R/hr 23 l
2.
PROCESS MONITORS a.
Containment
- 1) Gaseous Activity 1
6 a) Purge & Pressure -
1#
6 s2x background 10 -10 cpm 22 & 23 Vacuum Relief and Isolation 1,2,3,4&5 per Specification l
3.3.3.9 1
6 b) RCS Leakage 1
1,2,3&4 N/A 10 -10 cpm 20 Detection
- 2) Air Particulate Activity 1
6 a) Purge & Pressure -
1 6
s2x background 10 -10 cpm 22 Vacuum Relief l
Isolation 1
6 b) RCS Leakage 1
1,2,3&4 N/A 10 -10 cpm 20 Detection l
With fuel in the storage pool or building.
The plant vent noble gas monitor may also function in this capacity when the purge / pressure-vacuum relief isolation valves are open.
SALEM UNIT 1 3/4 3-36 Amendment No.157
TABLE 3.3-6 (Continued)
RADIATION MONITORING INSTRUMENTATION MINIMUM CilANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 2.
PROCESS MONITORS
- b. Noble Gas Effluent Monitors
- 1) Medium Range Auxiliary 1
1,2,3&4 s3.0x10-2pCi/cm3 10-3-10 pCi/cm 23 l
3 Building Exhaust System (Alarm only) l (Plant Vent) 2 3
10-1-10 pCi/cm 23 S
3
- 2) High Range Auxiliary 1
1,2,3&4 s1 0x10 pCi/cm Building Exhaust System (Alarm only) g t
(Plant Vent) 4
- 3) Main Steamline 1/
1,2,3&4 s10 mR/hr 1-10 mR/hr 23 Discharge (Safety MS Line (Alarm only)
Valves and Atmospheric Steam Dumps 4
6
- 4) Condenser Exhaust 1
1,2,3&4 s1.27x10 cpm 1-10 cpm 23 System (Alarm only) l SALEM UNIT 1 3/4 3-36a Amendment No.157
. ~
TABLE '. 3 3 RADIATION MONITOR.ING INSTRUMENTATION SURVEILLAfiCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED 1.
AREA MONITORS l
a.
Fuel Storage Area S
M R
Q b.
Containment Area S
M R
Q 1,
2, 3 &4 l
r 2.
PROCESS MONITORS a.
Containment Monitors 1)
Gaseous Activity a)
Purge & Pressure S
M R
Q 1,
2, 3,
4, 5 & 6 Vacuum Relief Isolation b)
RCS Leakage S
M R
Q 1,
2, 3&4 Detection l
2)
Air Particulate Activity a)
Purge & Pressure-S M
R O
1, 2,
3, 4,
& 6 Vacuum Relief l
Isolation b)
RCS Leakage S
M R
Q 1,
2, 3&4 Detection With fuel in the storage pool or building.
SALEM UNIT 1 3/4 3-38 Amendment No.157
TABLE 4.3-3 (Continued)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED 2.
PROCESS MONITORS b.
Noble Gas Effluent Monitors 1)
Medium Range Auxiliary S
M R
Q 1,
2, 3&4 Building Exhaust System (Plant Vent) l 2)
High Range Auxiliary S
M R
Q 1,
2, 3&4 Building Exhaust System (Plant Vent) 3)
Main Steamline S
M R
Q 1,
2, 3&4 Discharge (Salety Valves and Atmospheric Dumps) l l
4)
Condenser Exh. Sys.
S M
R Q
1, 2,
3 &4 SALEM UNIT 1 3/4 3-38a Amendment No.157 r
m
TABLE 3.3-12 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line 1
26 b.
Steam Generator Blowdown Line 4
27 2.
GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Containment Fan Coolers - Service Water Line 5
28 Discharge 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
29 b.
Steam Generator Blowdown Line 4
29 4.
TANK LEVEL INDICATING DEVICES a.
Temporary Outside Storage Tanks as Required 1
30 SALEM UNIT 1 3/4 3-59 Amendment No.
157
O TABLE 4.3-I2 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line D
P#
R(3)
Q(1) l b.
Steam Generator Blowdown Line D
M R(3)
Q(I) l 2.
GROSS RADICAcrIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Containment Fan Coolers - Service Water Line D
M R(3)
Q(2)
Discharge l
3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D(4)
N.A.
R N.A.
b.
Steam Generator Blowdown Line D (4 )
N.A.
R N.A.
4.
TANK LEVEL INDICATING DEVICES **
Temporary Outside Storage Tanks as Required D*
N.A.
