ML110960432

(Cns), Units 1 and 2, Supplement for License Amendment Request to Revise Technical Specification (TS) 3.3.2, Engineer Safety Feature Actuation System Instrumentation Removal of the Superceded TS and Bases Requirements

ML110960432
Person / Time
Site:	Catawba
Issue date:	03/31/2011
From:	Morris J Duke Energy Carolinas, Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME3722, TAC ME3723
Download: ML110960432 (8)

Text

/-IDuke

__ EnDuke James R. Morris Vice President, Catawba Nuclear Station Nuclear Generation Duke Energy Corporation Catawba Nuclear Station / CN01 VP 4800 Concord Road York, SC 29745 10 CFR 50.90 803-701-4251 803-701-3221 March 31, 2011 Jim.Morris@duke-energy.com U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Duke Energy Carolinas, LLC (Duke Energy)

Catawba Nuclear Station (CNS), Units 1 and 2, CNS Docket Nos. 50-413, 50-414 Supplement for License Amendment Request to Revise Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)

Instrumentation" Removal of the Superceded TS and Bases Requirements

REFERENCES:

1. Letter from Duke Energy, LLC to U.S. NRC, Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)

Instrumentation" Removal of the Superceded TS and Bases Requirements, dated September 16, 2010.

2. Letter from U.S. NRC to Duke Energy, LLC, Catawba Nuclear Station, Units 1 and 2, Issuance of Amendments Regarding Revision of the Technical Specifications to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program Using a Risk-Informed Justification (TSTF-425), dated March 29, 2011 (TAC NOS. ME3722 AND ME3723).

This letter provides a supplemented request regarding the Duke Energy License Amendment Request (LAR) dated September 16, 2010 (Ref. 1) related to an administrative request to remove superceded TS. This request was conveyed via email to Jon Thompson on March 28, 2011.

Catawba Nuclear Station is requesting upon issuance of the subject amendment a 90-day implementation is allotted in lieu of the standard 30-day implementation grace period. This request is being asked on the basis of the issuance of TSTF-425 (Ref. 2) prior to the subject LAR, thereby impacting parallel associated TS pages submitted on behalf of the subject amendment.

www.duke-energy.com ko~

The final Technical Specification and Bases pages are provided in Attachment 1. They were not included in the initial submittal of Ref. 1 due to current amendments pending NRC review that would directly impact the issuance of the final TS pages within this submittal.

This letter contains no new commitments.

Please contact A.F. Driver at 803-701-3445 or Adrienne. Driver(cduke-ener-qy.com.

Sincerely, J mes R. Morris : Catawba Technical Specification Final Pages

U.S. Nuclear Regulatory Commission March 31, 2011 Page 3 Oath or Affirmation James R. Morris 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.

(; a'4ý ý James F"orris Site Vice President, Catawba Nuclear Station Subscribed and sworn to me: ULWeA 3I , Z.:)

Date Notary Public INotary Public, South Carolina, State at Large My Commission Expires: myCommissionExpiresMarch6,2018 Date SEAL Pý

U.S. Nuclear Regulatory Commission March 31, 2011 Page 4 xc:

V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 '

J. H. Thompson, Project Manager (CNS & MNS)

U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station G. A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station S. E. Jenkins, Manager Radioactive & Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St.

Columbia, SC 29201

Attachment 1:

Catawba Technical Specification Final Pages

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME, J. One channel inoperable. J.1 ----- NOTE-------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR J.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> I K. One Main Feedwater K.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Pumps trip channel inoperable. OR K.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (continued)

Catawba Units 1 and 2 3.3.2-5 Amendment Nos.

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One channel inoperable. L.1 ---------- NOTE ----

The inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR L.2 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Catawba Units 1 and 2 3.3.2-6 Amendment Nos.

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 5)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT (2). SG Water 1,2(e),3(e) 4 per SG D SR 3.3.2.1 < 85.6% 83.9%

Level- High SR 3.3.2.2 (Unit 1) (Unit 1)

High (P-14) SR 3.3.2.4 < 78.9% 77.1%

SR 3.3.2.5 (Unit 2) (Unit 2)

SR 3.3.2.6 SR 3.3.2.9 SR 3.3.2.10 (3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements. See Injection Item 5.b.(1) for Applicable MODES.

(4) Tavg-Low 1,2(e) 4 J SR 3.3.2.1 > 561°F 564°F SR 3.3.2.5 SR 3.3.2.9 coincident with Refer to Function 8.a (Reactor Trip, P-4) for all initiation functions and requirements.

Reactor Trip, P-4 (5) Doghouse 1,2(e) 3 per train L SR 3.3.2.8 :512 inches 11 inches WaterLevel - per SR 3.3.2.9 above 577 ft above 577 High High doghouse SR 3.3.2.12 floor level ft floor level

6. Auxiliary Feedwater

a. Automatic 1,2,3 2 trains H SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays

b. SG Water Level 1,2,3 4 per SG D SR 3.3.2.1 >_9% .10.7%

- Low Low SR 3.3.2.5 (Unit 1) (Unit 1)

SR 3.3.2.9 > 35.1% 36.8%

SR 3.3.2.10 (Unit 2) (Unit 2)

c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d. Loss of Offsite 1,2,3 3 per bus D SR 3.3.2.3 Ž 3242 V 3500 V Power SR 3.3.2.9 SR 3.3.2.10

e. Trip of all Main 1,2 3 per pump K SR 3.3.2.8 NA NA Feedwater SR 3.3.2.10 Pumps

f. Auxiliary 1,2,3 3 per train M SR 3.3.2.8 A) > 9.5 psig A) 10.5 Feedwater Pump SR 3.3.2.10 psig Train A and Train B Suction B) > 5.2 psig B) 6.2 psig Transfer on (Unit 1) (Unit 1)

Suction >- 5.0 psig 6.0 psig Pressure - Low (Unit 2) (Unit 2)

(continued)

(e) Except when all MFIVs, MFCVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

Catawba Units 1 and 2 3.3.2-16 Amendment Nos.