ML19353B140
| ML19353B140 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/04/1989 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19353B141 | List: |
| References | |
| NUDOCS 8912120012 | |
| Download: ML19353B140 (9) | |
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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO F_ACILITY OPERATING LICENSE Amendment No.127 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Boston Edison Company (the licensee) dated September 11, 1989, 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 requirtments 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 3.B of Facility Operating License No. DPR-35 is hereby l
amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.127, are hereby incorporated in the license.
The licensee shell operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 9
D Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications Date of Issuance:
December 4, 1989 k
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This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/5 Richard H.
essman, Director Project Directorate I-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 4, 1989 1
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OFFICIAL RECORD COPY l
l ATTACHMENT TO LICENSE AMENDMENT NO.127 1
FACILITY OPERATING LICENSE NO. DPR-35 j
DOCKET NO. 50-293 i
Replace the following pages of the Appendix A Technical Specifications with-l the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
j Remove Insert
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195 195 196 196 197-197 199 199 201 201 i
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1 l,' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
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3.9.A AUX 1LIARY ELECTRICAL EOUIPMENT 4.9.A AUXILIARY ELECTRICAL EOUIPMENT (Cont'd)
SURVEILLANCE (Cont'd) 4.
4160 volt buses A5 and A6 are
- d. Once a month the quantity of energized and the associated 480 diesel fuel available shall volt buses are energized.
be logged.
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5.
The station and switchyard 125 and
- e. Once a month a sample of 250 volt batteries are operable.
diesel fuel shall be checked Each battery shall have an for quality in accordance operable battery charger, with ASTM 04057-81 or D4177-82.
The quality shall 6.
Emergency Bus Degraded Voltage be within the acceptable Annunciation System as specified limits specified in Table 1 in Table 3.2.B.1 is operable, of ASTM 0975-81 and logged.
7.
Soecification
- 2. Station and Switchyard Batteries Two redundant RPS Electrical
- a. Every week the specific Protection Assemblies (EPAs) shall gravity, the voltage and be operable at all times on both temperature of the pilot cell inservice power supplies, and overall battery voltage shall be measured and logged.
Action
- b. Every three months the
- a. With one EPA on an inservice measurements shall be made of power supply inoperable, voltage of each cell to continued operation is nearest 0.1 volt, specific permissible provided that the gravity of each cell, and EPA is returned to operable temperature of every fifth status or power it transferred cell.
These measurements to a source with two operable shall be logged.
EPXs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If this requirement cannot be met, trip
- c. Once each operating cycle.
the power source.
the stated batteries shall be subjected to a rated load
The specific inoperable on an inservice gravity and voltage of each power supply, continued cell shall be determined operation is permissible, after the discharge and provided at least one EPA is
- logged, restored to operable status or power is transferred to a
- 3. Emergency 4160V Buses A5-A6 source with at least one Degraded Voltage Annunciation
~
operable EPA within 30 System.
minutes.
If this requirement cannot be met, trip the power
- a. Once each operating cycle, source.
calibrate the alarm sensor.
NOTE: Only applicable if tripping the
- b. Once each 31 days perform a power source would not result in t channel functional test on
- scram, the alarm system.
Revision Amendment No. /2, U, N,127 195
LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B Ooeration with Inocerable 4.9. A Auxiliary Electrical Eauiement i
Eautoment Surveillance (Cont'd)
Whenever the reactor is in Run
- c. In the event the alarm system Mode or Startup Mode with the is determined inoperable reactor not in a Cold Condition, under 3.b above, commence the availability of electric power logging safety related bus shall be as specified in 3.9.B.1.,
voltage every 30 minutes 3.9.B.2, 3.9.B.3, 3.9.B.4, and until such time as the alarm 3.9.B.S.
is restored to operable status.
1.
From and after the date that incoming power is not available
- 4. RPS Electrical Protection from the startup or shutdown Assemblies transformer, continued reactor operation is permissible under
- a. Each pair of redundant RPS this condition for seven days.
EPAs shall be determined to During this period, both diesel be operable at least once per generators and associated 6 months by performance of an emergency buses must be instrument functional test.
demonstrated to be operable.
- b. Once per operating cycle, 2.
From and after the date that each pair of redundant RPS incoming power is not available EPAs shall be determined to from both startup and shutdown be operable by performance of transformers, continued operation an instrument calibration and is permissible, provided both by verifying tripping of the diesel generators and associated circuit breakers upon the emergency buses are demonstrated simulated conditions for to be operable, all core and automatic actuation of the containment cooling systems are protective relays within the operable, reactor power level is following limits:
redtided to 257 of design and the NRC is notified within one (1)
Overvoltage 1 132 volts hour as required by 10CFR50.72.
