ML20092N175
| ML20092N175 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/28/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092N179 | List: |
| References | |
| NUDOCS 9510050057 | |
| Download: ML20092N175 (14) | |
Text
putouq pa' UNITED STATES g
j NUCLEAR REGULATORY COMMISSION R
WASHINGTON, D.C. 20066-0001 o
'S9.....,o I
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. NPF-2 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 17, 1994, as supplemented June 15 and August 11, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; E
D.
The issuance of this license amendment will not be inimical to the comon 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.
NPF-2 is hereby amended to read as follows:
9510050057 950928 ADOCK0500g8 DR
i (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
16, are hereby incorporated in the license.
Southern Nuclear 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 30 days of issuance.
FOR TH NUCLEAR REGULATORY COMMISSION l
rbert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 28, 1995 i
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t
ATTACHMENT TO LICENSE AMENDMENT NO.116 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
i Remove Paaes Insert Paaes 3/4 3-1 3/4 3-1 3/4 3-15 3/4 3-15 8 3/4 3-2 8 3/4 3-2 B 3/4 3-2a l
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INSTRUMENTATION BASES l
EEACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM l
INSTRUMENTATION (Continued)
The verification of response time at the specified frequencies provides l
assurance that the reactor trip and ESF actuation associated with each channel l
is completed within the time limit assumed in the accident analyses.
Response
L time limits for the Reactor Trip System and Engineered Safety Features j
Actuation system are maintained in Tables 7.2-5 and 7.3-16 of the Farley FSAR, l reopectively. No credit was taken in the analyses for those channels with j
response times indicated as not applicable.
' Response time may be verified by actual tests in any series of sequential, overlapping or. total channel measurements, or by summation of l
allocated sensor response times with actual tests on the remainder of the channel in any series of sequential or overlapping measurements. Allocations l
for specific pressure and differential pressure sensor response times may be obtained from (1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite l.
(e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications. WCAP-13632, Revision 2, " Elimination of Pressure Sensor l
Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verification of the j
channel response time for specific sensors identified in the WCAP.
The allocations for these sensor response times must be verified prior to placing the sensor in operational service and re-verified following maintenance that say adversely affect response time.
In general, electrical repair work does l
not impact response time provided the parts used for repair are of the same, i
type and value. One example where time response could be affected is replacing j
the sensing assembly of a transmitter. Response time verification for other sensor types must be demonstrated by test.
f 3/4.3.3 MONITORING INSTRUKENTATION 3 /4. 3. 3.1 RADIATION HONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the l
radiation levels are continually measured in the areas served by the individual
]
channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
j Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and i
50,000 scfm in MODES 4, 5, and 6.
The containment purge setpoints are based on j
a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the affluent concentration limits stated in 10 CFR 20, Appendix I (to paragraphs 20.1001 - 0.2j01), Table 2, 6
t Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site l
- boundary.
1, FARLEY-UNIT 1 E 3/4 3-2 AMENDMENT NO. 2I, INI,116 1
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j INSTRUMENTATION
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RADIATION MONITORING INSTRUMENTATION (Continued) l I
The alare/ trip setpoint for the fuel storage pool area has been established I
j -
based on a flow rate of 13,000 sefm; a release in which Xe-133 and Kr-85 are.
j
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the predominant isotopes, on concentration values equal to or less than the' l
effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs i
20d001-30.2401), Table 2, Column 1fortheseisotopes,andonaX/Qof5.6x 10-sec/m at the site boundary.
i.
-3/4.3.3.2 MOVABLE INCORE DETECTORS j
The OPERABILITY of the movable incore detectors with the specified minimum j
complement of equipment ensures that the measurements obtained from 1se of this 1
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 determining the acceptability of its voltage curve.
s 1
For the purpose of measuring F (3), Ph,andF a full incore flux map g
is used.
Quarter-core flux maps, an defined in WCA -8648,-June 1976, may be j
used in recalibration of the excore neutron flux detection system.
Full i
incore flux maps or symmetric incore thimbles may be used for monitoring the j-QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
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FARLEY-UNIT 1
.B 3/4 3-2a AMENDMENT NO. 116 i
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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
APPLICABILITY: As shown in Table'3.3-1.
AGZlGE8 As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
.4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be verified to be within its limit at least once per 18 months.* Each verification shall include at least one logic train such that both logic trains i
are verified at least once per 36 months and one channel per function such that all channels are verified at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown j
in the " Total No. of. Channels" column of Table 3.3-1.
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- Neutron detectors are exempt from response time testing.
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t FARLEY-UNIT 1 3/4 3-1 AMENDMENT NO. II. III. 116 i
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l INSTRUMENTATION 3/4.3.2 ENGINeetED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTk? ION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip 4
setpoints set consistent with the values shown in the Trip Setpoint column of i
Table 3.3-4.
APPLICABILITY: As shown'in Table 3.3-3.
AEII2N8 l
With an ESFAS instrumentation channel or interlock trip setpoint a.
less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is i
i restored to OPERABLE status with the trip setpoint adjusted j
consistent with the Trip Setpoint value.
)
b.
