ML19337A644
| ML19337A644 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/08/1978 |
| 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 8009290367 | |
| Download: ML19337A644 (4) | |
Text
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December 8, 1978 6.0 ADMINISTRATIVE CONTROLS O
6' atsao"stsi'n' The Station Superintendent shall be responsible for overall operation
%6 6.1.1 of the Millstone Station Site while the Unit Superintendent shall be respon-sible for operation of the unit. The Station Superintendent and Unit Superin-l56 tendent shall each delegate in writing the succession to these respor.sitilities during their absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown in Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
Each on duty shift shall be composed of at least the minimur:
a.
shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control roo-wher. fuel is in the reactor.
1 At least two licsnsed Operators shall be present in the c.
control room during reactor start-up, scheduled reactor shutdow.
and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
All CORE ALTERATIONS after the initial fuel loading shall be e.
directly superviseo'by either a licensed Senior Reactor Operator or Sraior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of 3 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the Unit (2 members) or any personnel required for other essential functions during a fire emergency.*
eM 6.3 FACILITY STAFF QUALIFICATIONS a
a 6.3.1 Each member of the facility staff shall meet or exceed the minimum for comparable positions, except for (1) l qualifications of ANSI N18.1-1971 a
the Health Physics Supervisor wh6 shall meet or exceed the qualifications of Q
Regulatory Guide 1.8, Revision 1, and (2) the Shift Technical Advisor who C
shall have a Bachelor's Degree or equivalent in a scientific or engineering J
discipline with specific training in plant design, and response and analysis
.O of the plant for transients and accidents.
- To be effective by March 1,1978 Amendment No. JA, M. (#, 56 6-1
e October 28, 1075 TABLE 6.2-1 MINIM 0M SHIFT CREW COMPOSITION APPLICABLE MODE 5 LICENSE CATEGORY
- 1. 2 &
3
4 & 5**
1 1*
$0L 2
1 OL 2
1 Non-Licensed 1
None Required Shift Technical Advisor
- Does not include the licensed Senior Reactor or Senior Reactor Operator Lir.ited to Fuel Handling individual supervision CORE ALTERATIONS after the l
initial fuel loading.
5hif t crew composition may be less than the minimum requirements for a period i
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 /> to accommodate injury or sickness occurring to on duty shift crew members.
- Reactor Mode Switch Position is in RUN (any average coolant temperature)
STARTUP/ HOT STAT;08.Y (any average coolant temperature), and NOT SHUTDOWN (average coolant temperature greater than 212'F). respectively.
- eactor Mode Switch Position is in SHUTD3WN (average coolant temperature Rless than 212*F) and REFUELING (average coolant temperature less than 212*F),
respectively.
e G
e a
Amendment No.
44 6-4
~
a MILLSTONE NUCLEAR POWER STATION. UNIT NO. 1 DISCUSSION OF TMI TECHNICAL SPECIFICATION CHANGES (i) Regarding the model specifications for isolatier actuation instrumenta-tion, existing Technical Specification or procedural requirements provide adequate assurance of the operability of these systems.
Certain parameters identified in the model specifications are currently not a part of the Millstone Unit No.1 design.
(2) Regarding the model specifications on accident monitoring instrumentation, NNEco has previously docketed its respense by Reference (9).
(3) Regarding the model specifications for containment isolation valves, existing specifications adequately require their operability.
It is noted that ro metnod of testing the excess flow check valves during normal operation exists.
(4) The matters of the STA and the license conditions were discussed in the forwardita letter.
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