ML12242A476

Update to Technical Specification (TS) Table 3.3.3-1 and Technical Specification Bases (Tsbs) 3.3.3

ML12242A476
Person / Time
Site:	Watts Bar
Issue date:	08/27/2012
From:	Hruby R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12242A476 (6)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 27, 2012 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391

Subject:

Watts Bar Nuclear Plant (WBN) Unit 2 - Update to Technical Specification (TS) Table 3.3.3-1 and Technical Specification Bases (TSBs) 3.3.3

References:

1. TVA Letter to NRC dated June 5, 2012, "Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Revised Section 4.3, 'Fuel Storage,'

Developmental Revision G of the Unit 2 Technical Specification (TS)"

2. TVA Letter to NRC dated February 28, 2012, "Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases" This letter provides an update to Unit 2 TS Table 3.3.3-1, "Post Accident Monitoring Instrumentation," to delete footnote "(g)" from function 6), "Reactor Vessel Water Level."

In addition, TSB 3.3.3 has been updated to state that function 6), "Reactor Vessel Water Level," is now a Type A, Category 1 variable. These changes will be incorporated as part of TS, Developmental Revision H at a later date. This condition has been entered into TVA's corrective action program as Problem Evaluation Report 488815. provides page markups for both of these changes. Enclosure 2 provides the list of regulatory commitments associated with this letter.

U.S. Nuclear Regulatory Commission Page 2 August 27, 2012 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27th day of August, 2012.

Respectfully, Raymond A. Hruby, Jr.

General Manager, Technical Services Watts Bar Unit 2

Enclosures:

1. WBN Unit 2 TS and TSB Mark-ups

2. List of Regulatory Commitments cc (Enclosures):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

Enclosure I WBN Unit 2 TS and TSB Mark-ups

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS ACTION D.1

1) Intermediate Range Neutron Flux (g) 1(a), 2 (b) 3 2 E

2) Source Range Neutron Flux 2 (c), 3 2 E

3) Reactor Coolant System (RCS) Hot Leg 1,2,3 1 per loop E Temperature (T-Hot)

4) RCS Cold Leg Temperature (T-Cold) 1,2,3 1 per loop E

5) RCS Pressure (Wide Range) 1,2,3 3 E

6) Reactor Vessel Water Level (f)m 1,2,3 2 F

7) Containment Sump Water Level (Wide 1,2,3 2 E Range)

8) Containment Lower Comp. 1,2,3 2 E Atm. Temperature

9) Containment Pressure (Wide Range) (g) 1,2,3 2 E

10) Containment Pressure (Narrow Range) 1,2,3 4 E

11) Containment Isolation Valve Position (g) 1,2,3 2 per E penetration flow path (d)(i) 2 upper

12) Containment Radiation (High Range) 1,2,3 F containment 2 lower containment

13) RCS Pressurizer Level 1,2,3 3 E

14) Steam Generator (SG) Water Level 1,2,3 1I/SG E (Wide Range) (9)

(continued)

Watts Bar - Unit 2 3.3-44 (developmental) SH I

PAM Instrumentation B 3.3.3 BASES LCO 5. Reactor Coolant System Pressure (Wide Range) (continued) to make a determination on the nature of the accident in progress and where to go next in the procedure.

RCS pressure is also related to three decisions about depressurization.

They are:

" to determine whether to proceed with primary system depressurization;

" to verify termination of depressurization; and

" to determine whether to close accumulator isolation valves during a controlled cooldown/depressurization.

A final use of RCS pressure is to determine whether to operate the pressurizer heaters.

RCS pressure is a Type A variable because the operator uses this indication to identify events and to monitor the cooldown of the RCS following a steam generator tube rupture (SGTR) or small break LOCA.

Operator actions to maintain a controlled cooldown, such as adjusting steam generator (SG) pressure or level, would use this indication.

6. Reactor Vessel Water Level ReatorVeselWater Level, a non Typo A, Category 1 Yariablo, i proidedI for verificatfion andI long term 6urveillance o-f co-re coln.It is

_Also9 used foar acc-idet-Pit d-iagnosis and to dctermninc reactorF coolant inventor,' adequacy. Reactor Vessel Water Level, a Type A, Category 1 variable is provided for:

o SI re-initiation criteria, o Pressurizer Level Control, o Criteria for manually re-starting ECCS pumps, o Criteria for closing CLA isolation valves, o RCS Pressure Control, o Verification and long term surveillance of core cooling, o Accident diagnosis, o Determination of reactor coolant inventory adequacy, and o Pressurizer heater control (continued)

Watts Bar - Unit 2 B 3.3-130 (developmental) Ha I

ENCLOSURE 2 List of Regulatory Commitments

1. This letter provides an update to Technical Specification (TS) Table 3.3.3-1, "Post Accident Monitoring Instrumentation," to delete footnote "(g)" from function 6), "Reactor Vessel Water Level." In addition, Technical Specification Bases 3.3.3 has been updated to state that function 6), 'Reactor Vessel Water Level," is now a Type A, Category 1 variable. These changes will be incorporated as part of TS, Developmental Revision H at a later date.