ML041420080
| ML041420080 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/03/2004 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041420080 (7) | |
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Duke GARY R.
PETERSON tPowere Vice President A Duke Energy Company McGuire Nuclear Station Duke Power MGOVP/ 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax May 3, 2004 grpeteis@duke-energy.com 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 3.3.2, Engineered Safety Features Actuation System In a letter to Duke Energy Corporation (Duke) dated March 16, 2004, the NRC issued Amendments Nos. 220/202 for the McGuire Nuclear Station, Units 1 and 2, Facility Operating Licenses and Technical Specifications.
During the implementation of these amendments, Duke discovered an administrative alignment problem on Page 3.3.2-12 of this amendment package. Attachments 1 and 2 contain the corrected Page 3.3.2-12 in marked-up and reprinted versions.
Duke is requesting that the NRC re-issue the corrected Page 3.3.2-12 in a timely manner, such that the implementation of these amendments can proceed.
Inquiries on this matter should be directed to J. S. Warren at (704) 875-5171.
Very truly yours, G. R. Peterson www. duke-energy. corn
t' U. S. Nuclear Regulatory Commission May 3, 2004 Page 2 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)
NRC Senior Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-7 D11 Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Site Beverly 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645
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U. S. Nuclear Regulatory Commission May 3, 2004 Page 3 G. R. Peterson, 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.
G. R. Peterson, Site Vice President Subscribed and sworn to My co nmission expires:
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Date SEAL McGuire Units 1 and 2 Technical Specifications Marked Copy
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 5)
Engineered Safety Feature Actuation System Instrumentation I
APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 4.
Steam Line Isolation (continued)
(2) Negative Rate - High 3(b)(c) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9 s 120(d) psi 1oo(d)ps
- 5.
Turbine Trip and Feedwater Isolation
- a.
Turbine Trip 1.2 2 trains I
SR 3.3.2.2 NA I
~SR 3.32.4 (1) Automatic SR 3.3.2.6 Actuation Logic and Actuation Relays (2) SG Water Level-High High (P-14) 1,2 3 per SG J
SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9
< 85.6%
83.9%
(3) Safety Refer to Function I (Safety Injection) for all initiation functions and requirements. See Item Injection 5.a.(1) for Applicable MODES.
- b.
Feedwater Isolation (1) Automatic Actuation Logic and Actuation Relays (2) SG Water Level-High High (P-14) 1,2 (e), 3 (e) 1,2(e), 3(e) 2 trains 3 per SG H
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6-D SR 3.3.2.1.
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9 NA S 85.6 NA 83.9%
(continued)
(b)
Except when all MSIVs are closed and de-activated.
(c)
Trip function automatically blocked above P-11 (Pressurizer Pressure) interlock and may be blocked below P-11 when Safety Injection Steam Line Pressure-Low is not blocked.
(d)
Time constant utilized in the ratellag controller is > 50 seconds.
(e)
Except when all MFIVs. MFCVs. and associated bypass valves are closed and de-activated or isolated by a closed manual valve.
McGuire Units 1 and 2 3.3.2-1 2 Amendment Nos. 220/202 McGuire Units 1 and 2 Technical Specifications Reprinted Page
N ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 5)
Engineered Safety Feature Actuation System Instrumentation I
APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 4.
Steam Une Isolation (continued)
(2) Negative Rate - High 3(b)(c) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9 s
20(d) psi 10 0(d) psi
- 5.
Turbine Trip and Feedwater Isolation
- a.
Turbine Trip (1) Automatic Actuation Logic and Actuation Relays (2) SG Water Level-High High (P-1 4) 1,2 1,2 2 trains 3perSG I
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 J
SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9 NA
< 85.6%
NA 83.9%
(3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements. See item Injection 5.a.(1) for Applicable MODES.
- b.
Feedwater Isolation (1) Automatic Actuation Logic and Actuation Relays (2) SG Water Level-High High (P-14) 1,2 (e), 3(e) 1,2(e), 3(e) 2 trains 3 per SG H
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 D
SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9 NA S85.6 NA 83.9%
(continued)
(b)
Except when all MSIVs are closed and de-activated.
(c)
Trip function automatically blocked above P-1I (Pressurizer Pressure) Interlock and may be blocked below P-11 when Safety Injection Steam Line Pressure-Low Is not blocked.
(d)
Time constant utilized In the rateAag controller Is > 50 seconds.
(e)
Except when all MFIVs, MFCVs, and associated bypass valves are closed and de-activated or Isolated by a closed manual valve.
McGuire Units 1 and 2 3.3.2-1 2 Amendment No. 220/202