ML19332B239
| ML19332B239 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/09/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332B240 | List: |
| References | |
| NUDOCS 8009260331 | |
| Download: ML19332B239 (6) | |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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'o, UNITED STATES
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h NUCLEAR REGULATORY COMMISSION 3
- j WASHINGTON, D. C. 20555 g.....,/
TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No, DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensed) dated August 26, 1980, as supplemented by letter dated August 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense 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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-68 is hereby amended to read as fol?ows:
(2) Technical Specifications The Technical Specificatinns contained in Appendices A and B, as revised through Amendment No.34, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
800926033(
. 3.
This, license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
Q I
Thomas K.rIppolito, Chief
~
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septenber 9,1980 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. DPR-68 D_0CKET NO. 50-296 4
i Revise Appendix A as follows:
1.
Remove the following pages and replace with the identically numbered i
pages:
156 157 171 2.
Marginal lines on each page indicate the revised area.
1 i
e 4
9 4
9 1
9
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I LIMITING CONDITIONS FOR OPERATION
' SURVEILLANCE REQUIREMENTS sr COOEItiG SkbIhhh
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- 4. 5 CORE AND CO;7tAIMMENT COOLING
- 3. 5 CORE AND CONTAlgEST
~
SYSTEMS 2.
During reactor power 2.
a.
If no more than operation, RRRSW two RHRSW pumps pumps must be are inoperable, operable and assigned increased to service as surveillance is indicated below for not required.
the specified time limits.
b.
When three RHRSW pumps are inoperable, the I
TIME MINIMUM remaining pumps, LIMI T SERVICE ASSIGUMENT associated (DAYS)
RERSW EECW**
essential control valves, Inde finite 7*
3*
and associated e
diesel
' $,3 0 7
- or 6 * *
- 2* or 3***
generators shall be operated 7
6*
2*
weekly.
c.
When four RHRSW
inoperable, the remaining pumps,
- only automatically starting pumps associated 1
may be assigned to EECW header essential service.
control valves, and associated
- Nine pumps must be operable.
diesel Either configuration is acceptable:
generators shall
/f, j 7 and 2 or 6 and 3.
be operated j
daily.
)
g1 3.
During power operation, both RHRSW 3.
Routine surveillance
{
pumps B1 and B2 for these pumps is
- normally or specified in 4.5.C.1.
alternately assigned to the RilR heat exchanger header supplying the standby coolant supply connection must be operable; except as specified in 3.5.c.4 I
and 3.5.C.5 below, i
r' 156
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0" Amendment No. 34 ed o
i
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 4. 5 CORE AND CONTA,I1 DENT OJCMlig j
3.5 CORE AND cot?TAINMENT SYSTEgS COOLING __ SYSTEMS 4.
One of the B1 or B2 4.
When it is determined RHRSW pumps assigned t that the B1 or B2 the RHR heat exchanger RHRSW pump is supplying the standby inoperable at a time coolant supply connection when operability is may be inoperable for a required, the operable RHRSW pump period not to exceed on the same header 30 days provided the and its associated operable pump is diesel generator and aligned to supply the the RHR heat RHR heat exchanger exchanger header and header and the associated essential associated diesel control valves shall generator and be demonstrated to be essential control operable immediately valves are operable.
and every 15 days thereafter.
5.
The standby coolant supply capability may be inoperable for a period not to exceed ten days.
6.
If specifications 3.5.C.2 through 3.5.C.5 are not met, an orderly shutdown shall be initiated a,nd the unit placed in the cold shutdcun condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 7.
There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.
157 Amendment No. 34
H 3.5 BASES R EFEREt:C ES 1.
Residual Heat Removal System (BFNP FSAR subsection 4.8) 2.
Core Standby Cooling Systems (BFHP FSAR Section 6)
C.
RHR Se rvice Wa ter System and Emeroency Ecu'ipment Coolina Water System (EECWS)
There are two EECW headers (north and south) with four automatic starting RHRSW pumps on each header.
All components requiring emergency cooling water are fed f rom both headers thus assuring continuity of operation if either header is operable.
Each header alone can handle the flows to all components.
Two RERSW pumps can supply the full flow requirements of all essential EECW loads for any abnormal or postaccident situation.
There are four RHR heat exchanger headers (A, B, C, D) with one RHR heat exchanger f rom each unit on each header.
There are two RHRSW pumps on each header; one normally assigned to each header (A2, B2, C2, or D2) and one on alternate assignment (A1, B1, C1, or D1).
One RHR heat exchanger header can adequately deliver the flow supplied by both RERSW pumps to any two of the three RHR heat exchangers on the head er.
One RHRSW pump can supply the full flow requirement of one RHR heat exchanger.
Two RHR heat exchangers can more than adequately handle the cooling requirements of one unit in any abnormal or postaccident situation.
The RHR Service Water System was designed as a shared system for three units.
The specification, as written, is conservative when consideration is given to particular pumps being out of service and to possible valving arrangements.
If unusual operating conditions arise such that more pumps are ou t of service than allowed by this specification, a special case request may be made to the NRC to allcw continued operation if the actual system cooling requirements can be assured.
Should one of the two RHRSW pumps normally or alternately assigned to the RHR heat exchanger header supplying the standby coolant supply connection become inoperable, an equal capability for long-term fluid makeup to the unit reactor and for cooling of the unit containment remains operable.
Because of the availability of an equal makeup and cooling capability which is demonstrated to be operable immediately and with specified subsequent surveillance, a 30-dry repair period is iustified. Should the capability to provide standby coolant supply be lost, a 10-day repair time is justified based on the low probability for ever needing the standby coolant suppig.
Amendment No. 34 171