ML20154S470
| ML20154S470 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/27/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154S469 | List: |
| References | |
| NUDOCS 8604010254 | |
| Download: ML20154S470 (6) | |
Text
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UNITED STATES g
o,,f NUCLEAR REGULATORY COMMISSION g
4 E WASHINGTON, D. C. 20555
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DAIRYLAND POWER COOPERATIVE DOCKET N0. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 47 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated December 12, 1985 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 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 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 reqJirements have been satisfied.
8604010254 e60327 PDH ADOCK 05000409 P
. 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. 47, 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 l0MMISSION i
M w
John
\\. Zwolinski, Director BWR P)oject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27,1986 l
ATTACHMENT TO LICENSE AMENDMENT N0.47 PROVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET N0. 50-409 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned anendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 16 16 33 33 34 34 4
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' 2.7.3 Control Rods i
2.7.3.1 Twenty-nine movable control rods shali be provided as shown in Figure 1. Coolant flow past the control rods shall be guided by the control r
rod channels formed by the fuel shrouds and by 52 vertical posts made of zirconium alloy.
2.7.3.2 The control rods shall be of cruciform shape and shall conform to either the Allis-Chalmers (A-C) tube-sheath desige or the ASEA-ATOM (AA) plate design with norizontally drilled absorber holes. The neutron absorber section of each control rod shall have a nominal length of 83 inches.
2.8 CONTROL ROD DRIVE SYSTEM 2.8.1 Twenty-nine drive mechanisms shall operate the control rods over a minimuc travel range of 82 in. and shall fix their position in the reactor as required. Individual rad positions derived from synchro pairs and from reed switches shall be indicated continuously.
2.8.2 Each control rod shall be connected to a put.h rod by a positive latch, j
and the push rod shall be moved and positioned vertically by means'of a roller l
nut assembly and a leadecrew which shall be rotated by an electric motor. All i
rod motion shall be accomplished against a mechanical brake which maintains the rod in position when the drive motors are not operating. Interlocks shall prevent withdrawal of more than one rod at a time and shall prevent control.
rod withdrawal while the speed of either of the forced-circulation pumps is increasing.
2.8.3 A hydraulic motor on each drive mechanism shall cause the control rod to be rapidly driven upward upon receipt of a scram signal until it is fully inserted in the core. The electric drive motor on each drive archanism shall independently drive the control rod into the reactor core upon receipt of a scram signal if the hydraulic motor fails to do so.
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Amendment No. dd,47 f
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4.2.4.3 Deleted 4.2.4.4 The reactor shall not be operated at a power level above 1 Mwt with less than 72 fuel assemblies installed in the reactor.
4.2.4.5 The reactor shall have a negative, temperature coef ficient for all moderator temperatures from ambient to 557 F or shall be preheated to obtain a negative temperature coefficient prior to withdrawal of control rods.
4.2.4.6 The core shall be suberitical by a least 0.5% delta k/k in the cold clean condition with the rod of maximum worth in its fully withdrawn position and with all other rods fully inserted.
4.2.4.7 The reactor may be operated with cuatrol rod drives inoperable prosided that the associated rods are secured in the fully inserted or fully withdrawn position by electrically disconnecting the clutch an/ drive member and provided that all other requirements of these specificiatiens are met.
4.2.4.8 If an unexplainable change of greater than 0.6 percent in core reactivity is observed in a core which has undergone no physical change, the reactor shall be shut down.
Except as required to investigate the reactivity change, the reactor shall not be operated until a satisfactory reason for the change has been found.
4.2.4.9 Follouir.g core reloading and/or core rearrangement, operation will be discontinued if the difference between the observed and predicted value of core reactivity exceeds 2 percent. If this difference is exceeded, the effect of the difference on further operation will be evaluated before operation is continued.
Amendment No. AA,47 l
. 4.2.5 Reactor Control 4.2.5.1 The total scram time of each control rod as measured by the rod scram timer shall not exceed 3.0 sec.
4.2.5.2 The control rod configurations used during reactor operation shall be such that the maximum increase in reactivity that would be caused by the complete withdrawal of any one control rod from a critical core would not er.ceed 2.5% celta k/k.
4.2.5.3 The maximum rate at which reactivity shall be increased by movement of control rods when keff of the reactor exceeds 0.99 shall not exceed 18 cents /sec.
4.2.5.4 The maximum rate at which forced circulation flow rate may be increased by changes in forced circulation pump speed shall be 1200 gpm/sec.
4.2.5.5 The reactor shall not be operated above 10-5 of full power unicss at least one forced circulation pump is operating at or above its set minimum speed (34 percent of full rated speed).
4.2.5.6 The speed of the forced circulation pumps shall be controlled manually or automatically by the pressure control system.
l 4.2.5.7 Except during plant startup and shutdown, the main steam bypass valve control shall be set to begin opening the bypass valve at an indicated pressure corresponding to a turbine inlet pressura not more than 15 psi above its nominal value.
4.2.5.8 The rod position indication systems, i.e.,
the synchro pairs, the reed switches, and the limit switches which indicate full rod inserticn or withdrawal, shall be available for indication of individual rod positions, excepc that one of these systems may be removed for maintenance for a time period not exceeding 24 hr.
4.2.6 Safety Instrumentation 4.2.6.1 The safety instrumentation shall provide scram, isolation action, and other safety actions as specified in Table 1 of these specifications.
CMdddd Md. 2, 4 Amendment ho. 47 l
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