R Q
a.
SALEM UNIT I 3/4 3-62 Amendment No.157
TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
WASTE GAS HOLDUP SYSTEM a.
Noble Gas Activity Monitor - Providing 1
31 g
Alarm and Automatic Termination of Release I
b.
Oxygen Monitor 1
35 2.
CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF a.
Noble Gas Activity Monitor - Providing 1
34 Alarm and Automatic Tennination of Release 3.
PLANT VENT llEADER SYSTEM #
l a.
Noble Gas Activity Monitor 1
33 b.
Iodine Sunpler 1
36 c.
Particulate Sampler 1
36 d.
Flow Rate Monitor 1
32 e.
Sampler Flow Rate Monitor 1
32 The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:
(a)
Condenser Air Removal System (b)
Auxiliary Building Ventilation System (c)
Fuel Handling Building Ventilation System (d)
Radwaste Area Ventilation System (e)
Containment Purges Action item #34 applies to the purging of the containment only.
SALEM UNIT 1 3/4 3-65 Amendment No.157
+
-- _-___ = _ _ _ _ _ _ _ _ _ _ _ _ _ _, _ _ _ _ _ _ _, _ _ _ _ _ _ _ _ _ _ _ _
TABLE 4.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES I'* WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT OPERABLE CllECK CALIBRATION TEST REQUIRED 1.
WASTE GAS HOLDUP SYSTEM a.
Noble Gas Activity Monitor - Providing P
P R(3)
Q(1) l Alarm and Automatic Tennination of Release b.
Oxygen Monitor D
N.A.
Q(4)
M 2.
CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF a.
Noble Gas Activity Monitor - Providing P
P R(3)
Q(1)
Alarm and Automatic Tennination of Release 3.
PLANT VENT HEADER SYSTEM #
a.
Noble Gas Activity Monitor D
M R(3)
Q(2) l b
Iodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
d.A.
N.A.
i d.
Flow Rate Monitor D
N.A.
R N.A.
e.
Sampler Flow Rate Monitor W
N.A.
R N.A.
The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:
(a)
Condenser Air Removal System (b)
Auxiliary Building Ventilation System (c)
Fuel Handling Building Ventilation System (d)
Radwaste Area Ventilation System (e)
Containment Purges SALEM - UNIT 1 3/4 3-68 Amendment No. 157
~. -. -- -.
~.
(
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3 /4. 3. 2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESP)
]
INSTRUMENTATION l
1 The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combinaticn thereof exceeds its setpoint, 2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out of service J
for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation and, 3) sufficient system functions capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The l
integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum _
1 j
fre'uencies are sufficient to demonstrate this capability. Specified q
l surveillance intervals and surveillance and maintenance outage times have been j
j determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and Supplements to that report.
Surveillance intervals and out of service times were determined based on maintaining an j
appropriate level of reliability of the Reactor Protection System and j
l Engineered Safety Features instrumentation.
1 l
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.
l No credit was taken in the analyses for those channels with response times indicated as not applicable.
(
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, ensite or offsite test measurements or 2) i utilizing replacement sensors with certified response times.
{
l 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION
)
l l
The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated i
when the radiation level trip setpoint is exceeded.
I i
SALEM - UNIT 1 B 3/4 3-1 Amendment No.157 J
I
INSTRUMENTATION BASES 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION (Continued)
CROSS REFERENCE - TABLES 3.3-6 and 4.3-3 Func Rad Mon Rad Mon Unit Number fjanction Area Monitors la 1RS/1R9 Fuel Storage Area lb 1R44 Containment Area Process Monitogg 2a1 1R12A Containment Purge & Pressure / Vacuum Relief Gaseous Activity 1R41C Plant Vent Noble Gas Monitor may substitute for 1R12A when the Purge & Pressure Vacuum Relief Valves are open.
2a2 1R11A Containment Purge & Pressure / Vacuum Relief Air Particulate Activity 2b1 1R45B Medium Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent l
2b2 1R45C High Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b3 1R46 Main Steamline Discharge (Safety Valves and Atmospheric Dump Valves) Noble Gas Effluent 2b4 1R15 Condenser Exhaust System Noble Gas Effluent 3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event l
and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
SALEM - UNIT 1 B 3/4 3-2 Amendment No.157 I
I
INSTRUMENTATION BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 THIS SECTION DELETED l
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that i
sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the Recommendations of Regulatory Guide 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975.
3/4.3.3.8 RADICACTIb LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.