Undervoltage 2 108 volts Underfrequency 1 57Hz 3.
From and after the date that one of the diesel generators or associated emergency bus is made or found to be inoperable for any reason, continued reactor operation is permissible in accordance with Specification 3.5.F if Specification 3.9.A.1 and 3.9. A.2.a are satisfied.
4.
From and after the date that one of the diesel generators or associated emergency buses and either the shutdown or startup transformer power source are made Revision Amendment No, p 127 196
I
, " ' LIM TING 00NDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.8 Ooeration with Inonerable Eauinment (Cont'd) or found to be inoperable for any j-reason, continued reactor operation is permissible in accordance with Specification 3.5.F. provided either of the following conditions are satisfied:
- a. The startup transformer and both offsite 345 kV transmission lines are available and capable of automatically supplying auxiliary power to the emergency 4160 volt buses.
- b. A transmission line and associated shutdown transformer are available and capable of automatically supplying auxiliary power to the emergency 4160 volt buses.
- 5. From and after the date that one of the 125 or 250 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three days within electrical safety considerations, provided repair work is initiated in the most expeditious manner to return the failed component to an operable state, and Specification 3.5.F is satisfied.
- 6. With the emergency bus voltage less than 3959V but above 3868V (excluding transients) during l
normal operation, transfer the safety related buses to the diesel generators.
If grid L
voltage continues to degrade be in at least Hot Shutdown l
within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in Cold Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> unless the gric conditions improve.
Revision Amendment No. #2, H, EE, J23, 127 197
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,;A&iES(continued) 3.9 can be used for either 125 volt battery, (2) a 250 volt d-c back-up battery charger is supplied.
Thus, on loss of normal battery charger, the back-up charger can be used. The 125 volt battery system shall have a mininium of 105 volts at the battery terminals to be considered operable.
The 250 volt battery system shall have a minimum of 210 volts at the battery terminals to be considered operable.
Automatic second level undervoltage (Degraded Voltage) protection is installed on the startup transformer and is available when safety related loads are being supplied from this source.
During normal operation, the unit auxiliary transformer supplies safety related buses. Automatic second level undervoltage protection is not installed on the unit auxiliary transformer.
The Safety Bus Degraded Voltage Alarm System and new Degraded Voltage Operating Procedure will be relied upon to guide Operator action to preclude operation with a degraded bus voltage condition.
Each of the two motor generator sets and the alternate power supply for the Reactor Protection System (RPS) have two Electrical Protection Assemblies (EPAs), installed in series, between the RPS 120 Volt 60Hz power source and its respective RPS bus. A random, or seismically-induced abnormal voltage or frequency condition on the output of an MG Set or on the alternate supply would trip one or both of the EPAs. This protects the RPS components and auxiliaries from damage due to sustained abnormal voltage conditions (overvoltage, undervoltage or underfrequency).
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> maximum service limit of an " inservice power supply" with only one EPA operable provides reasonable assurance that a single failure would not prevent an abnormal voltage condition from being detected prior to damaging RPS components.
The " inservice power supplies" are defined as either the two RPS HG Sej,s or one RPS MG Set and the alternate power source fed from B10/B6.
The 30 minute maximum service limit without either EPA operable provides
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reasonable assurance that an abnormal voltage condition would not damage RPS components.
The tripping of an RPS power supply to an RPS bus will result in
'a half-scram on that channel.
Revision Amendment No. 52' I ' I27 199
'.'.'EASIS:
(C:nt'd) 4.9 The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel er.gine.
When it is determined that some auxiliary electrical equipment is out of service, the increased surveillance required in Section 4.5.F is deemed adequate to provide assurance that the remaining equipment will be operable.
The Electrical Protection Assemblies (EPAs) on the RPS inservice power supplies (either two motor generator sets or one motor generator and the alternate supply), consist of protective relays that trip their incorporated circuit breakers on overvoltage, undervoltage or underfrequency conditions.
There are 2 EPAs in series per power source.
It is necessary to periodically test the relays to ensure the sensor is operating correctly and to ensure the trip unit is operable.
Based on experience at conventional and nuclear power plants, a six month frequency for the channel functional test is established.
This frequency is consistent with the Standard Technical Specifications.
The EPAs of the power sources to the RPS shall be determined to be operable by performance of a channel calibration of the relays once per operating cycle.
During calibration, a transfer to the alternate power source is required; however, prior to switching to alternate feed, de-energization of the applicable MG set power source must be accomplished.
This results in a l
half-scram on the channel being calibrated until the alternate power source is connected and the half scram is cleared.
Based on operating experience, drift of the EPA protective relays is not significant.
Therefore, to avoid possible spurious scrams, a calibration frequency of once per cycle is established.
Revision Amendment No. 127 201