ML13346A767
| ML13346A767 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/18/2013 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Heacock D Dominion Nuclear Connecticut |
| Kim J | |
| References | |
| TAC ME8320, TAC ME9189 | |
| Download: ML13346A767 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 December 18, 2013
SUBJECT:
MILLSTONE POWER STATION UNIT NO.3-CORRECTION LETTER TO LICENSE AMENDMENT NOS. 256 AND 257 (TAC NOS. ME9189 AND ME8320)
Dear Mr. Heacock:
On January 11, 2013, the Nuclear Regulatory Commission (NRC) issued Amendment No. 256 to Renewed Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3),
in response to your application dated July 31, 2012, as supplemented by letter dated August 28, 2012. On February 6, 2013, the NRC issued Amendment No. 257 to Renewed Facility Operating License No. NPF-49 for MPS3, in response to your application dated April 2, 2012.
Amendment Nos. 256 and 257 both added new information to MPS3 Technical Specification (TS) Section 6.8.4, "PROCEDURES AND PROGRAMS." Simultaneous implementation of Amendment Nos. 256 and 257 necessarily resulted in an additional TS page, 6-17g, due to the combined length of the two amendments. However, TS page 6-17e was inadvertently removed in lieu of creating a newTS page, 6-17g.
Enclosed please find corrected TS pages, 6-17e, 6-17f, and 6-17g.
Please contact me at 301-415-4125 if you have any questions.
Docket No. 50-423
Enclosure:
As stated cc w/encls: Distribution via Listserv Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) associated with a crack(s), then the indication need not be treated as a crack.
- e.
Provisions for monitoring operational primary to secondary LEAKAGE.
- h.
Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVs), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a.
The definition of the CRE and the CRE boundary.
- b.
Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision 0.
MILLSTONE - UNIT 3 The following are exceptions to Sections C. I and C.2 ofRegulatory Guide 1.197, Revision 0:
- 1. Appropriate application of ASTM E7 41 shall include the ability to take minor exceptions to the test methodology. These exceptions shall be documented in the test report, and
- 2. Vulnerability assessments for radiological, hazardous chemical and smoke, and emergency ventilation system testing were completed as documented in the UFSAR and other licensing basis documents. The exceptions to the Regulatory Guides (RG) referenced in RG 1.196 (i.e., RG 1.52, RG 1. 78, and 6-17e Amendment No. 243, 245, 256
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
RG 1.183), which were considered in completing the vulnerability assessments, are documented in the UFSAR/current licensing basis. Compliance with these RGs is consistent with the current licensing basis as described in the UFSAR and other licensing basis documents.
- d.
Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREV s, operating at the flow rate required by the Surveillance Requirements, at a Frequency of 48 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.
- e.
The quantitative limits on unfiltered air inleakage into the CRE.
These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
The provisions of Surveillance Requirement 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c. and d., respectively.
- 1.
Snubber Examination, Testing, and Service Life Monitoring Program Plan This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (lSI) requirements for supports. The program shall be in accordance with the following:
- a.
This program shall meet 10 CFR 50.55a(g) lSI requirements for supports.
- b.
The program shall meet the requirements for lSI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b), subject to its limitations and modifications, and subject to Commission approval.
MILLSTONE - UNIT 3 6-17f Amendment No. 245, 256, 257
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- c.
The program shall, as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and Inservice Examination and Testing ofDynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" in lieu of Section XI ofthe ASME BPV Code lSI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).
- d.
The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications listed therein.
6.8.5 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.
6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 6.8.5 above shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.
Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP, within 14 days of implementation.
MILLSTONE - UNIT 3 6-17g Amendment No. 257
Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 December 18, 2013
SUBJECT:
MILLSTONE POWER STATION UNIT NO.3-CORRECTION LETTER TO LICENSE AMENDMENT NOS. 256 AND 257 (TAC NOS. ME9189 AND ME8320)
Dear Mr. Heacock:
On January 11, 2013, the Nuclear Regulatory Commission (NRC) issued Amendment No. 256 to Renewed Facility Operating License No. NPF-49 for Millstone Power Station, Unit No.3 (MPS3),
in response to your application dated July 31, 2012, as supplemented by letter dated August 28, 2012. On February 6, 2013, the NRC issued Amendment No. 257 to Renewed Facility Operating License No. NPF-49 for MPS3, in response to your application dated April 2, 2012.
Amendment Nos. 256 and 257 both added new information to MPS3 Technical Specification (TS) Section 6.8.4, "PROCEDURES AND PROGRAMS." Simultaneous implementation of Amendment Nos. 256 and 257 necessarily resulted in an additional TS page, 6-17g, due to the combined length of the two amendments. However, TS page 6-17e was inadvertently removed in lieu of creating a newTS page, 6-17g.
Enclosed please find corrected TS pages, 6-17e, 6-17f, and 6-17g.
Please contact me at 301-415-4125 if you have any questions.
Docket No. 50-423
Enclosure:
As stated Sincerely, Ira/
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAKGoldstein RidsNrrPMMillstone RidsRgn1 Mail Center RidsNrrDoriDpr Resource RidsOgcMaiiCenter Resource ADAMS Accession No.: ML13346A767 OFFICE LPL 1-1/PM LPL1-1/LA LPL 1-1/BC NAME JKim KGoldstein BBeasley DATE 12/17/13 12/17/13 12/18/13 OFFICIAL Rl ~l;QRD COPY RidsNrrDorllpl1-1 Resource R. McKinley, Rl RidsAcrsAcnw_MaiiCenter Resource LPL 1-1/PM JKim 12/18/13