CROSS REFERENCE - TABLES 3.3-12 and 4.3-12 Func. Rad Mon Rad Mon Unit Number Function la 1 RIB Liquid Radwaste Effluent Line Gross Activity lb
- 1R19A, B,
Steam Generator Blowdown Line Gross Activity C,
and D l
2a
- 1R13A, B,
Containment Fan Coil Unit - Service Water Line Gross I
C, D,
and E Activity SALEM - UNIT 1 B 3/4 3-3 Amendment No.157 l
l
i l
1 INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation l
also includes provisions for monitoring (and controlling) the concentrations l
of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
CROSS REFERENCE - TABLES 3.3-13 and 4.3-13 l
t l
Func Rad Mon Rad Mon Enit Number Function la 1R41C Waste Gas Holdup System - Noble Gas Activity 2a 1R12A or Containment Purge and Pressure-Vacuum Relief Noble Gas 1R41C Activity 3a 1R16 or Plant Vent Header Noble Gas Activity l
1R41C SALEM - UNIT 1 B 3/4 3-3a Amendment No. 157
I l
/o are%,
3 c
4 j
7 i S
UNITED STATES i
5:
NUCLEAR REGULATORY COMMISSION
~
\\.v+...,/
WASHINGTON, D.C. 2055MKXH j
f PUBLIC SERVICE ELECTRIC & GAS COMPANY i
i PHILADELPHIA ELECTRIC COMPANY l
j DELMARVA POWER AND LIGHT COMPANY l
ATLANTIC CITY ELECTRIC COMPANY j
DOCKET NO. 50-311 j
SALEM NUCLEAR GENERATING STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.138 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found
]
that:
i A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light i
Company and Atlantic City Electric Company (the licensees) dated j
May 25, 1994, complies with the standards and requirements of the j
Atomic Energy Act of 1954, as amended (the Act), and the Commission's j
rules and regulations set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the j
Commission; i
C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted wit 30ut endangering the health and 4
i safety of the public, and (ii) that sud ::tivities will be conducted j
in compliance with the Commission's regulations set forth in 10 CFR j
Chapter I; j
D.
The issuance of this amendment will not be inimical to the common t
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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$ blaLL (
C Mohan C. Thadani, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 8, 1994 i
i
ATTACHMENT TO LICENSE AMENDMENT NO. 138 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 3-39 3/4 3-39 l
l 3/4 3-39a 3/4 3-39a j
3/4 3-41 3/4 3-41 3/4 3-41a 3/4 3-41a 3/4 3-54 3/4 3-54 3/4 3-57 3/4 3-57 3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63 B 3/4 3-2 8 3/4 3-2 i
B 3/4 3-3 B 3/4 3-3 i
B 3/4 3-3a
TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.
AREA MONITORS s15 mR/hr 10-1-10 mR/hr 23 4
a.
Fuel Storage Area 1
l 3
7 b.
Containmerit Area 2
1,2,3&4 s10 R/hr 1-10 R/hr 26 2.
PROCESS MONITORS a.
Containment 1)
Gaseous Activity 1
6 a) Purge & Pressure -
1#
6 s2x background 10 -10 cpm 26 Vacuum Relief and Isolation 1,2,3,4&5 per Specification 3.3.3.9 1
6 b) RCS Leakage 1
1,2,3&4 N/A 10 -10 cpm 24 Detection 2)
Air Particulate Activity 1
6 a)
Purge & Pressure -
1 6
s2x background 10 -10 cpm 25 Vacuum Relief Isolation 1
6 b)
RCS Leakage 1-1,2,3&4 N/A 10 -10 cpm 24 f
Detection With fuel in the storage pool or building.
The plant vent noble gas monitor may also function in this capacity when the purge / pressure-vacuum l
relief isolation valves are open.
SALEM UNIT 2 3/4 3-39 Amendment No. 138
l TABLE 3.3-6 (Continued)
RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 2.
PROCESS MONITORS b.
Noble Gas Effluent Monitors l
3 3
10-3-10 pCi/cm 26 1)
Medium Range Auxiliary 1
1,2,3&4 s3.0x10-2pCi/cm Building Exhaust System (Alarm only)
(Plant Vent) 5 3
2 3
10-1-10 pCi/cm 26 2)
High Range Auxiliary 1
1,2,3&4 s1.0x10 pCi/cm Building Exhaust System (Alarm only) l (Plant Vent) i 4
3)
Main Steamline 1/
1,2,3&4 10 mR/hr 1-10 mR/hr 26 Discharge (Safety MS Line (Alarm only)
Valves and Atmospheric Steam Dumpcl 4
6 4)
Condenser Fxhaust 1
1,2,3&4 s7.12x10 cpm 1-10 cpm 26 l
System (Alarm onl2)
SALEM - UNIT 2 3/4 3-39a Amendment No.138
=E
.. m.
m
l TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE l
INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED 1.
