ML20126E502
| ML20126E502 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/07/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126E490 | List: |
| References | |
| NUDOCS 8506170099 | |
| Download: ML20126E502 (7) | |
Text
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UNITED STATES
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7, NUCLEAR REGULATORY COMMISSION b
wAsmNGTON, D. C. 20655
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DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR DOCKET N0. 50-409 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 43 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (thelicensee)datedSeptember 29, 1982, 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;
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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 Comission's regulations and all applicable requirements have been satisfied.
8506170099 850607 ADOCK 050 g 9 DR e
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.. 2.
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 Provisional Operating License No. DPR-45 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 43, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGULATORYC0yISSIdN f
J John
. Zwolinski, Chief Opera ing Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 7, 1985.
ATTACHMENT TO LICENSE AMENDMENT N0.43 PROVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET NO. 50-409 Revise Appers'x A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 6
6 30g 30g 30h 301
, (1) A pump shall not be capable of being started unless its suction valve is fully open and its discharge valve is fully closed.
(2) A pump shall automatigally be tripped upon full closure of its pump suction valve.
(3) Interlocks shall cause pump speed to increase autcmatically upon startup to a minimum set speed of 34 percent of full-rated speed and shall then prevent pump operation below this minimum speed.
(4) Increase in pump speed shall be prevented when the rod control switch is in the withdrawal position.
(5) On reactor scram, each pump shall be run back automatically to a set speed which is sufficiently low to prevent pump cavitation, but which is greater than 34 percent of full rated speed.
2.4 REACTOR AUXILIARY SYSTEMS 2.4.1 Deleted 2.4.2 Shutdown Condenser System 2.4.2.1 A shutdown condenser. system capable of condensing 61,000 lb/hr of steam at 1365 psig shall be provided.
2.4.2.2 The shutdown condenser system shall normally be isolated from the reactor by air-operated automatic control valves.
Upon abacrmal conditions as specified in items 3, 9, and 10 in Table 1, these valves shall open automaticclly and shall cause the system to function; and these valves shall close automatically when the abnormal conditions have been corrected.
This ' action shall be subject to manual override.
2.4.2.3 Redundant steam inlet valves to the condenser shall open i= mediately on receipt of the actuating signal, and redundant condensate return valves from the condenser shall open approximately 10 sec later.
The steam inlet valves shall be capable of manual positioning, and the condensate return valves shall be capable of manual opening.
Amendment No. 43
REACTOR COOLANT SYSTEM SAFETY VALVES LIMITING CONDITION FOR ODERATION 4.2.2.5 At least two reactor coolari system safety valves shall be OPERABLE with lift settings within f,1% of the set pressure:
1 Safety valve with a set pressure of 1390 psig, and 1 Safety valve with a set pressure of 1390 or 1426 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3*.
ACTION:
With one or both of the above required reactor coolant system safety valves inoperable, either restore the inoperable valve to operable status, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- Except during performance of primary system hydrostatic or leak tests.
SURVEILLANCE REOUIREMENTS 5.2.2.5 The reactor coolant safety valves shall be demonstrated OPERABLE by verifying the set pressure in accordance with the schedule and requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, with Summer 1975 addenda.
I I
6 30g Amendment No. /6, /,43
REACTOR COOLANT SYSTEM BASES 4.2.2.5 SAFETY VALVES The safety valves are designed to meet the requirements of the ASME Boiler and Pressure Vessel Code. The reactor primary system overpresstri:ation protection is sufficient to limit the pressure within the pressure-retaining boundaries to less than 1540 psig, which is less than 110% of the vessel design pressure of 1400 psig.
The safety valves have a minimum stamped relieving capacity of 294,612 lb per hour at a relief pressure of 1390 psig and 302,160 lb per hour at a relief pressure of 1426 psig. Three safety valves are installed. The relieving capacity with one valve inoperable is sufficient to limit the primary system pressure to less than 110 of the vessel design pressure during an abnormal limiting transient with the highest pressure, which is the MSIV closure. A high pressure scram is initiated at 1340 psia and no credit is taken for the MSIV closure scram signal, the power-flow scram, the overpower scram nor~ the pressure reduction due to automatic operation of the shutdown condenser heat sink.
During a normal most limiting pressure transient caused by a main steam isolation valve closure and full scram from 100% power, reactor pressure would not reach 1390 psig, the lowest safety valve set point. The safety valve function is therefore not expected to be required under the most limiting operational transient.
The testing frequency applicable to the safety valve function is provided to ensure operability and demonstrate reliability of the valves. The required testing interval varies with observed valve failures.
Set point drift within
+ 3% of the setpoint is not considered to be valve failure for the purposes of this test schedule. Setpoint drift > + 3% of the setpoint will be cause to test additional valves in accordance with ASME Section XI test schedule. The popping setpoints are significantly below the 110% primary system design pressure safety limit. Therefore, adequate margin exists between the setpoint and the safety limit of 1555 psia.
For the purposes of establishing the test frequency, a valve shall be considered to have failed to function properly if the test relief pressure is determined to be outside of the a12- -ble setpoint tolerance specified in the ASME Code to which the valve was icted.
For the LACBWR spring loaded valves which are constructed to t.
." Code Section VIII, 1962, and Nuclear Code Case N-1271, 1962, and which m.. ae removed from the primary steam system to conduct the test, the allowable setpoint tolerance is + 3% of the set pressure.
However, when the safety valve relief pressure is set prior to installing the valve on the reactor system, the maximum deviation of the test relief pressure from the specified set pressura shall not exceed + 1.0% of the required set pressure.
30h Amendment No. 43
1 t
l 4.2.2.6 At least one forced circulation loop shall be non-isolated, i.e.
suction and discharge valves open, anytime the shutdown condenser is operating,,or the Reactor Building. Main Steam Isolation Valve (MSIV) and the Turbine Building MSIV are non-isolated.
4.2.2.7 The suction, discharge, and discharge bypass valves of the forced circulation pumps shall operate as described in Section 2.3.3.4.
1 h
pf,7, 43 301 Amendment
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