ML20237G402
| ML20237G402 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/30/1987 |
| From: | Thomas C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G394 | List: |
| References | |
| NUDOCS 8708240076 | |
| Download: ML20237G402 (12) | |
Text
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UNITED STATES l
E NUCLEAR REGULATORY COMMISSION o
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- j WASHINGTON, D. C. 20555
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i NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 "N'
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. DPR-21 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Northeast Nuclear Energy Company,(thelicensee)datedMay 22, 1987, 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 (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 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 requirements have been satisfied.
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1 8708240076 870730 PDR ADOCK 05000245 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as-follows:
(2) Technical Specifications 1
The Technical Specifications contained in Appendix A, as revised l-
- through Amendment No. 5, are hereby incorporated in the I;
license. The licensee shall operate the facility in accordance i
1.
with the Technical Specifications.
i 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-0bb 0
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1 Cecil 0. Thomas, Director Integrated Safety Assessment Project Directorate Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:. July 30, 1987 l
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4 ATTACHMENT TO LICENSE AMENDMENT N0. 5 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET N0. 50-245 ReviseAppendixATechnicalSpecificationsbyremovingthepagesindentified.
l-below and inserting the enclosed pages. The revised pages are identified by
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the captioned amendment number and contain marginal lines indicating the area j
. of change.
REMOVE INSERT 3/4-4-1 3/4 4-1
~3/4 4-2*
3/4 4-2*
3/4 4-3*
3/4 4-3*
3/4 4-4 3/4 4-4 3/4 4-5 3/44-5(blank) 3/4 4-6 3/4 4-6 B 3/4 4-1 B 3/4 4-1 8 3/4 4-la B 3/4 4-la B 3/4 4-2 B 3/4 4-2 l
- 0verleaf page provided to maintain document cor.,pleteness.
No changes contained on this page.
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l LIMITING CONDITION FOR OPERATION 3.4 STANDBY LIQUID CONTROL SYSTEM 1
l Applicability:
1 Applies t_o the operating status of the standby liquid control system.
Objective:
To assure the availability of the standby liquid control system.
Specification:
A.
Normal Operation During periods when fuel is in the reactor, the liquid poison system shall be operable, except when the reactor is in the COLD SHUTDOWN or REFUEL CONDITION and Specification 3.3.A is met, and except as noted in Specification 3.4.8 below.
SURVEILLANCE REQUIREMENT 4.4 STANDBY LIQUID CONTROL SYSTEM Applicability:
Applies to the periodic testing requirements for the standby liquid control system.
Objective:
I To verify the operability of the standby liquid control system.
Specification:
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A.
Normal Operation The operability of the standby liquid control system shall be verified by performance of the following tests:
1.
At least once per month Demineralized water shall be recycled to the test tank.
Pump j
minimum flow rate of 40 gpm shall be verified against a system head corresponding to a reactor vessel pressure of 1225 psig.
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==nement me.1, 5 Millstone Unit 1 3/4 4-1
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1 SURVEILLANCE REQUIREMENT (Continued) 4.4 STANDBY LIQUID CONTROL SYSTEM 4.4.A.2.
At least once during each operating cycle Manually initiate ora of the two standby liquid control systems a.
and poing demineralized water inf o the reactor vessel at or near operating pressurec.
This test checks explosion of the charge associated with the tested syst em, proper operation of the valves and pump capacity.
The replacement charges to be installed will be selected from thes same batch as those tested.
Both systems shall be tested and inspected, including each explosion valve in the course of two orerating cycles.
b.
Manually initiate cach system, except the explosion valve and pump solution in the recirculation path back to.the storage tank.
c.
Test that the setting of the system pressure relief valves is between 1350 and 1450 psig.
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l LIMITING CONDITION FOR OFEFATION 3.4 STANDBY LIQUID CONTROL SYSTEM B,
Operation with Inoperable Components From and af ter the date that a redundant component is made or found to be inoperable, Specification 3.4.A shall be considered fulfilled, provided that:
1.
The component is returned to an OPERABLE condition within 7 days, or 2.
A written report shall be submitted to the Nuclear Regulatory Commission when the maintenance to restore the component to an operable-condition will last longer than 7 days.
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I-Millstone Unit 1 3/4 4-3
LIMITING CONDITION FOR OPERATION 34 STANDBY LIQUID CONTROL SYSTEM C.
' Boron Requirements The liquid poison tank shall contain a boron-bearing solution that satisfies the following requirements at all times when the liquid poison system is required to be OPERABLE:
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Boron enrichment (atom % B-10) 2 50%, and o
Solution concentration 411 wt%, and o
Solution volume 211,850 gallons, and o
The temperature of the solution, including that in the piping, shall not be less than the temperature presented in Figura:3 4.1.
- D.
Shutdown Requirement If Specifications 3 3;A through C are not met, an orderly shutdown shall te initiated.
SURVEILLANCE REQUIREMENT 4.4 STANDBY LIQUID CONTROL SYSTEM C.
The availability of the proper boron-bearing solution shall be verified ty performance of the following tests.
1.
At least once per month Boron concentration shall be determined.
