ML19029B249
| ML19029B249 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/12/2019 |
| From: | V Sreenivas Plant Licensing Branch 1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Sreenivas V, NRR/DORL/LPLI, 415-2597 | |
| References | |
| EPID L-2018-LLA-0020 | |
| Download: ML19029B249 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 12, 2019 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNIT 2-CORRECTION TO AMENDMENT NO. 195 REVISING TECHNICAL SPECIFICATIONS TO LOWER THE MINIMUM STANDBY LIQUID CONTROL SYSTEM PUMP FLOWRATE (EPID L-2018-LLA-0020)
Dear Mr. Hanson:
By letter dated November 27, 2018 (Agencywide Documents Access and Management System Accession No. ML18255A278), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 195 to Renewed Facility Operating License No. NPF-85 for the Limerick Generating Station, Unit 2. The amendment was in response to your application dated January 29, 2018, as supplemented by letter dated June 11, 2018.
The amendment lowered the Technical Specification (TS) standby liquid control system (SLCS) surveillance requirement (TS 3/4.1.5) pump flow rate value, raised the TS SLCS surveillance requirement Boron-10 enrichment value of the sodium pentaborate added to the SLCS tank, and expanded the operating range in the sodium pentaborate solution temperature/concentration requirements figure.
Subsequent to issuance of the amendment, the NRC staff was notified by Exelon Generation Company, LLC of two typographical errors inadvertently introduced that changed subparagraph numbering/lettering on TS page 3/4 1-20. Specifically, subparagraph c appears as subparagraph e and subparagraph d.1 appears as subparagraph d.e. The NRC staff has determined that these typographical errors were made inadvertently and are entirely editorial in nature. These two typographical errors do not change any of the conclusions in the safety evaluation associated with the issuance of Amendment No. 195 and do not affect the associated notice to the public. Enclosed is the replacement TS page.
If you have any questions, please contact me at 301-415-2597 or V.Sreenivas@nrc.gov.
Docket No. 50-353
Enclosure:
Corrected TS page 3/4 1-20 cc: Listserv Sincerely, V. Sreenivas, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Enclosure Corrected TS page 3/4 1-20
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
In accordance with the Surveillance Frequency Control Program by:
1.
Verifying the continuity of the explosive charge.
2.
Determining by chemical analysis and calculation* that the available weight of Boron-IO is greater than or equal to 18 5 lbs; the concentration of sodium pentaborate in solution is less than or equal to 13.8% and within the limits of Figure 3.1.5-1 and; the following equation is satisfied:
c x
E x
o
1 13% wt.
29 atom%
86 gpm where C = Sodium pentaborate solution(% by weight)
Q = Two pump flowrate, as determined per surveillance requirement 4.1.5.c.
E = Boron 10 enrichment (atom% Boron 10) 3.
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
4.
Verifying that no more than two pumps are aligned for automatic operation.
c.
Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 37.0 gpm per pump at a pressure of greater than or equal to 1230 +/- 25 psig is met.
ct.
In accordance with the Survei 11 ance Frequency Control Program by:
l.
Initiating at least one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch success fully fired. All injection loops shall be tested in 3 operating cycles.
2.
Verify all heat-treated piping between storage tank and pump suction is unblocked.**
e.
Prior to addition of Boron to storage tank verify sodium pentaborate enrichment to be added is³ 49 atom% Boron 10.
This test shall also be performed anytime water or boron is added to the solu tion or when the solution temperature drops below the limits of Figure 3.1.5-1 for the most recent concentration analysis, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron addition or solution temperature is restored.
- This test shall also be performed whenever suction piping temperature drops below the limits of Figure 3.1.5-1 for the most recent concentration analysis, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is.restored.
LIMERICK - UNIT 2 3/4 1-20 Amendment No. '.µ.J4,,4g,¶,+/-4e.+4+,
- .195
ML19029B249 OFFICE NRR/DORL/LPL 1 /PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1 /BC NAME VSreenivas LRonewicz JDanna DATE 01/29/2019 01/29/2019 02/11/2019