ML20033C182
| ML20033C182 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/29/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| TASK-2.F.1, TASK-TM NUDOCS 8112020828 | |
| Download: ML20033C182 (3) | |
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DISTRIBUTION Docket File NRC PDR Local PDR OCT 2 91981 NSIC TERA ORB 1 File Docket Nos. 50-348 D
senh" and 50-364 3;
] emes
-l//4 N
S. Varga f
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/>'d ffr. F1 L. Clayton E. Reeves 2 6Lt
~h C. Parrish
~i Senior Vice President OELD M
N y 9 198 P ~
Alabama Power Company IE (3) f
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P. O. Bcx 2641 ACRS (10)
A u$ E" Birmingham, Alabama 35291 n
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Dear Mr. Clayton:
f9., g SUCJECT: STATUS OF NUREG-0737 ITEMS II.F.1.1 AND II.F.1.2 FOR JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO.1 AND NO. 2 f!UREG-0737 Itens II.F.1.1 and II.F.1.2 related to the installation of high range noble gas effluent monitors and provisions for effluent monitoring of radioiodines at. accident conditions by January 1,1982. Since a post-implementation review is planned, we are presently reviewing only deviations to the stated NRC positions. Based on our review of your sutxaittals, no tech-nical deviations from the stated positions are needed to implement Items II.F.1.1 and II.F.1.2.
If this understanding is not correct, we request formal notification of such within 30 days of receipt of this letter.
Your letter dated Septeraber 9,1981 for Farley Unit No.1 advised of a minor schedular problem based on your third refueling outage scheduled to start about February 1982. This would have put your Installation about one month after January 1, 1982. However, as the Unit No. 1 outage has nce started ahead of schedule, due to the nain generator failure, your staff (Fr. J. Ripple) advised our Project Manager (Mr. Ed Reeves) on October 20, 1981 that the installation was underway now. Thus, the original NUREG-0737 schedule would be met. For Unit No. 2 the installation was completed prior to achieving 5 percent power. Since the Commission will review any requests for delayed inplementation of all NUREG-0737 items, please inforn us as early as possible of any schedule revisions.
Changes to the existing Unit No.1 and Unit No. 2 Technical Specifications (TS's) i appear necessary to fully implement Items II.F.1.1 and II.F.1.2.
Therefore, i
sample Standard TS pages are enclosed for your assistance. Your application for such proposed changes may be suhaitted any time prior to January 1,1982. However, I
the upgrading of Unit No.1 TS's to the Unit No. 2 type may negate the need for further changes if the Unit 2 TS are compatible with Items II.F.1.1 and II.F.1.2.
In any case, your response to these specific NUREG-0737 items should include comments relative to the sample Standard TS's provided herein.
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PDR.
l unc ronu m oo-w uncu om OFFICIAL RECORD COPY usem un-mm
e Mr. F. L. Clayton OCT 2 91981 If you have questions on any portions of this letter, please contact the NRC Project Manager. Ed Reeves.
Sincerely, Wiginal Sip; nod BYJ Steven A. Yarga, Chief Operating Reactors Branch No.1 Division of Licensing
Enclosure:
As stated cc: See next page i
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..a 10/.23/81 tac ronu sis oo-eomacu oua OFFICIAL RECORD COPY usom ini-333-m
d Mr. F. L. Clayton, Jr.
Alabama Power Company cc:
Mr. W. O. Whitt Executive Vice President Alabama Power Company -
' Post.0ffice Box 2641 Birmingham, Alabama 35291 Ruble A. Thomas, Vice F esident Southern Company Services, Inc.
t Post Office Box 2625 Birmingham, Alabama 35202 George F. Trowbridge, E' squire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Wa shi ngto'1, D. C.
20036 1
Mr. Robe-t A. Buettner, Esquire Balch, Bingham, Baker, Hawthorne, Williams and Ward Post Office Box 306 Birmingham, Alabama 35201 George S. Houston Memorial Library 212 W. Burdeshaw Street Dothan, Alabama 36303 Resident Inspector i
U. S. Nuclear Regulatory Commission Post Office Box 24-Route.2 Columbia, Alabana 36319 l
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INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
, ACTION:
a.
With a radiation monitoring channel alara/ trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpcint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inorerable.
b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
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c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.3.1 tach radiation monitoring instrumentation channel shall be demon-strated 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 4.3-3.
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TABLE 3.3-6 h
RADIATION MONITORING INSTRUMENTATION I
MINIMUM l
CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.
AREA MONIT01S a.
Fuel Storage Pool Area
_j 4
i.
Criticality Monitor (1) 1 15 mR/hr (10
- 10 ) mR/hr 25 ii.
Ventilation System 5
Isolation (1)
($ 2 x background)
(1 - 10 ) cpm 27 5
i b.
Containment - Purge &
(1) 6
($ 2 x background)
(1 - 10 ) cpm 28 Exhaust Isolation 4
c.
Control Room Isolation (1)
All MODES
($ 2 x background)
(10
- 10 )mR/hr 29 j
8 d.
Containment Area 2
1, 2, 3 & 4
(
) r5tt/hr 1-10 rad /hr 30 2.
PROCESS MONITORS a.
Fuel Storage Pool Area -
Ventilation System Isolation 5
i.
