ML033090085
| ML033090085 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/23/2003 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033090085 (7) | |
Text
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'iPowere A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax October 23, 2003 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Proposed Technical Specifications Amendments 3.3.2, Engineered Safety Feature Actuation System Instrumentation
Reference:
Letter from Duke Energy Corporation to NRC, same subject, dated August 19, 2003 The reference letter transmitted Duke Energy Corporation's proposed license amendment to revise the Catawba Nuclear Station Facility Operating Licenses and Technical Specifications (TS) to modify the requirements for the Containment Pressure Control System (CPCS) in TS 3.3.2, Table 3.3.2-1, Function 9. This change was requested in order to eliminate a problem with CPCS circuit fluctuation as a result of electronic noise.
On September 10, 2003, the NRC issued License Amendments 208 and 202 for Catawba Units 1 and 2, respectively.
These amendments modified the TS and Bases for TS 3.3.2 and resulted in revisions to the pages contained in the reference letter.
Therefore, the subject pages for the CPCS proposed amendment are being remarked and resubmitted to reflect the currently issued pages.
This resubmittal of the affected TS and Bases pages does not result in changes to the technical discussion associated with the reference letter.
Also, no changes to the originally transmitted No Significant Hazards Consideration Analysis or Environmental Analysis are necessary.
There are no NRC commitments contained in this letter or its attachment.
'A C' www. duke-energy. corn
U.S. Nuclear Regulatory Commission Page 2 October 23, 2003 Pursuant to 10 CFR 50.91, a copy of this letter is being sent to the appropriate state official.
Inquiries on this matter should be directed to L.J. Rudy at (803) 831-3084.
Very truly yours, Dhiaa M. Jaml LJR/s Attachment
U.S. Nuclear Regulatory Commission Page 3 October 23, 2003 Dhiaa M. Jamil, 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 Subscribed and sworn to me:
/0.2°3 Date Notar Public a
My commission expires:
7 -/ - sa Date SEAL
U.S. Nuclear Regulatory Commission Page 4 October 23, 2003 xc (with attachment):
L.A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters (addressee only)
NRC Senior Project Manager (CNS)
U.S. Nuclear Regulatory Commission Mail Stop 08-H12 Washington, D.C. 20555-0001 H.J. Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATIONS AND BASES PAGES FOR CATAWBA
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 5)
Engineered Safety Feature Actuation System Instrumentation APPUCABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDmONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 7. Automatic Switchover to Containment Sump
- a.
Automatic 1.2,3,4 2 trains C
SR 3.3.22 NA NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays
- b.
Refueling Water 1,2.3,4 4
N SR 3.3.2.1 2 162.4 177.15 Storage Tank SR 3.32.7 Iches Inches (RWST) Level -
SR 3.32.9 Low SR 3.32.10 Coincident with Refer to Function 1 (Safety Injection) for all Initiation functions and requirements.
Safety Iniection
- 8. ESFAS Interlocks
- a.
Reactor Trip, P-4 1.2,3 1 per train, F
SR 3.3.2.8 NA NA 2 trains
- b.
Pressurizer 12,3 3
0 SR 3.3.2.5 2 1944 and 1955 psig Pressure, P-1I SR 3.3.2.9 5 1966 psig
- c.
Trg - Low Low, 1,2,3 1 per loop 0
SR 3.3.2.5 25500F 553°F P-12 SR 3.3.2.9
- 9. Containment Pressure Control S
System C S
- a.
Start Permissive 1,2,3,4 4 per train P
psid id SR 3.3.2.9
- b.
Termination 1.23,4 4 per train P
SR 3.3.2.1 20.25 psid SR 3.3.2.9
- 10. Nuclear Service 1,2,3,4 3 per pit Q,R SR 3.3.2.1 2 El. 555.4 ft El. 557.5 ft Water Suction SR 3.3.2.9 Transfer - Low Pit SR 3.3.2.11 Level SR 3.3.2.12 Catawba Units 1 and 2 3.3.2-1 5 Amendment Nos. C0A2
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued) decreasing temperature, the P-12 interlock removes the arming signal to the Steam Dump System to prevent an excessive cooldown of the RCS due to a malfunctioning Steam Dump System.
Since Ta is used as an indication of bulk RCS temperature, this Function meets redundancy requirements with one OPERABLE channel in each loop. These channels are used in two-out-of-four logic. This Function must be OPERABLE in MODES 1, 2, and 3 when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This Function does not have to be OPERABLE in MODE 4, 5, or 6 because there is insufficient energy In the secondary side of the unit to have an accident.
- 9.
Containment Pressure Control System Permissives The Containment Pressure Control System (CPCS) protects the Containment Building from excessive depressurization by preventing inadvertent actuation or continuous operation of the Containment Spray and Containment Air Return Systems when containment pressure is at or less than the CPCS permissive setpoint. The control scheme of CPCS is comprised of eight independent control circuits (4 per train), each having a separate and independent pressure transmitter and current alarm module.
Each pressure transmitter monitors the containment pressure and provides input to its respective current alarm. The current alarms are set to inhibit or terminate containment spray and containment air return systems when containment pressure falls to or below The alarm modules switch back to the permissive state (allowing the systems to operate) when containment pressure is greater than or equal toqR This function must be OPERABLE in MODES 1, 2,3, and 4 when there is sufficient energy in the primary and secondary sides to pressurize containment following a pipe break. In MODES 5 and 6, there is insufficient energy in the primary and secondary sides to significantly pressurize the containment.
- 10.
Nuclear Service Water System Suction Transfer - Low Pit Level Upon an emergency low pit level signal from either NSWS pit, interlocks isolate the NSWS from Lake Wylie, align NSWS to the standby nuclear service water pond, close particular crossover Catawba Units 1 and 2 B 3.3.2-30 Revision No.M