In addition, the boron concentration shall be determined any time water or boron is added or if the solution temperature drops below the limits specified by Figure 3.4.1.
2.
At least once per day Solution volume shall be checked.
3 At least once per day The solution temperature, including that in the pipir.g, shall be checked.
I 4.
At least once per refueling cycle Boron-10 enrichment shall be deter'ained.
In addition, the. boron-10 enrichment shall be determined within 60 days of adding sodium pentaborate to the tank.
Millstone Unit 1 3/4 4-4 Amendment No. 5 i
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34 STANDBY LIQUID CONTROL SYSTEM BASES A.
Normal Operation The design objective of the liquid control system is two fold. One objective is to provide the capability of bringing the reactor from full power to a cold, xenon-free shutdown assuming that none of the withdrawn control rods can be inserted. To meet this objective, the liquid control sygpem is designed to inject a sufficient quantity of Boron-10 (the boron isotope with the higher neutron absorption cross-section) in less than 125 minutes to bring the reactor from full power to a minimum of 2.6% delta K suberitical condition considering the hot to cold reactivity swing, xenon poisoning, analytical biases and uncertainties, etc. This quantity is equivalent to the quantity of naturally occurring boron which produces a concentration of 660 ppm.
An additional 25% of boron solution is provided for possible imperfect mixing of the chemical solution in the reactor coolant.
A minimum quantity of 1,610 net gallons of 50% B-10 enriened sodium pentaborate in a solution having a concentration of no less than 10 wt% (the higher minimum solution concentration in the LCO accounts for the measurement uncertainty) is required to meet this shutdown requirement. Actral minimum system volume for this quantity is 1,850 gallons.
(240 gallons are contained below the pump suction and, therefore, cannot be inserted.)
The time requirement (125 minutes) for insertion of the boron solution was selected to override the rate of reactivity insertion due to cooldown of the reactor folicwing the xenon poison peak.
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The second objective of the liquid control system is to meet the requirement of the ATWS rule (10CFR50.62) which states that, in part:
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l "Each boiling water reactor must have a standby liquid control system I
(SLCS) with a minimum flow capacity and boron content equivalent in control capacity to 86 gallons per minute of 13-weight percent sodium pentaborate solution."
The equivalency requirement is met by satisfying the following equaticns:
33, M251, C_,
0 E
2: 1 M
13 19.8 Where:
Q=
Flowrato from one SLCS pump, 38 gpm.
(The higher value specified in the LCO accounts for the measurement uncertainty).
Millstone Unit 1 B 3/4 4-1 Amendment No. J, 5 i
o 34 STANDBY LIQUID C011 TROL SYSTEM (con't.)
i BASES 3
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M251 :
The ratio of mass of water in the reactor vessel and M
recirculation system at hot rated conditions for a plant with a vessel diameter of 251 inches to that of Millstone Unit 1.
(This ratio is greater than 1.25).
- C=
Sodium pentaborate solution concentration, 10 wt$ (the higher value specified in the LCO accounts for the measurement uncertainty).
E=
B-10 isotope enrichment, 50 atom percent.
Boron concentration, solution temperature (within the tank and connecting piping including check of tank heater and pipe heat tracing system), and volume are checked on a frequency to assure a high reliability of operation of the system should it ever be required. Experience with pump operability indicates that monthly testing is adequate to detect if failures have occurred. Testing cf B-10 enrichment once per refueling cycle or whenever sodium pentaborate is added to the tank provides sufficient assurance that the minimum B-10 enrichment will be maintained.
Components of the system are checked periodically, as described above, and make a functional test of the entire system on a frequency of less than l
once during each operating cycle unnecessary. A test of one installed explosive charge is made at least once during each operating cycle to assure that the charges are satisfactory. The r6 placement charge will be selected from the same batch as the tested charge.
A continual check of the firing circuit continuity is provided by pilot lights in the control room.
The relief valves in the standby liquid control system protect the system piping and positive displacement pumps, which are nominally designed for 1500 psi, from overpressure. The pressure relief valves discharge back to the standby liquid control solution tank.
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Millstone Unit 1 3 3/4 4-la Amendment No. 2, 5
l 3.4 STANDBY LIQUID CONTROL SYSTEM BASES B.
Operation with Inoperable Components Only one of the two standby liquid control pumping circuits is needed for proper operation of the system.
If one pumping circuit is found to be inoperable, there is no immediate threat to shutdown capability, and redbtor operation may continue while repairs are being made.
C.
Boron Requirements The solution saturation temperature of 13% sodium pentaborate, by weight, is 580F. The solution shall be kept at least 100F above the saturation temperature within the tank and suction piping to guard against boron precipitation. The 100F margin is included in Figure 3.4.1.
Temperature l
and liquid level alarms for the system are annunciated in the control room.
Pump operability is checked on a frequency to assure a high reliability of operation of the system should it ever be required.
Once the solution has been made up, boron concentration will not vary unless more boron or more water is added or removed. Level indication and alarm indicate whether the solution volume has changed which might indicate a possible solution concentration change.
Considering these factors, the test interval has been established.
Minstone Unit 1 B 3/4 4-2 Amendment No. 5 i