ML19350D172
| ML19350D172 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/01/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350D173 | List: |
| References | |
| NUDOCS 8104130637 | |
| Download: ML19350D172 (8) | |
Text
7 )l
- o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
g j
WASHINGTON. D. C. 20$55 s...../
BOSTON EDIS0N COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Boston Edison Company (the licensee) dated March 16, 1981 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; 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 (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 comon defense and security or to the health and sofcv vi i.ne 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 Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications' contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
I I
810.4130 M7
-2_
3.
This license Amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION
, A -
Thomas
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 1,1981
[
t I
l
?
I t
i
.=
ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Remove the following pages and insert identically numbered pages:
58 59 66 73 211 L
i l
f I
i I
f l
l l
t
TABLE 3.2.F
_SURVEILIANCE INSTRUMENTATION Minimum f of Operable Instrument Type Indication Channels Instrurent #
Instrument and Range Notes 2
640-29A & B Reactor Water Level Indicator 0-60" (1) (2) (3) 2 640-25A & B Reactor Pressure Indicator 0-1200 psig (1) (2) (3) 2 TRU-9044 Drywell Pressure Recorder 0-80 psia (1) (2) (3)
TRU-9045 2
TRU-9044 Dryvell Temperature Recorder, Indicator (1) (2) (3)
TI-9019 0-400 F 2
TRU-9045 Suppressico ChamNer Air Recorder, Indicator (1) (2) (3)
TI-9018 Temperature 0-4000F 2
LR-5038 Suppression Chamber Water Level Recorder 0-32" (1) (2) (3)
LR-5049 1
NA Control Rod Position 28 Volt Indicating )
Lights
)
)
(1) (2) (3) (4) 1 NA Neutron Monitoring SRM, IRM, LPRM
)
O to 100% power
)
2 TI-5047 Suppression Chamber Water Indicator 50-150 F (1) (2) (3)
TI-5048 Temperature E
1 PI-5021 Drywell/ Torus Diff. Pressure Indicator
.25*3.0 psid (1) (2) (3) (4) 1 PI-5067A Drywell Pressure Indicator
.25 +3.0 psig '
PI-5067B Torus Pressure Indicator -1.0 *+2.0 (1) (2) (3) (4) psiR 1/ Valve a) Primary Safety / Relief Valve Position a) Acoustic monitor (5)
(5)
Indicator b) Thermocouple or b) Backup 1/ Valve a) Prinary Safety Valve Position Indicator a) Acoustic monitor (5)
(5) b) Thermocouple or b) Backup Amendment No. 48
A a
NOTES FOR TABLE 3.2.F_
)
From and after the date that one of these. parameters is reduced (1) to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.
From and after the da:e that one of these parameters is not indi-(2) cated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.
If the requirements of notes (1) and 1) cannot be met, an (3) orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
These surveillance instruments are considered to be redundant to (4) each other.
At a minimum, the primary or back-up parameters shall be operable for (5)
With both primary each valve when the valves are required to be operable.
instrument channels inoperable either return one (1) channel and backup to operable status within 31 days or be in a shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The following instruments are associated with the safety / relief & saf ety valves:
Primary Secondary Valve Acoustic Monitor Tail Pipe Tereperature Thernocouple 203-3A ZT-203-3A TE6271-B 203-3B ZT-20 3-3B TE6272-B 203-3C ZT-203-3C TE6273-B 203-3D ZT-203-3D TE6276-B 20 3-4 A ZT-203-4A TE6274-B 203-4B ZT-20 3-4B TE6275-B j
p k
t 9
Amendment No. 48 l
59
PNPS TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUENCY FCR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check 1)
Reactor Level Once/6 months Each Shift 2)
Reactor Pressure Once/6 months Each Shift 3)
Drywell Pressure Once/6 months Each Shift 4)
Drywell Temperature Once/6 months Each Shift 5)
Suppression Chamber Temperature Once/6 months Each Shift 6)
Suppression Chamber Water Level Once/6 months Each Shift 7)
Control Rod Position NA Each Shift 8)
Neutro.2 Monitoring (2)
Each Shift,
[
9)
Drywell/ Torus Differential Pressure Once/6 months Each Shift E.
10)fDrywellPressure Once/6 months Each Shift
[ Torus Pressure Once/6 months n
E
~
- 11) Safety / Relief Valve Each refueling Once each day Position Indicator outage (Primary / Secondary) es
- 12) Safety Valve Position Each refueling Once each day c'
Indicator (Primary /
outage Secondary)
Amendment No. 48
3.2 RA1Q (Cont'd)
For most parameters monitored, as listed in Table 3.2.F. there are two (2)
By comparing readings between these two (2) channels of instrumentation.
channels, a near continuous surveillance, of instrument performance is available. Meaningful deviation in comparative readings of these instru-ments will initiate an early recalibration, thereby maintaining the quality of the instrument readings.
'Ihe Safety - Safety / Relief Valve position indication instrumentation provides the operator with information on selected plant parameters ident.
to monitor and assess these variables during and following an acc The recirculation pump trip / alternate rod insertion syst 25016 (Reference 1) as referenced by the NRC as an acceptableRe design (Reference 2) for RPT.
The pump trip is provided descriptions and performance analyses.
to sdnimize reactor pressure in the highly unlikely event of a plant transient coincidsnt with the failure of all control rods to The rapid flow reduction increases core voiding providing a scram.
negative reactivity feedback.The rectreulation pump trip is only sensors initiate the trip.
required at high reactor power lesels, where the safet Requiring the to be generated in this unlikely postulated event. trip to b The low water level trip function includes a time delav of nine (9) seconds t one (1) second to avoid increasing the consequences tive.
This delay has an insignificant effect on of a postulated LOCA.
ATVS consequences.
Alternate red insertion utilizes the same initiation logic and functions as RPT and provides a diverse means of initiating system to depressurize the scram pi. lot air header, which in turn reactor s, cram.
causes all control rods to be inserted.
I References _
NEDO-25016. " Evaluation of Anticipated Transie 1.
1976.
NUREG 0460, Volume 3, December 1978.
2.
l 73 l
I Amendment No. 48
\\
e PILCRIM NUCLEAR POWER STATION MINIMUM SHIFT CREW COMPOSITION _
TECHNICAL SPECIFICATION TABLE 6.2-1 STATION CONDITION
- CREW MINIMUM NUMBER ON DUTY 0?ERATING Licensed Senior Reactor Operator 1
Licensed Reactor Operator 2
Unlicensed Operator 2
Shif t Technical Advisor **
1 l
COLD SHUTDOWN Licensed Senior Reactor Operator 1
and Licensed Reactor Operator 1
REFUELING Unlicensed Operator 1
Shif t Technical Advisor **
None Required
- Higher grade licensed operators may take the place of lover grade licensed or unlicensed personnel.
- Provides an On-Shif t Technical Advisor who has a bachelor's degree or equivalent (l)in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
(1) Or equivalent is defined as an Associate Degree in nuclear or mechanical engineering plus 5 years nuclear exnerience.
Amendment No. 48 211
,