ML20003A525
| ML20003A525 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png (DPR-45-A-022, DPR-45-A-22) |
| Issue date: | 01/16/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003A523 | List: |
| References | |
| NUDOCS 8102040211 | |
| Download: ML20003A525 (7) | |
Text
gf UNITED STATES NUCLEAR REGULATORY COMMISSION 3
o WASHINGTON, D. C. 20555 y
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DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LACROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 22 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated September 12, 1980, 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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and sarety 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 connon defense and security or to the health and safety of the public; I
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 Speci-fications 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:
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i (2) Technical Specifications The Technical Specifications contained in Appendix A issued October 21, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 22, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 16, 1981
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 22 LACROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE N0. DPR-45 Revise Appendix A by replacing the following pages with the enclosed i
pages. The revised pages are identified by the captioned amendment j
number and contain marginal lines indicating the areas of change.
Remove Insert 36 35 36b 36a*
47 47 52 52 s
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- There is no change.to'the provisions contained on this page.
It is-l included only for pagination. purposes.
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. 4.2.6.7 During operation in the nuclear instrument power range, at least three of nuclear channels 5, 6, 7, and 8 and their automatic gain control sub-system channels shall be in operation. Whenever a channel is deliberately made inoperative, its scram contacts shall be placed in the trip position.
4.2.6.8 Safety channels directly backed up by'an identical channel or channels, performing the same safety function may be bypassed for maintenance.
Safety channels in the partial scram circuit may be bypassed for maintenance provided that the reactor shall be brought to a condition under which the channel protection is not required if the bypass cannot be removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.2.6.9 Both reactor forced circulation pumps shall be automatically shut down by a high reactor pressure signal or by a low reactor water level signal.
Bases - The RPTS is a diverse and independent backup except for common current sensing loops to the normal scram system for rapid shutdown of the reactor.
To protect the primary system from an ATWS event in which either MSIV closes at power, thus eliminating the main condenser as a heat sink, the recirculation pumps must be shut down to prevent damage to the primary system. A rapid shut down of the recirculation pumps has the effect of causing an increase in the moderator. voids in the reactor core.
A substantial negative reactivity results and the power and pressure surges that might otherwise occur in the most limiting transient (MSIV closure) are substantially reduced.
With the recirculation pumps shut down, the reactor power will be reduced to a steady state power level of less than 20% (based on natural circulation through the core).
4.2.7 Waste ';isposal i
- 4. 2. 7.1 All liquid waste system radioactive effluents shall be batch-sampled i
and analyzed prior to release.
4.2.7.2 Disposal of the radioactive gaseous waste shall be through the stack, with at least one stack blower in operation.
The discharge rates shall not exceed the limits in the following chart.
The maximum permissible concentra-(
tions (MPC in micro-curies per ml) shown in this chart are for individual isotopes and mixtures lis,ted in Column 1, Table II, Appendix 8 of 10 CFR 20.
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Change No. J, 2, Amendment No. 22 l
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TWO-BLOWER OPERATION C1umn 1 Column 2 Column ^_
Maximum curies per second Curies per second to be Type of Activity to be released released, avo. over 1 yr.
~ Particulate matter and halogens with half lives longer than 8 days 5.1 x 103 x MPC 5.1 x 102 x MPC All other radioactive isotopes 3.4 x 106 x MPC 3.4 x 105 x MPC II.
ONE-BLOWER OPERATION Particulate matter and halogens with half lives longer than 8 days 2.4 x 103 x MPC 2.4 x 102 x MPC All other radioactive isotopes 1.6 x 106 x MPC 1.6 x 105 x MPC i
Amandment No. 22
-. Channels Action Mininum Frequency 22.
CRD accumulators low gas Test Prior to each plant startup if pressure scram relay test has not been performed within 30 days.
Check pressure Weekly indication
- 23. Turbine stop valve Test Prior to each plant startup if test has not been performed within 30 days.
24.
Reactor Pressure (RPTS)
Calibration At each refueling shutdown
- 25. Reactor Water Level Calibration At each refueling shutdown (RPTS)
- Test shall include tripping of the scam relays K-ll4.
5.2.16 Corrosion test coupons shall be inserted in tne forced circulation loop to evaluate the corrosion deterioration of chromium-molybdenum piping; and that piping shall be replaced if the reduction in pipe wall thickness, as indicated by weight loss and netallographic evaluation of the test coupons, is greater th'an 0.190 inches.
The replacement piping shall be stainless steel or shall be clad internally with stainless steel and shall meet the design -
requirements of Section 2.3.2.
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l Amendment 30. 22
Table 1 - Operating Limits (Cont'd)
Keysvitch Bypass Item Ho.
Condi tior.
Channel or Sensor Cet Point
. Action Provisions 17 off-gas holdup radiation monitor
< gaseous activ-diversion tank effluent ity levels which effluent gas a
activity high correspond to to the storage Column 2 of the tanks limitations given in Sec.
4.2.7.2 18 reactor buildi..g radiation monitors f, radiation closure of none levels which ventilation ventilation correspond to dampers exhaust Column 2 of the lir.1 cations giver in Sec. 4.2.7.2 e
19 simultaneous low pressure transmitter 25-30 psig and opening of dia-f3 reactor pressure and water level y,12 in. below phragm valve
.and low water safety channel 1 or 2 nominal indicated allowing water level to flow directly level from overhead storage tank to l
core spray nozzles 20 nlauitaneous high reactor building f,5 psig and opening of motor reactor building pronsure trancmittor f_ 12 in, below operating valves l
pressure and 1 or 2 and reactor nominal indi-and start of engine reactor low water water Invn1 nafety cated level driven pumps of low 1cvel channel 1 or 2 pressure coolant in-jection system 21 high reactor 3 reactor pressure f_ 1350 psig or trip of both recirc-l[
pressure or low or 3 reactor level
< 30 inches below ulation pump breakers
-reactor water transmitters nominal indicated s
j d[
level level.
the protective function
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can be bypassed whenever the reactor is shutdown
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or recirculation pump o
operation is required s.
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for safety reasons.
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