ML19323E097
| ML19323E097 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/24/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323E091 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8005220762 | |
| Download: ML19323E097 (5) | |
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UNITED STATES
[ g,(j,,,9 NUCLEAR REGULATORY COMMISSION
- .g WASMNGTON, D. C. 20556 (vowj
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CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. DPR-61 l
l 1.
The' Nuclear Regulatory Comission (the Comission) has found that:
i A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated March 21, 1978, as supported by information submitted by letters dated May 14,1974, April 18, 1980 and April 23, 1980, complies with the standards and require-ments 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 Cor: mission; 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 activit* s will be conducted in compliance with the Comission's repeations; D.
The issuance of this amendment will not be inimical to the co=on defer.:e 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 ratisfied.
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8005220 767_ -
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license Amer.dment and paragraph 2.C(2) of Operating t.icense No. DPR-61 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 35, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.' This licen'se amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-fn. -
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,;tunw Dennis L. Ziemannf/ Chief Operating Reactors Branch #2 i
Division of Operating Reactors
Attachment:
Changes to the Technical Specifications
'Date of Issuance:
April 24,1980
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ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. DPR-61 00CXET NO. 50-213 1
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by the cap-tiened amendment number and contain vertical lines indicating the area of changes.
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REMOVE PAGES INSERT PAGES 3-23 3-23 3-24 3-24*
" he-e are ne changes to the provisier.s contained on this page.
The Technical S:ecifications have.ere:y been recesitiened.
a 3.13 NEFUELING t
Applicability:
Applies to operating limitations during refueling operations.
i obj ective:
To insure that no incident could occur during refueling opera-tions that would affect public health and safety.
Specification:
A.
Radiation levels in the containment and fuel storage building shall be monitored continuously.
8.
Core suberitical neutron flux shall be continuously moni-tored by at least two neutron monitors, each with con-tinuous visual and audible indication available, whenever core geometry is being changed. When core geometry is not
'being dianged, at least one neutron flux monitor shall be in service.
C.
At least one residual heat removal pump shall be in ope ration.
D.
During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shall be maintained at not less than that required to shut down the core to a k off - 0.92 (see Specification 3.11)
E.
One charging pump capable of injecting borated water to the reactor coolant shall be available at all times when changes in core geometry are taking place.
F.
Whenever new fuel is added to the reactor core, a 1/M plot shall be maintained to verify the suberiticality of the Core.
G.
Direct communication between the control room and the refueling cavity manipulator crane shall be available when-ever changes in care geometry are taking place.
H.
Spent fuel casks shall not be handled above the spent fuel pool or 'its edge._except as provided_jn Section 3.13.I, until such time as NRC has received and approved the spent fuel cask drop evaluation.
I.
After April 23, 1980, a spent fuel cask may be brought into the spent fuel building and may be moved into or over the spent fuel pool a total of ten times in order to remove fuel from the pool for study at an off-site laboratory, or to return the fuel from the laboratory to the pool. Moyenent of the spent fuel cask under the provisions of this paragraph is conditioned on compliance [by the licensee] with all commitments made by the licensee in its letter.: to the NRC dated April 18, 1980 and April 23, 1980.
In addition, all fuel within the spent fuel pool shall have decayed for at least 90 days before a spent fuel cask is handled above the pool.
3-23 Amendment No. 7', 35
Basis:
ne equipment and general procedures to be utilized during refueling are discussed in the Facility Description and Safety Analysis.
Detailed instructions will be available for use by refueling personnel. nese instructions, the above-specified precautions, and the design of the fuel handling equipment incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard'to public health and.
s afety. Whenever no change is being made in core geometry, one flux monitor is sufficient. His permits maintenance of the instrumentation. Continuous monitoring of radiation levels (PA" above) and neutron flux provides immediate indication of an tasafe condition. Re residual heat pump is used to
" maintain a daifore boren ~eoncentration. The shutdown margin
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indicated in Part D will keep the core saberitical, even if all centrol rods were withdrawn from the core. Weekly checks of' refueling water boron concentration insure the proper shut-down wrgin. Part C allows the contrci room operator to infore the manipular opeirator of any impending unssfa condition detected from the main control board indicators during fuel movement.
References:
(1)
FDSA Section 5.2.9 (2) FDSA Section 7.4 4
Amendment No. 35 3-24 I: -
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