ML19344D111
| ML19344D111 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/22/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19344D105 | List: |
| References | |
| NUDOCS 8003110347 | |
| Download: ML19344D111 (7) | |
Text
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UNITED STATE 5 k
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BOSTON EDISON COMPANY C0CKET NO. 50-293 PILGRIM NUCLEAR POWER STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 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 November 21, 1977 as supplemented December 7,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regu-lations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity 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 conductad in compliance with the Comission's regulations; D.
The issuance of this 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 3.8 of Facility License No. DPR-35 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A an'd B, as revised through Amendment No. 41, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8003110 N 7
. 3.
This license amendment is effective as of the date of its issuaace.
FOR THE NUCLEAR REGULATORY COMMISSION Wr.yzeb Thom'at A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical.
Specifications Date of Issuance:
February 22, 1980 I
ATTACHMENT TO LICENSE AMENDMENT NO. 41 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Revise Appendix A as follows:
Remove Insert 203 203 203a 205 205 208a (correct an admin, error in Amendment 40) i
LIMITING CONDITIONS FOR OPERATION SURVEILTANCE REQUIREMENTS 2.
Tha SRM shall have a minimum Spiral Reload of 3 cps except as specified in During spiral reload, SKK operability 3 and 4 below.
will be verified by using a portable external source every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until 3.
Prior to spiral unloading, the SRM's shall have an initial the required enount of fuel is loaded count race of > 3 cps. During to maintain 3 cps. As an alternative to the above, up to two fuel assemblies spiral unloading, the count will be loaded in different cells rate on the 52M's may drop containing control blades around each below 3 cps.
SRM to obtain the required 3 cps.
Until these assemblies have loaded, 4.
During spiral reload, each cor t?.ol cell shall have at the cps requirement is not necessary.
least one assembly with a minimum exposure of 1000 MWD /t.
C.
Spent Fuel Pool Water Level C.
Spent Fuel Pool Water Level Whenever irradiated fuel is stored in Whenever irradiated fuel is stored in the spent fuel pool, the pool water level the spent fuel pool, the water level shall be maintained at or above 33 feet.
shall be recorded daily.
D.
Multiple Control Rod Removal D. Multiple Control Rod Removal Iny number of control rods and/
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the start of or control rod drive mechanisms l
removal of control rods and/or control rod drive mechanisms from the core and/
may be removed from the reactor pressure vessel provided that at or reactor pressure vessel and at least least the following requirements once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until all are satisfied until all control control rods and control rod drive rods and control rod drive mech-mechanisms are reinstalled and all anisms are reinstalled and all control rods are fully inserted in the control rods are fully inserted core, verify that:
in the core.
The reactor mode switch is a.
The reactor mode switch is operable a.
operable and locked in the and locked in the Refuel position Refuel position per Specifi-per Specification 3.10.A.
cation 3.10.A, except that the Refuel position "one rod out" interlock may be bypassed, as y
required, for those control g
rods and/or control rod drive mechanisms to be removed, i
g 4
after the fuel assemblies 5
have been removed as specified i below jf b.
The SRM channels are operable per f:
b.
The source range monitors (SRM)-
Specification 3.3.3.4 are operable per Specification !
3.3.B.4.
c.
The Reactivity Margin requirements l
of Specification 3.3. A.1 are satisfied.
c.
The Reactivity Margin require-1 203 ments of Specification 3.3.A.1 are satisfied.
LIMITING CONDITIONS FOR OPERATION l
SURVEILLANCE REQUIREMENTS d.
All control rods in a 3x3 d.
All control rods in 3 x 3 array array centered on each of centered on each of the control rods the control rods being removed or being removed are fully removed are fully inserted inserted and electrically or hydrauli-and electrically or hydrauli-cally disarmed, or have the cally disarmed, or have the surrounding four fuel assemblies surrounding four fuel assem-removed.
blies removed from the core cell.
e.
All other control rods are e.
All other control rods are fully fully inserted.
inserted.
f.
The four fuel assemblies are I f.
The four fuel assemblies surrounding removed from the core cell I
each control rod and/or control rod I
drive mechanism that is to be removed surrounding each control rod or control rod drive mech-from the reactor vessel at the same anism to be removed from the time are removed from the core and/or core and/or reactor vessel.
l reactor vessel.
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203a Amendment No. 41 i
l
1 3.10 RASES R.
Core Monitoring The SRM's are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and station startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that quadrant during such alterations. The requirement of 3 counts per second provides l
assurance that neutron flux is being monitored and insures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
l The limiting conditions for operation of the SRM subsystem of the Neutron Monitoring System are derived from the Station Nuclear Safety Operational Analysis (Appendix C) and a functional analysis of the neutron monitor sg d
system. The specification is based on the Operational Nuclear Safety Re-quirements in subsection 7.5.10 of the Safety Analysis Report.
C.
Spent Fuel Pool Water Level To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established.
The minimum water level of 33 feet is established because it would be a significant change from the normal level (-l foot) and is well above the level to assure adequate cooling.
D.
Multiple Control Rod Removal These specifications ensure that maintenance or repair of control rods or rod drives will be persormed under conditions that limit the probability of inadvertent criticality. The requirement that the fuel assemblies in the cell controlled by the control rod be removed from the reactor core before the interlock can be bypassed e
insures that withdrawal of another control rod does not result in inadvertent criticality. Each control rod essentially provides reactivity control for the fuel assemblies in the cell associated with the control
>3.
Thus, removal of an entire cell (fuel assenblies plus control rod) results in a.over reactivity potential of the core.
4.10 BASES A.
Refueling Interlocks Complete functional testing of all refueling interlocks before any refueling outage will provide positive indication that the interlocks operate in the situations for which they were designed. By loading each hoist with a weight equal to the fuel assembly, positioning the refueling platform, and with-drawing control rods, the interlocks can be subjected to valid operational tests. Where redundancy is provided in the logic circuitry, tests can be performed tc assure that each redundant logic element can independently perfers its functins.
B.
Core Monitoring Requiring the SRM's to be functionally tested prior to an; core alteration assures that the SRM's will be operable at the start of that alteration.
The daily response check of the SRM's ensures their continued operability.
205 Amendment No. 41
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-6.4 TRAINING A.
A retraining and replacement training program for the facility staff shall be maintained under the direction of the Pilgrim Station Manager.
B.
A retraining program for the licensed operators shall be maintained under the direction of the Senior Nuclear Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55.
C.
A training program for the Fire Brigade shall be maintained under the direction of the Fire Protection and Prevention Officer and shall meet or exceed the requirements of Section 27 of the NFPA Code 1975. Training sessions will be held quarterly.
Amendment No.
41 208a
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