ML042170281
| ML042170281 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/29/2004 |
| From: | Barron H Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042170281 (9) | |
Text
Duke
- rPowere A Duke Energy Company HENRY8.BARRON Group VP, Nuclear Generation and Chief Nuclear Officer Duke Power EC07H/ 526 South Church Street Charlotte, NC 28202-1802 Mailing Address:
PO Box 1006 EC07H Charlotte, NC 28201-1006 July 29, 2004 704 382 2200 704 382 6056 fax hbarron @duke-energy. corn U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370 Supplement to License Amendment Request for McGuire Technical Specifications 3.4.11, Pressurizer Power Operated Relief Valves, Surveillance Requirement 3.4.11.1 Pursuant to 10CFR50.90, Duke Energy Corporation (Duke) has previously submitted a license amendment request (LAR) for the McGuire Nuclear Station Facility Operating Licenses and Technical Specifications (TS) by letter to the NRC dated December 4, 2003.
This LAR applies to TS 3.4.11, Pressurizer Power Operated Relief Valves (PORV), and proposes extending the Frequency for Surveillance Requirement (SR) 3.4.11.1, which is the quarterly stroke time test for the Pressurizer PORV Block Valves.
Based on a March 3, 2004 telephone conference with members of the NRC Staff, Duke is revising this LAR to require that the SR be performed at a Frequency consistent with the plant's Inservice Testing Program (IST).
The requested Frequency extension will be pursued through separate Duke submittal to be made in accordance with the ASME Code relief/deferral request process.
This LAR supplement contains the necessary revisions to the December 4, 2003 LAR in order to implement the NRC's directions from the March 3, 2004 telephone conference.
provides a marked copy of the existing TS for McGuire Units 1 and 2. The marked copy shows the proposed changes.
Reprinted TS and Bases pages will be provided prior to issuance of the approved amendment.
Duke has reviewed the original No Significant Hazards Consideration that was performed pursuant to 10CFR50.92 for this LAR, and has determined that it remains valid.
Likewise, the original basis, that was determined pursuant to 10CFR51.22(c)(9), for the categorical exclusion of this LAR from performing an Environmental Assessment/Impact Statement also remains valid.
,.O-0 www. dukepower. corn
I U. S. Nuclear Regulatory Commission July 29, 2004 Page 2 This submittal document contains the commitments listed below, which are the same as those originally stated in the December 4, 2003 Duke letter to the NRC.
1.Duke will implement this LAR within 30 days following NRC approval.
- 2. Duke will make the necessary revisions to the McGuire Inservice Testing Program in accordance with the applicable codes and regulations.'2 Inquiries on this matter should be directed to J. S. Warren at (704) 875-5171.
Very truly yours, Henry B. Barron xc w/Attachments:
W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. J. Shea (Addressee Only)
J. B. Brady NRC Project Manager (MNS)
NRC Senior Resident Inspector Mail Stop 0-8 H12 McGuire Nuclear Site Washington, DC 20555-0001 Beverly 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 1 10 CFR 50.55a(a)(3)(ii), Codes and standards.
2ASME Code for Operation and Maintenance.
U. S. Nuclear Regulatory Commission July 29, 2004 Page 3 Henry B. Barron, affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
Henry B. Barron Group Vice President, Nuclear Generation and Chief Nuclear Office Subscribed and sworn to me:
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, Notary Public My commission expires: 23' 1, 6 9 I
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U. S. Nuclear Regulatory Commission July 29, 2004 Page 4 bxc w/Attachments:
K. L. Crane E. L. Hyland L. F. Firebaugh NRIA File/ELL McGuire Master File -
Mail Code MGO1DM McGuire Units 1 and 2 Technical Specifications Marked Copy
SURVEILLANCE REQUIREMENTS\\
=
SURVEILLANCE FREQUENCY SR 3.4.1 1.1
NOTE ------------------------------ -----
/
Not required to be met with block valve closed in accordance with the Required Action of Condition A, B, or E.
Perform a complete cycle of each block valve.
SR 3.4.11.2 ----------------------------- NOTE-----------------------------------
Required to be performed in MODE 3 or MODE 4 when the temperature of all RCS cold legs is > 300'F and the block valve closed.
Perform a complete cycle of each PORV.
18 months SR 3.4.11.3 Verify the nitrogen supply for each PORV is OPERABLE 18 months by:
- a.
Manually transferring motive power from the air supply to the nitrogen supply,
- b.
Isolating and venting the air supply, and
- c.
Operating the PORV through one complete cycle.
McGuire Units I and 2 3.4.11-4 Amendment Nos.uwi17
Pressurizer PORVs B 3.4.1 1 BASES ACTIONS (continued)
H.1 and H.2 If the Required Actions of Condition F or G are not met, then the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODES 4 and 5, maintaining PORV OPERABILITY may be required. See LCO 3.4.12.
SURVEILLAN REQUIREME1 CE SR 3.4.11.1 ITS*
Block valve cy ng verifies tha he valve(s) be closed if nee ed.
The basis fo he Frequency 92 days is th ASME Code, Sec on Xl (Ref. 4). the block valve inclosed to isolae a PORV that is pable of being nually cycled, th OPERABILITY of the block valve I of impgance, because op ning the block lve is necessary t permit the P
V to be used for anual control of eactor pressure. Ithe block alve is closed to iso te an otherwise noperable PORV, t e maximum Completion Time t restore the PO and open the bloc valve is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, which iwell within the al wable limits (25%) o extend the block valve Freguency of 92 days Furthermore, thes test requirements would be co leted by the reop ing of a recently clsed block valve upon restor ion of the PORV t OPERABLE status i.e., completion of thje Requird Actions fulfills th SR).
The Note modifies this SR by stating that it is not required to be met with the block valve closed, in accordance with the Required Action of this LCO.
SR 3.4.11.2 SR 3.4.11.2 requires a complete cycle of each PORV. Operating a PORV through one complete cycle ensures that the PORV can be manually actuated for mitigation of an SGTR. The Frequency of 18 months is based on a typical refueling cycle and industry accepted practice.
The SR is modified by a Note which states that the SR is required to be performed in MODE 3 or 4 when the temperature of the RCS cold legs is
> 3000 F consistent with Generic Letter 90-06 (Ref. 5).
McGuire Units 1 and 2 B 3.4.1 1-6 Revision No.
INSERT SRs are specified in the Inservice Testing Program.
The Pressurizer PORV block valves are to be tested in accordance with the requirements of the ASME Code for Operation and Maintenance (OM Code), Reference 4, which provides the activities and Frequencies necessary to satisfy the SRs.
No additional requirements are specified.
Pressurizer PORVs B 3.4.11 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.4.11.3 The Surveillance demonstrates that the emergency nitrogen supply can be provided and is performed by transferring power from normal air supply to emergency nitrogen supply and cycling the valves. The Frequency of 18 months is based on a typical refueling cycle and industry accepted practice.
REFERENCES 1
Regulatory Guide 1.32, February 1977.
- 2.
UFSAR, Section 15A.
- 3.
10 CFR 50.36, Technical Specifications, (c)(2)(H).
/ 5.
Resolution of Generic Issue 70, "Power-Operated Relief Valve and Block Valve Reliability," and Generic Issue 94, Additional Low-Temperature Overpressure Protection for Ught-Water Reactors,'
Pursuant to 10 CFR 50.54(f) (Generic Letter 90-06).
ue CUie 1O aB 1Re n
McGuire Units 1 and 2 B 3.4.11-7 Revision Noe/