ML15296A056
| ML15296A056 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/23/2015 |
| From: | Bhalchandra Vaidya Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Nuclear, Nine Mile Point |
| Vaidya B, NRR/DORL/LPL3-2, 415-3308 | |
| References | |
| CAC MF3056 | |
| Download: ML15296A056 (4) | |
Text
.OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 November 23, 2015
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO. 2-CORRECTION LEITER TO AMENDMENT NO. 151 RE: MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (CAC NO. MF3056)
Dear Mr. Hanson:
By letter dated September 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15230A487), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 151, "Maximum Extended Load Line Limit Analysis Plus" (MELLLA+), to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Unit No. 2 (NMP2). The amendment consists of changes to the technical specifications (TSs) in response to your application transmitted by letter dated November 1, 2013, as supplemented by letters dated January 21, February 14, February 25, March 10, May 14, June 13, October 10, December 11, 2014, and February 18, 2015.
By emails dated September 29 and October 21, 2015 (non-publicly available), and the discussion with your staff on October 21, 2015, they identified: (1) a correction to TS page 3.3.1.1-9, and (2) several instances where the publicly-available MELLLA+ safety evaluation (SE) (ADAMS Accession No. ML15223B144) contained sensitive proprietary information that has been submitted previously by the licensee and approved by the NRC for withholding from public disclosure in accordance with Section 2.390 of Title 10 of the Code of Federal Regulations (1 O CFR). The NRG acknowledges the error on the TS page, as well as associated portions of the NRC SE that should have been withheld from public disclosure in accordance with Secf1on 2.390 of 10 CFR, and has replaced the publicly-available version of the MELLLA+
SE, in its entirety, in ADAMS under the existing Accession No. ML152238144.
NOTICE: Enclosure 3 to this letter contains Sensitive Proprietary Information Upon separation from the Enclosure 3, this letter is DECONTROLLED OFFICIAL USE ONLY SENSl'fl1t'E PROPFUETARV INFORMATION
OFFICIAL USE ONLY - SENSITIVE PROPRIETARY INFORMATION The corrected TS page (TS 3.3.1.1-9) and corrected publicly-available SE that reflects the additional redacted information is enclosed. Also, for consistency, the non-publicly available version of the MELLLA+ SE has been updated and replaced in ADAMS under the existing Accession No. ML15195A257.
These corrections do not change the amendment pages of the license or any of the conclusions in the SE associated with the amendment, and do not affect the associated notice to the public.
Please contact me at 301-415-3308 if you have any questions.
Docket No. 50-410
Enclosure:
- 1) Corrected TS Page TS 3. 3.1.1-9 Sincerely, Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 2) Corrected Non-proprietary Safety Evaluation (ML152238144)
- 3) Corrected Proprietary Safety Evaluation cc w/encls 1 and 2 only: Distribution via Listserv OFFICIAL USE ONLY SENSITIVE PROPRIETARY INFORMATION
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 2. Average Power Range Monitors (continued)
- e.
OPRM-Upscale
<!18% RTP(f) 3 per logic F
SR 3.3.1.1.2 NA channel SR 3.3.1.1.7 SR 3.3.1.1.10 SR 3.3.1.1.13
- f.
2-0ut-Of-4 Voter 1,2 2
H SR 3.3.1.1.2 NA SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.17
- 3.
Reactor Vessel Steam Dome 1,2 2
H SR 3.3.1.1.1 s 1072 psig Pressure - High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.17
- 4.
Reactor Vessel Water 1,2 2
? 157.8 inches Level - Low, Level 3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.17
- 5. Main Steam Isolation 8
G SR 3.3.1.1.8 s 12% closed Valve - Closure SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.17
- 6. Drywell Pressure - High 1,2 2
H SR 3.3.1.1.1 s 1.88 psig SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.14 (continued)
(f)
Following DSS-CD implementation, DSS-CD is not required to be armed while in the DSS-CD Armed Region during the first reactor startup and during the first controlled shutdown that passes completely through the DSS-CD Armed Region. However, DSS-CD is considered OPERABLE and shall be maintained OPERABLE and capable of automatically arming for operation at recirculation drive flow rates above the DSS-CD Armed Region.
NMP2 3.3.1.1-9 Amendment 91, 92, 140, 151 Correction Letter Dated
Package: ML15299A049 Correction Letter and corrected TS Page 3.3.1.1-9: ML15296A056 G. Thomas, NRR/SRXB D. Saenz, NRR/SRXB R. Stattel, NRR/EICB I. Tseng, NRR/EMCB DSchroder, Region 1 N. Karipineni, NRR/SCVB M. Panicker, NRR/SNPB M. Honcheric, NRR/STSB R. Pederson. NRR/ARCB J. Tsao, NRR/EPNB D. Frumkin, NRR/AFPB Email from Licensee identifying the inadvertent release of Proprietary information: ML15295A018 C
N P
d P SE ML 1 5A257 orrected on-ropr1etary orrecte roprietary 519 OFFICE N RR/DORL/LPLI 11-2/PM N RR/DORL/LPLl-1 /LA NRR/DORL/LPLl-1 /BC NRR/DORL/LPLlll-2/PM NAME BVaidya KGoldstein TTate BVaidya (MHenderson for)
DATE 11/18/2015 11/18/2015 11/23/2015 11/23/2015