AREA MONITORS l
a.
Fuel Storage Area S
M R
Q l
b.
Containment Area S
M R
Q 1,
2, 3 &4 2.
PROCESS MONITORS a.
Containment Monitors 1)
Gaseous Activity a)
Purge & Pressura S
M R
Q 1,
2, 3,
4, 5 & 6 Vacuum Relief Isolation b)
RCS Leakage S
M R
Q 1,
2, 3 & 4 l
Detection
- 2) Air Particulate Activity a)
Purge & Pressure-S M
R Q
1, 2,
3, 4,
& 6 Vacuum Relief Isolation b)
RCS I4akage S
M R
Q 1,
2, 3 & 4 Detection With fuel in the storage pool or building.
SALEM UNIT 2 3/4 3-41 Amendment No. 138
..m..---
m
TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED 2.
PROCESS MONITORS b.
Noble Gas Effluent Monitors 1)
Medium Range Auxiliary S
M R
Q 1,
2, 3&4 Building Exhaust System (Plant Vent) 2)
High Range Auxiliary S
M R
Q 1,
2, 3 &4 Building Exhaust System l
(Plant Vent) 3)
Main Steamline S
M R
Q 1,
2, 3 & 4 Discharge (Safety valves and Atmospheric l
Dumps) 4)
Condenser Exh.
S M
R Q
1, 2,
3&4 Sys.
SALEM UNIT 2 3/4 3-41a Amendment No.138
...m..
TABLE 3.3-12 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE l
a.
Liquid Radwaste Effluent Line 1
26 b.
Steam Generator Blowdown Line 4
27 2.
GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Containment Fan Coolers - Service Water Line 3
28 Discharge b.
Chemical Waste Basin Line 1
31 l
3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
29 b.
Steam Generator Blowdown Line 4
29 4.
TANK LEVEL INDICATING DEVICES a.
Temporary Outside Storage Tanks as Required 1
30 F
SALEM UNIT 2 3/4 3-54 Amendment No. 138
TABLE 4.3-12 i
RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMEffrATION l
SURVEILLANCE REOUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE l
a.
Liquid Radwaste Effluent Line D
P#
R(3)
Q (1) l b.
Steam Generator Blowdown Line D
M R(3)
Q(1) l 2.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Containment Fan Coolers - Service Water Line D
M R (3)
Q(2)
Discharge b.
Chemical Waste Basin Line D
M R(3)
Q(2) l 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D (4 )
N.A R
N.A.
b.
Steam Generator Blowdown Line D (4 )
N.A.
R N.A.
4.
TANK LEVEL INDICATING DEVICES **
a.
Temporary Outside Storage Tanks as Required D*
N.A.
R Q
l SALEM - UNIT 2 3/4 3-57 Amendment No.138 o
TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
WASTE GAS HOLDUP SYSTEM a.
Noble Gas Activity Monitor - Providing 1
31 Alarm and Automatic Termination of Release b.
Oxygen Monitor 1
35 1
2.
CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF a.
Noble Gas Activity Monitor - Providing 1
34 Alarm and Automatic Termination of Release 3.
PLANT VENT HEADER SYSTEM #
a.
Noble Gas Activity Monitor 1
33 b.
Iodine Sampler 1
36 c.
Particulate Sampler 1
36 d.
Flow Rate Monitor 1
32 e.
Sampler Flow Rate Monitor 1
32 The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:
(a)
Condenser Air Removal System (b) Auxiliary Building Ventilation System (c)
Fuel Handling Building Ventilation System
.' d )
Radwaste Area Ventilation System (e)
Containment Purges Action item #34 applies to the purging of the containment only.
SALEM UNIT 2 3/4 3-60 Amendment No.138 9
o
l TABLE 4.3-13
,R_ADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT OPERABLE CHECK CALIBRATION TEST REQUIRED 1.
WASTE GAS HOISUP SYSTEM a.
Noble Gas Activity Monitor - Providing P
P R(3)
Q(1) g t
Alarm and Automatic Termination of Release l
b.
Oxygen Monitor D
N.A.
Q(4)
M 2.
CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF a.