Gaseous Activity (1)
(1 2 x background)
(1 - 10 ) cpm 27 ii.
Particulate Activity (1)
($ 2 x background)
(i 10 ) cpm 27 b.
Containtrent i.
Gaseous Activity a) Purge & Exhaust Isolation (1) 6
($ 2 x background)
(1 - 10 ) cpm 28 b)RCS Leakage Detection (1) 1, 2, 3 & 4 N/A (1 - 10 ) cpm 26 ii.
Particulate Activity a)Furge & Exhaust Isolation (1) 6 (1 2 x background)
(1 - 10 ) cpm 28 b)RCS Leakage Detection (1) 1, 2, 3 & 4 N/A (1.- 10 ) cpm 26
- With. fuel in the storage pool or building-
- With irradiated fuel in the storage pool 7
TABLE 3.3-6 (Continued) h RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT J
INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION PROCESS MONITORS (Continued) c.
Noble Gas Effluent Monitors i.
Radwaste Buildin:)
2 Exhaust System 1
1, 2, 3 & 4
(
) rad /hr 1-10 uCi/cc 30 j
ii.
Auxiliary Building 3
I Exhaust System 1
1, 2, 3 & 4
(
) rad /hr 1-10 uCi/cc 30 l
iii.
Steam Safety Valve 3
{
Discharge 1/ valve 1, 2, 3 & 4
(
) rad /hr 1-10 6Ci/cc 30 T
iv.
Atmospheric Steam Dump Valve 3
Discharge 1/ valve 1, 2, 3 & 4
(
) rad /hr 1-10 uCi/cc 30 v.
Exhaust System 1
1, 2, 3 & 4
(
) rad /hr 1-10 uCi/cc 30 vi.
Containment Purge &
5 Exhaust System 1
1, 2, 3 & 4
( ) rad /hr 1-10 uCi/cc 30 vii.
Condenser Exhcust 5
System 1
1, 2, 3 & 4
(
) rad /hr 1-10 uCi/cc 30 Y
TABLE 3.3-6 (Continued)
ACTION STATEMENTS ACTION 25 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 26 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification (3.4.6.1).
ACTION 27 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification (3.9.12).
ACTION 28 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification (3.9.9).
ACTION 29 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recircelet % n mode of operation.
ACTION 30 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) tc OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
- 1) Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and
- 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
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j TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH I
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS INSTRUMENT CllECK CALIBRATION TEST REQUIRED 1.
AREA MONITORS a.
Fuel Storage Pool Area i.
Criticality Monitor S
R M
ii.
Ventilation System Isolation S
R H
b.
Containment - Purge & Exhaust Isolation S
R M
6 Control Room Isolation S
R M
All MODES c.
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d.
Containment Area S
R M
1, 2, 3 & 4 2.
PROCESS MONITORS T
a.
Fuel Storage Pool Area - Ven-tilation System Isolation i.
Gaseous Activity S
R H
ii.
Particulate Activity S
R M
b.
Containment j
i.
Gaseous Activity a) Purge & Exhaust
)
Isolation S
R M
6 b) RCS Leakage Detection S
R M
1, 2, 3, & 4 l
ii.
Particulate Activity a) Purge & Exhaust Isolation S
R M
6 1
i b) RCS Leakage Detection S
R H
1, 2, 3, & 4
- With fuel in the.stcrage pool or building.
- With irradiated fuel in the storage pool.
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TABLE 4.3-3 (Continued)
U RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
.m CHANNEL MODES FOR WHICH CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE IS INSTRUMENT CllECK CALIBRATION TEST REQUIRED PROCESS MONITORS (Continued) c.
Noble Gas Effluent..tonitors i.
Radwaste Building Exhaust System 5
R M
1, 2, 3 & 4 ii.
Auxiliary Building Exhaust System S
R M
1, 2, 3 & 4 iii.
Steam Safety Valve
{
Discharge 5
R M
1, 2, 3 & 4 Y
iv.
Atmospheric Steam Dump Valve Discha.ge S
R H
1, 2, 3 & 4 v.
Shield Building Exhaust System S
R M
- 1. 2, 3 & 4 vi.
Containment Purge &
Exhaust System S
R M
1, 2, 3 & 4 vii.
Condenser Exhaust System S
R M
1, 2, 3 & 4 P
INSTRUMENTATION BASES 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 integrated operation of each of these systems is consistent with the assumptions used ir. the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design stat.1ards. "The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
The measurement of response time at the specified frequencies provides assurance that the RPS and ESFAS action function associated with each channel is completed within the time limit assumed in the safety analyses. 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 test demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or
- 2) utilizing replacement sensors with certified respt"o times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:
- 1) the radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) 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 and Environs Conditions During and Following an Accident," Deceder 1980 and NUREG-0737,
" Clarification of TMI Action Plan Requirements," November, 1980.
3/4.3.3.2 R. ABLE 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 distributien of the The OPERABILITY of this system is demonstrated by irradiating reactor core.
each detector used and. determining the acceptability of its voltage curve.
a full incore flux map is used.
for the purpose of measuring F (Z) or F H 9
Quarter-co e flux caps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore f
flux maps or syn.etric incore thimbles may be used for monitoring tne Q'JADRANT POWER TILT RATIO when one Pc er Range Channel is ireperable.
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