ML19309E084
| ML19309E084 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/14/1980 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19309E077 | List: |
| References | |
| NUDOCS 8004180366 | |
| Download: ML19309E084 (2) | |
Text
A
-Sa-lh
- 2. (cont.)
C. (cont.)
Paragraphs 3.1.1 through 3.1.11 and 3.13 through 3.18 l
of the NRC's Fire Protection Safety Evaluation Report on the Trojan Nuclear Plant dated Fbrch 22, 1978.
These modifications shall be completed by the end of the second refueling outage of the Trojan facility and prior to return to operation for Cycle 3.
In addition, the licensee shall submit the additional information identified in Table 3.2 of this Safety Evaluation Report in accordance with the schedule contained therein.
In lieu of performing the modification identified in Para-graph 3.1.12, an automatic fire suppression system will be installed in the cable spreading room and required control room cabinets to prevent cable spreading room and control room cabinet fires from affecting a safe shutdown capability.
The cable spreading room fire suppression system will be complete by November 1, 1980 and the suppression' system for the control room cabinets will be installed by startup of Cycle 4.
In the event these dates for submittal cannot be met, the licensee shall submit a report explaining the circumstances, together with a revised shedule.
(9) Primary Shielding Modification The licensee is authorized to modify the primary shielding design as described in PGE letter dated April 22, 1977, as supplemented and amended by letters dated September 22 and 23,1977, December 22, 1977, January 4 and 24,1978, Fbrch 20, and April 4,1978.
(10) Control Building (a) Upon the effective date of this amendment (Amend-ment No. 35), and until further Order of the Atomic Safety and Licensing Board issued in conjuction with the decision on the scope and timeliness of modifica-tions from a safety standpoint required by the Order for Modification of License' dated !by 26, 1978, Facil-ity Operating License No. NPF-1 is modified by waiver of those portions of Technical Specification 5.7.1 and the FSAR criteria referenced therein which are not com-plied with because of the identified design deficiencies in the Control Building shear walls, including:
(i) the requirement that the Control Building meet an OBE capacity of 0.15g using 2% damping as required by FSAR Table 3.7.1; Amendment No. 22,29,35 Date of Issuance:
December 22, 1978 8004180
r a
f l
6.0 ADMINISTRATIVE CONTROLS l
6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
The minimum shift crew necessary for safe shutdown is five.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two license Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Crigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
l TROJAN-UNIT 1 6-1 Anendment No. 18
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL 1
1*
OL 2
1 Non-Licensed 3
1
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling supervising CORE ALTERATIONS after the initial fuel loading.
- Shift crew composition may be 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 taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
i t
e TROJAN-UNIT 1 6-4
.