Noble Gas Activity Monitor - Providing P
P R(3)
Q(1)
Alarm and Automatic Termination of Release 3.
PLANT VENT HEADER SYSTEM #
l a.
Noble Gas Activity Monitor D
M R (3)
Q(2) b.
Iodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
R N.A.
e.
Sampler Flow Rate Monitor W
N.A.
R N.A.
The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:
(a)
Condenser Air Removal System (b) Auxiliary Building Ventilation System i
(c)
Fuel Handling Building Ventilation System (d)
Radwaste Area Ventilation System (e)
Containment Purges SALEM - UNIT 2 3/4 3-63 i
INSTRUMENTATION BASES 3 /4. 3. 3.1 RADIATION MONITORING INSTRUMENTATION (Continued)
CROSS REFERENCE - TABLES 3.3-6 and 4.3-3
)
Func Rad Mon Rad Mon Unit Fumber Function Area Monitors la 2R5/2R9 Fuel Storage Area lb 2R44 Containment Area Process Monitors 2a1 2R12A Containment Purge & Pressure / Vacuum Relief Gaseous Activity 2R11C Plant Vent Noble Gas Monitor may substitute for 2R12A when the Purge & Pressure Vacuum Relief Valves are open.
2a2 2R11A Containment Purge & Pressure / Vacuum Relief Air Particulate Activity 2b1 2R45B Medium Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent 2b2 2R45C High Range Auxiliary Building Exhaust System (Plant Vent)
Noble Gas Effluent l
2b3 2R46 Main Steamline Discharge (Safety Valves and Atmospheric Dump Valves) Noble Gas Effluent 2b4 2R15 Condenser Exhaust System Noble Gas Effluent i
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.
N For the purpose of measuring Fg(Z) or F 3, a full incore flux map is used.
Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in I
recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT l
POWER TILT RATIO when one Power Range Channel is inoperable, t
3/4.3.3.3 SEISMIC INSTRUMENTATION NOT REQUIRED 3 /4. 3. 3. 4 METEOROLOGICAL INSTRUMENTATION NOT REQUIRED SALEM UNIT 2 B 3/4 3-2 Amendment No. 138
(
. = _ - -.
INSTRUMENTATION BASES 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.
3/4.3.3.6 THIS SECTION DELETED 3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION l
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the Recommendations of Regulatory Guide 1.97,
" Instrumentation for Light-htter-Cooled Nuclear Power Plants to Assess Plant Conditions During and FollowinJ an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Tas) Force Status Report and Short-Term Recommendations."
3 /4. 3. 3. 8 '&DICACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION I
The radioactive liquid effluent instrumentation is provided to monitor and l
control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior tc exceeding the limits of 10 CFR Part 20. The OPERABILITY and use j
of this instrumentation is consistent with the requirements of General Design 1
Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank I
level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive l
materials to UNRESTRICTED AREAS CROSS REFERENCE - TABLES 3.3-12 and 4.3-12 Func. Rad Mon Rad Mon Unit Number Function la 2R18 Liquid Radwaste Effluent Line Gross Activity lb 2R19A,B, Steam Generator Blowdown Line Gross Activity C and D 2a
- 2R13A, Containment Fan Coil Unit - Service Water Line Gross B and C Activity 2b R37 Chemical Waste Basin Line Gross Activity SALEM - UNIT 2 B 3/4 3-3 Amendment No.138 l
i l
\\
INSTRUMENTATION BASES 3 /4. 3. 3. 9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as cpplicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation l
also includes provisions for monitoring (and controlling) the concentratior.s l
of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
CRCSS REFERENCE - TABLES 3.3-13 and 4.3-13 l
Func Rad Mon Rad Mon Unit Number Function l
l la 2R41C Waste Gas Holdup System - Noble Gas Activity j
2a 2R12A or Containment Purge and Pressure-Vacuum Relief Noble Gas 2R41C Activity 3a 2R16 or Plant Vent Header Noble Gas Activity 2R41C l
3/4.3.4 TURBINE OVERSPEED PROTECTION i
l l
This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine l
excessive overspeed is required since excessive overspeed of the turbine could l
generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.
The overspeed protection instrumentation consists of five solenoid valves and one trip mechanism which can be grouped into three independent systems. These I
are:
1.
Mechanical Overspeed Trip The mechanical overspeed trip valve will dump the autostop oil.
The dump of the autostop oil will open the oil operated interface valve to dump the emergency electro-hydraulic trip fluid.
1 I
Salem Unit 2 B 3/4 3-3a Amendment No.138 1
r s