ML20236U469
| ML20236U469 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/30/1987 |
| From: | Fairtile M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236U472 | List: |
| References | |
| NUDOCS 8712030074 | |
| Download: ML20236U469 (10) | |
Text
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g UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 5
l WASHINGTON, D. C. 20555
\\...../
BOSTON EDIS0N COMPANY DOCKET N0. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated. lune 2,1987 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 Comission; C.
There is reasonable assurance (1) that the activities authorized by j
this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 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 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 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows:
87120300'74 e71130 PDR ADOCK 05000293 P
?..
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.110, are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the
' Technical Specifications.
3.
This license amendment is effective 30 days after the date of issuance.
FOR THE NtICLEAR REGULATORY COMMISSION
'LY Let L
Morton B. Fairtile, Acting Director Project Directorate 1-3 Division of Reactor Pro.iects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: November 30, 1987
1 ATTACHMENT TO LICENSE AMEN 0 MENT NO.110 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the' enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
l l
Remove Pages Insert Pages 43 43 54 54 55 55 55a*
63 63 67 67 71 71 1
1
- New page i
l l
1 I
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT C.
Control Rod Block Actuation C.
Control Rod Block Actuation j
1.
The 1imiting conditions of I.
Instrumentation shalI be operation for the instrumentation functionally tested, calibrated that initiates control rod block and checked as indicated in Taele are given i?. Table 3.2.C-l.
The 4.2.C.
trip setpoints for this instrumentation shall be set System logic shall be i
consistent with Table 3.2.C-2.
functionally tested as indicated in Table 4.2.C.
D.
Radiation Monitoring Systems -
D.
Radiation Monitoring Systems -
Isolation & Initiation Functions Isolation & Initiation Functions I
1.
Reactor Building Isolation and 1.
Reactor Buildina Isolation and j
Control Svstem and Standbv Gas Control System and Stanabv Gas Treatment System Treatment System j
i The limiting conditions for Instrumentation shall be j
operation are given in Table functionally tested, calibrated 3.2.0.
and checked as indicated in Table 4.2.D.
i System logic shall be functionally tested as indicated in Table 4.2.D.
i
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Notes for Table 3.2.C-1
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1.
With the-number of operable channels:
l a.
One less than_ required by the minimum operable channels per trip l
function requirement, restore an_ inoperable channel to operable status within 7 days or place an inoperable channel in the tripped condition within the next hour.
b.
Two or more less than required by the minimum operable channels per trip function requirement, place at least one inoperable channel in the tripped condition within one hour.
2.
The minimum operable channels for the rod block monitor trip function may be reduced by one for maintenance and/or testing, provided that this condition does not last longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any thirty day period.
3.
If the number of operable channels is less than required by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within one hour.
4.
SRM operability requirements during core alterations are given in Technical Specification 3.10.
1 l
i Amendment No. 77,110 55
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NOTES FOR TABLES 4.2.A THROUGH 4.2.G 1.
Initially once per month until exposure hours (H as defined on Figure 5
4.1.1) is 2.0 x 10 ; thereafter, according to Figure 4.1.1 with an interval not less than one month nor more than three months.
2.
Functional tests, calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations of IRMs and SRMs shall be performed during each startup or during controlled shutdowns with a required frequency not to exceed once per week.
Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operable.
3.
This instrumentation is excepted from the functional test definition.
The functional test will consist of injecting a simulated electrical signal into the measurement channel.
I 4.
Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.
5.
Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2.A since they are tested on Table 4.1.2.
6.
The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip J
systems.
7.
Calibration of analog trip units will be performed concurrent with functional testing. The functional test will consist of injecting a j
simulated electrical signal into the measurement channel. Calibration of associated analog transmitters will be performed each refueling outage.
i Amendment No. O, 99, 110 67
l l
3.2 BASES (Cont'd)
The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the Safety Limit MCPR.
The trip logic for this function is 1 out of n:
e.g., any trip on one of six APRM's, eight IRM's, or four SRM's will result in a rod block.
The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met. The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration.
This time period is only
- 37. of the operating time in a month and does not significantly increase the risk of preventing an inadvertent control rod withdrawal.
The APRM rod block function is flow biased and prevents a significant reduction in MCPR. especially during operation at reduced flow.
The APRM provides gross core protection; 1.e., limits the gross core power increase from withdrawal of control rods in the normal withdrawal sequence.
The trips are set so that MCPR is maintained greater than the Safety Limit MCPR.
The RBM rod block function provides local protection of the core, for a single rod withdrawal error from a limiting control rod pattern.
The IRM rod block function provides local as well as gross core protection. The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.
A downscale indication on an APRM or IRM is an indication the. instrument has failed or the instrument is not sensitive enough.
In either case the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented.
The downscale trips are as shown in Table 3.2.C-2.
l The flow comparator and scram discharge volume high level components have only one logic channel and are not required for safety.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate ir, time.
The automatic pressure relief function is provided as a backup to the l
i Amendment No. E, 110 71 l
Bases revised l
July 1, 1986
.