With an ESFAS instrumentation channel or interlock inoperable, take j
the ACTION shown in Table 3.3-3.
i SURVEILLANCE REQUIREMENTS i
4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CNANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
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4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the
(
automatic actuation logic test. The total interlock function shall be l
demonstrated OPERABLE at least once per 18 months.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME.of each ESFAS function shall be verified to be within the limit at least once per 18 months. Mach verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the j
" Total No. of Channels" Column of Table 3.3-3.
s FARLEY-UNIT 1 3/4 3-15 AMENDMENT NO. 26, 195, 116
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666 0001
'+9.....,o SOUTHERN NUCLEAR _0PERAIING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE 1
Amendment No.108 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 17, 1994, as supplemented June 15 and August 11, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; e
8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission'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. NPF-8 is hereby amended to read as follows:
~.
_.2 (2)
Technical Soecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.108, are hereby incorporated in the
' license.
Southern Nuclear 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- l rbert N. Berkow, Director roject Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 28, 1995 l
f 4
)
1 i
J J
ATTACHMENT TO LICENSE AMENDMENT NO.108 TO FACILITY OPERATING LICENSE N0. NPF-8 DOCKET NO. 50-364 Replace-the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 3-1 3/4 3-1 3/4 3-15 3/4 3-15 B 3/4 3-2 B 3/4 3-2 B 3/4 3-2a i
1 4
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t 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minis.um. the reactor trip system instrumentation channels and interlocks of Table 3.3-1 snall be OPERABLE.-
s APPLICABILITY:' As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
d i
SURVEILLANCE REOUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated l
OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown i
in Table 4.3-1.
4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be verified to be within its limit at least once per 1B months.* Each j
verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
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- Neutron detectors are exempt from response time testing.
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FARLEY-UNIT 2 3/4 3-1 AMENDMENT NO. 98,108 j
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INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FIATURE ACTUATION SYSTEM INSTRUMENTATION 4
LIMITINO CONDITION FOR OPERAT2ON J
3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip 4-setpoints set. consistent with the values shown in the Trip setpoint column of j
Table 3.3-4.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
With an ESFAS instrumentation channel or interlock trip setpoint a.
less conservative t.han the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply i
the applicable ACTEON requirement of Table 3.3-3 until the channel is restored to OPEllABLE states with the trip setpoint adjusted conmistent with this Trip Setpoint value.
1 J
b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
i SURVEILLANCE REQUIREMENTS
{
i 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
l l
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within the limit at least once per 18 months. Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N times 1E months where N is the i
l total number of redundant channels in a specific ESFAS function as shown in the
" Total No. of Channels" Column of Table 3.3-3.
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FARLEY-UNIT 2 3/4 3-15 AMENDMENT NO. 77, 95, 108 I
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INSTRUMENTATION 4
1 l
j BASES REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTKM INSTRUMENTATION (Continued) i The verification of response time at the specified frequencies provides l
j assurance that the reactor trip and ESF actuation associated with each channel l
is completed within the time limit assumed in the accident analyses. Responsa j
time limits for the Reactor Trip System and Engineered Safety Features Actuation System are maintained in Tables 7.2-5 and 7.3-16 of the Farley FSAR, l 4
respectively. No credit was taken in the analyses for those channels with response times indicated as not applicable.
1 l
Response time may be verifica by actual tests in any series of j
sequential, overlapping or total channel measurements, or by summation of allocated sensor response times with actual tests on the remainder of the channel in any series of sequential or overlapping measurements. Allocations j
for specific pressure and differential pressure sensor response times may be i
obtained from (1) historical records based on acceptable response time tests j
(hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilising vendor engineering j
specifications. WCAP-13632, Revision 2, " Elimination of Pressure Sensor j
Response Time Testing Requirements," provides the basis and methodology for i
using allocated sensor response times in the overall verification of the l
channel response time for specific sensors identified in the NCAP.
The
{
allocations for these sensor response times must be verified prior to placing i
the sensor in operational service and re-verified following maintenance that j
may adversely affect response time.
In general, electrical repair work does l
not impact response time provided the parts used for repair are of the same,
l-type and value. One example where time response could be affected is replacing the sensing assembly of a transmitter. Response time verification for other i
sensor types must be demonstrated by test.
~
I i
3/4.3.3 MONITORING INSTRUMENTATION t
3 /4. 3. 3.1 RADIATION MONITORING INSTRUMENTATION i
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 when the radiation level trip eetpoint is exceeded.
f Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and l
50,000 scfm in NODES 4, 5, and 6.
The containment purge setpoints are based on l
a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the offluent concentration limits
{
stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 0.2pl), Table 2, 6
j Column 1 for these isotopes, and on a X/Q of 5.6 x 10 esc /m at the site j
boundary.
i f
FARLEY-UNIT 2 3 3/4 3-2 AMENDMENT NO. 92, 95, 108 l
4 INSTRUMENTATION nasEs j
RADIATION MONITORING INSTRUMENTATION Continued)
The alarm / trip setpoint for the fuel storage pool area has been established based on a flow rate of 13,000 sefm; a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix 5 (to paragraphs 20.g001-30.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.
3/4.3.3.2 MOVAaLE 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 determining the acceptability of its voltage curve.
For the purpose of measuring F (3), F%g, and F, a full incore flux map g
Quarter-corefluxmaps,asdefinedinWCAh-8648, June 1976,maybe is used.
used in recalibration of the excore neutron flux detection system.
Full incore-flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
n g ;
FARLEY-UNIT 2 B 3/4 3-2a AMENDMENT NO.108 l