ML20190A105
| ML20190A105 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/11/2020 |
| From: | Michael Wentzel NRC/NRR/DORL/LPL2-2 |
| To: | Jim Barstow Tennessee Valley Authority |
| Michael Wentzel-NRR/DORL 301-415-6459 | |
| References | |
| CAC MF5749 | |
| Download: ML20190A105 (6) | |
Text
August 11, 2020 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 2 - CORRECTION TO AMENDMENT NO. 319 REGARDING REVISIONS TO TECHNICAL SPECIFICATION 3.3.6.1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION (CAC NO. MF5749)
Dear Mr. Barstow:
On December 23, 2015 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML15321A472), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 319 to Renewed Facility Operating License No. DPR-52 for Browns Ferry Nuclear Plant, Unit 2 (Browns Ferry 2). The Amendment revised Technical Specification (TS)
Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," to add the number 3 to the column titled, "Applicable Modes or Other Specified Conditions, for Function 5.g, Standby Liquid Control System Initiation.
Table 3.3.6.1-1 is three pages long and is located on pages 3.3-59 through 3.3-61 of the Browns Ferry 2 TSs. The TS page 3.3-62 contains TS 3.3.6.2, Secondary Containment Isolation Instrumentation. Function 5.g is located on the third page of Table 3.3.6.1-1 (i.e.,
page 3.3-61). Amendment No. 319 was supposed to replace page 3.3.6.1-1 with revised page reflecting the approved change. During preparation of Amendment No. 319, the NRC staff used a revised TS page that contained a typographical error in the page number, listing it as page 3.3-62, instead of page 3.3-61. As a result, the NRC staff inadvertently replaced the first page of TS 3.3.6.2 on page 3.3-62 with the revised third page of Table 3.3.6.1-1, instead of replacing page 3.3-61. Table 3.3.6.1-1 was subsequently revised on December 26, 2019, by Amendment No. 334 (ADAMS Accession No. ML19294A011), which revised the Browns Ferry 2 TSs to adopt Technical Specifications Task Force Traveler, TSTF-542, "Reactor Pressure Vessel Water Inventory Control (ADAMS Accession No. ML16343B008). As part of Amendment No. 334, the NRC staff issued page 3.3-62, as revised by changes approved in the Amendment.
The purpose of this letter is to issue a correction to TS pages 3.3-61 and 3.3-62 for Amendment No. 319, as modified by Amendment No.334. The NRC staff concludes that the corrections are entirely editorial in nature and do not change the staffs previous conclusion in its safety evaluations for Amendment Nos. 319 and 334, nor does it affect the no significant hazards consideration, as published in the Federal Register on May 26, 2015 (80 FR 30097),
and May 7, 2019 (84 FR 19974), respectively.
J. Barstow If you have any questions regarding this matter, please contact me at (301) 415-6459 or by email at michael.wentzel@nrc.gov.
Sincerely, Michael J. Wentzel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260
Enclosure:
Correction to Technical Specifications cc: Listserv Michael J.
Wentzel Digitally signed by Michael J. Wentzel Date: 2020.08.11 12:54:57 -04'00'
Enclosure CORRECTIONS TO TECHNICAL SPECIFICATIONS RENEWED FACILITY OPERATING LICENSE NO. DPR-52 FOR BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications, as follows:
Remove page Insert page 3.3-61 3.3-61 3.3-62 3.3-62
Primary Containment Isolation Instrumentation 3.3.6.1 BFN-UNIT 2 3.3-61 Amendment No. 253, 254, 260 277, 297, 319, 000 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5.
Reactor Water Cleanup (RWCU) System Isolation a.
Main Steam Valve Vault Area Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 188°F b.
Pipe Trench Area Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 135°F c.
Pump Room A Area Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 152°F d.
Pump Room B Area Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 152°F e.
Heat Exchanger Room Area (West Wall)
Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 143°F f.
Heat Exchanger Room Area (East Wall)
Temperature - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 170°F g.
SLC System Initiation 1,2,3 1(a)
H SR 3.3.6.1.6 NA h.
Reactor Vessel Water Level - Low, Level 3 1,2,3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 528 inches above vessel zero 6.
Shutdown Cooling System Isolation a.
Reactor Steam Dome Pressure - High 1,2,3 1
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 115 psig b.
Reactor Vessel Water Level - Low, Level 3 3
2 I
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 528 inches above vessel zero c.
Drywell Pressure - High 1,2,3 2
F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 2.5 psig (a)
One SLC System Initiation signal provides logic input to close both RWCU valves.
(b)
Deleted.
334
Secondary Containment Isolation Instrumentation 3.3.6.2 BFN-UNIT 2 3.3-62 Amendment No. 253 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6.2-1.
ACTIONS
NOTE---------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Place channel in trip.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 1 and 2 AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1 and 2 B. One or more automatic Functions with secondary containment isolation capability not maintained.
B.1 Restore secondary containment isolation capability.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)
Package ML20190A101 Correction Letter ML20190A105 BFN2 Page Revision ML20190A111 Original Letter ML15321A472
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