ML19337A638
| ML19337A638 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/30/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19337A626 | List: |
| References | |
| TASK-2.E.1.1, TASK-2.E.1.2, TASK-TM TAC-11733, NUDOCS 8009290362 | |
| Download: ML19337A638 (3) | |
Text
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e ADMINISTPATIVE CONTROLS
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6.3 FACILITY STAFF QUALIFICATIONS _
Each member of the facility staff shall meet or exceed 6.3.1 the minimum qualifications of ANSI N18.1-1971 for comparable l
positions.
6.3.1.1 The position of llealth Physics Supervisor shall meet the following minimum qualifications:
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i Academic degree in an engineering or science field or a.
equivalent as p,er Section 6.3.1.1.c.
b.
Minimum of five years professional technical eicperience in the area of radiological safety, three years of which shall be in applied radiation work in a nuclear facility dealing with problems simi.1Lar to those encountered in a nuclear power reactor.
i, Tecnnical experience in the area of radiological safety c.
beyond the five year minimum may be substituted on a one-for-one basis towards the academic degree requirement l'
(four years of technical experience being equivalent to a four year academic degree).
d.
Academic and technical experience must total a minimum
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of nine years.
6.3.1.2 The position of the Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
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TRAINING l
6.4.1 A retraining and replacement training program for the facility staf f shall be maintained under the direction of the Training Coordinator assigned progrcm responsibility and shall be in accordance with Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
i 6.4.2 A fire brigade training program shall be maintained under the direction of the training department'and shall meet or exceed the intent of Section 27 of the NFPA Code-1976 except that drills / training shall be conducted at least quarterly.
The effective date of this specification is March 1, 1978.
6.5 REVIEW AND LUDIT 6.5.1 PLANT OPERATIr"C REVIEW COFDtITTEE (PORC)
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f FUNCTION 6.5.1.1 The Ponc shall function to cdvise the Station Superintendent on all matters related to nuclear safety..
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TABLE 6.2-1 MINIMUJ SHIFT CREIJ COMPOSITION Personnel Number Condition Category Required of Unit
- SOP 1
Normal Operating R0P 2
Condition Except AOP 2
Cold Shutdown STA 1
Cold Shutdown
- SOP 1
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Conditions ROP 1
AOP 2
'Ab'brev'1ations: SOP - Licensed Senior Reactor Operator
_, ROP -, Licensed Reactor Operator AOP - Additional Operator
- pualified in Radiation Protection Procedures
- Shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members,provided immediate action is tsken to restore the shift crew cowposition to within the minimum requirements of Tabic 6.2-1.
This provision Jpes not permit any shif t crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
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i HADDAM NECK PLANT DISCUSSION OF TMI TECHNICAL SPECIFICATION CHANGES (1) The issue of auxiliary f eedwater systems is discussed in the forwarding letter.
(2) The section on accident monitoring instrumentation is not being proposed a*. this time.
It is noted that Referenr.e (1) proposes the add'.cion of instruments li through 18 to an existing table.
The first ten instruments are not currently a part of the Haddam Neck Plant Technical Specifications.
It would be inconsistent to incorporate the TMI-related items in'.o the Technical Specifications, in the absence of the other parameters. Use of these instruments is adequately and appropriately addressed in plant operating procedures. Furthermore, many of these parameters are not of immediate importance to saf ety as discussed previously.
(3) The model specifications regarding the FORV's have been customized for the Haddam Neck Plant Technical Specifications. No substantive changes from the model are proposed.
(4) An LCO for the pressurizer is being proposed. A value of 150 Kw of pressurizer heater capacity has been previously established to be adequate to ensure natural circulation in the hot standby condition.
A value of pressurizer water level is not being proposed. Additional evaluation is required to develop meaningful values in consideration l
of providing a reasonable operating band which is compatible with accident analysis assumptions. The absence of the model bases to address the questien of pressurizer level is an additional reason for this segment of the LCO to be unaddressed at this time.
(5) Specifications for containnent isolation valves are being proposed; the LCO is consistent with the model specifications. The valves identified are those which close upon receipt of a CI signal.
There is no need to distinguish between parameters which initiate isolation as all valves close upon either a CI signal or safety injection signal. The design of the circuits associated with these systems is such that they occur simultaneously.
No other parameters are used to initiate C1.
(6) The matters of the STA and the license conditions were discussed in the forwarding letter.
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. DOCKET NO. 50-245 ATTACHMENT 2 i
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS TMI-RELATED REQUIREMENTS 1
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i SEPTEMBER, 1980 i
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