ML20247E033
| ML20247E033 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 03/23/1989 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E036 | List: |
| References | |
| NUDOCS 8903310275 | |
| Download: ML20247E033 (6) | |
Text
-
..pM**%
p
.f UNITE D STATES y-
- en
~ NUCLEAR REGULATORY COMMISSION
~ f.,
-l WASHINGTON, D. C. 20655 a
%,....../
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION' DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-42
- 1..
The Nuclear Regclatory Comission (the Comission) has found that:
A.
The. application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear.0perating Corporation (the Corporation)',
-dated August 25, 1986 and as supplemented on July 8, 1987, 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 cenformity with the application, as aunded, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the hehlth 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 license amendment will not b6 inimical to the commen defense-and security or.tc the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 JR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
pgsaggg 8s8ggg2 P
L-I' L
I L
, 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendaent and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised-through Amendment No. 28, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION' W
4, db Jose A. Calvo, Director Project Directorate - IV.
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Ch6nges to the Technical Specifications Date of Issuance: March 23, 1989 1
mm_._=________
l ATTACHMENT TO LICENSE AMENDMENT NO.28 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document I
completeness.
I REMOVE PAGES INSERT PAGES 3/4 8-16 3/4 8-16 3/4 8-18 through 45 inclusive B 3/4 8-3 B 3/4 8-3 l
l l
1
\\..
ELECTRICAL POWER SYSTEMS ONSITE POWER DISTRIBUTION SHUTDOWN.
l LIMITING CONDITION FOR OPERATION 3.8.3.2. As a minimum, one of the following divisions of electrical busses shall be energized in the specified manner:
a.
Division 1, consisting of:
1) 4160-Volt Emergency Bus #NB01, and 2)
'480-Volt Emergency Busses #NG01, NG03 and NG05E, and 3) 120-Volt A.C.. Vita 1' Busses #NN01 and NNO3 enargized from their associated inverter connected to D.C. Busses #NK01 and NK03, and 4) 125-volt D.C. Busses #NK01 and NK03 energized from Batteries
- NK11 and NK13 and Chargers #NK21 and NK23, or b.
Division 2, consisting of:
1) 4160-Volt Emergency Bus #NB02, and 2) 480-Volt Emergency Busses #NG02, NG04 and NG06E, and 3) 120-Volt A.C. Vital Busses #NN02 and NN04 energized from their associated inverter connected to D.C. Busses #NK02 and NK04, and 4) 125-Volt D.C. Busses #NK02 and NK04 energized from Batteries
- NK12 and NK14 and Chargers #NK22 and #NK24.
APPLICABILITY:
MODES 5 and 6.
ACTION:
Without one of the above required divisions of electrical busses energi:ed in the required manner, immediately suspend all operations involving CORE ALTERA-TIONS, positive reactivity changes, or movement of irradiated fuel; initiate corrective action to energize at least one division of the required busses in the specified manner.
SURVEILLANCE REQUIREMENTS i
4.8.3.2 The specified busses shall be determined energized in the required l
manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.
1 l
1 l
WOLF CREEK - UNIT 1 3/4 8-15
- . :.: 3 y
ELECTRICAL POWER SYSTEMS
'3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.1 For each containment penetration provided with'a penetration conductor overcurrent protective device (s), each device shall be OPERABLE.
APPLICABILITY: MODES 1,-2,-3, and 4.
ACTION:
With one'or more of the above required containment penetration conductor overcurrent protective device (s) inoperable:
Restore the protective device (s) to OPERABLE status or deenergize a.
the circuit (s) by tripping the associated backup circuit breaker-or racking out.or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the e cted system or component inoperable, and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out,.or removed, at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or removed, or b.
Be in at least HOT STANDBY within t.1e next 6 h'ours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS.
L 4.8.4.1 Protective devices required to be OPERABLE as containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE.
a.
At least once per 18 months:
1)
By verifying that the 13.8 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers, and performing the following:
a)
A CHANNEL CALIBRATION of the associated protective' relays,.
b)
An integrated system functional test which includes simulated-automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed and as specified in Table 3.8-1, and WOLF CREEK - UNIT 1 3/4 8-16 Amendment No.28
T
. ELECTRICAL POWER SYSTEMS f
BASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors'are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance.
The Surveillance Requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker.
Each manufacturer's molded case and metal case circuit breakers are grouped.into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.
If a wide variety exists within any manufacturer's brand of cir-c"uit breakers, it is necessary to divide that manufacturer's breakers.into groups and treat each group as a separate type of breaker for surveillance purposes.
A list of containment penetration conductor overcurrent protective devices whose circuit limiting fault current exceeds the penetration rating, with information;of location and size and equipment powered by the protected circuit, is available at the plant site in accordance with Section 50.71(c) of 10 CFR Part 50.
The addition or deletion of any containment penetration conductor overcurrent protective device would be made in accordance with Section 50.59 of 10 CFR Part 50.
I WOLF CREEK - UNIT I B 3/4 8-3 Amendment No. 28
_ _ - _ _ _ _ _ _ _ _ _ _ - _ -. _ _ _ _