CNL-19-086, Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)

Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)

ML19283G098
Person / Time
Site:	Watts Bar
Issue date:	10/09/2019
From:	Polickoski J Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-19-086, WBN-TS-19-02
Download: ML19283G098 (12)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-19-086 October 9, 2019 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)

References:

1. TVA Letter to NRC, CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02), dated June 7, 2019 (ML19158A398)

2. NRC Letter to TVA, Watts Bar Nuclear Plant, Unit 1 - Issuance of Amendment to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified Intervals (EPID L-2018-LLA-0187), dated August 16, 2018 (ML18204A252)

In Reference 1, Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to make miscellaneous administrative changes to the Watts Bar Nuclear Plant (WBN),

Units 1 and 2 Technical Specifications (TS). One of the changes was to delete several historical footnotes associated with TS 3.6.15, Condition B for WBN Unit 1. However, a separate LAR is currently under development that overlaps this change. Accordingly, TVA has elected in this supplement to rescind this proposed change from Reference 1.

Additionally, subsequent to the Reference 1 LAR submittal, the Nuclear Regulatory Commission (NRC) informed TVA that the markup pages to WBN Unit 1 TS Surveillance Requirement (SR) 3.0.2 and Table SR 3.0.2-1 in Attachment 1 to Reference 1 did not reflect the changes made by License Amendment 121 (Reference 2). Accordingly, TVA is supplementing Reference 1 to include the revisions to WBN Unit 1 TS Surveillance Requirement (SR) 3.0.2 and Table SR 3.0.2-1 based on Reference 2. Changes to the clean pages and the Attachment 5 Bases change accurately incorporated Amendment 121, so inclusion of these pages is unnecessary.

U.S. Nuclear Regulatory Commission CNL-19-086 Page 2 October 9, 2019 An additional errata change is made to Table of Contents Page iii of Attachment 1 to address a typographical error.

The enclosure to this letter provides change instructions to the LAR to make the above supplements. This enclosure does not change the no significant hazards consideration or the environmental considerations contained in the referenced LAR. Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the enclosure to the Tennessee Department of Environment and Conservation.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Kimberly D. Hulvey, TVA Fleet Licensing Manager, at 423-751-3275.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 9th day of October 2019.

Respectfully, ames T. Polickoski Director, Nuclear Regulatory Affairs

Enclosure:

Change Instructions to the June 7, 2019, License Amendment Request cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation

Enclosure Change Instructions to the June 7, 2019, License Amendment Request (9 Pages)

1. Replace Enclosure Page E2 of 7 to include License Amendment 121 as a Relevant Amendment to the WBN1 TS 3.0 changes, and to rescind the change to WBN1 TS 3.6.15.

2. Replace Attachment 1 Page iii for WBN1 to correct a typographical error in the designation of the TS 3.7.16 page number.

3. Replace Attachment 1 Pages 3.0-4 and 3.0-6 for WBN1 to reflect the current pages of Record, which include License Amendment 121. Delete Attachment 1 Page 3.0.7, which was removed with License Amendment 121.

4. Delete Attachment 1 Page 3.6-40 and Attachment 3 Page 3.6-40 to rescind change to WBN1 TS 3.6.15.

5. Delete Attachment 5 Pages B 3.6-97 and B 3.6-98 to rescind change to WBN1 TS 3.6.15.

Note: General page instructions are provided in green font. Specific changes on each page are provided in red font.

CNL-19-086 E-1 of 1

Replace this page Enclosure in the Enclosure to the LAR 1.0

SUMMARY

DESCRIPTION In accordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) 50.90, "Application for amendment of license, construction permit, or early site permit," Tennessee Valley Authority (TVA) is requesting a license amendment to the Watts Bar Nuclear Plant (WBN) Units 1 and 2 Technical Specifications (TS). The proposed amendment would modify the TS by making various administrative changes.

This includes:

• Elimination of historical one-time License Amendments from the Unit 1 and Unit 2 TS.

• Replacing dated TS Figures 4.1-1 and 4.1-2 with analogous text for Units 1 and 2.

• Revising Unit 2 TS 3.7.7 and 3.9.6 for consistency with the WBN Unit 1 TS.

• Correcting the Table of Contents (TOC) based on previous License Amendments.

2.0 DETAILED DESCRIPTION

2.1 DESCRIPTION

OF THE PROPOSED CHANGE The following TS changes are being made by this License Amendment Request (LAR).

2.2.1 One-Time License Amendment Removal The following table describes the one-time TS that are being removed and the originating License Amendments.

Unit Technical Information Being Removed Relevant Specification Amendments WBN1 TS 3.0 Delete Table SR 3.0.2-1 (and pages) and the text 114 , 121 invoking it in SR 3.0.2.

WBN1 TS 3.5.2 Delete Note in Frequency column of SR 3.5.2.3. 43 WBN1 TS 3.6.6 Delete footnote for Completion Time of Condition A. 93 WBN1 TS 3.6.8 Delete footnote for LCO 3.6.8, Condition A and 10 Condition B. Delete footnote for SR 3.6.8.1.

WBN1 TS 3.6.12 Delete Note in Frequency column of SR 3.6.12.3, SR 3 3.6.12.4, and SR 3.6.12.5.

WBN1 TS 3.6.15 Delete footnotes regarding Penetration 1-EQH-271- 59 0010 and 11 in the Note to Condition B.

WBN1 TS 3.7.8 Delete Condition C and associated footnote. 69 WBN1 TS 5.7.2.19 Delete second paragraph regarding conducting the 63 10-year Type A test.

WBN2 TS 3.0 Delete Table SR 3.0.2-1 (and pages) and the text 3, 10, 12, 13, invoking it in SR 3.0.2. 14 WBN2 TS 5.7.2.19 Delete Table-5.7.2-1 (and page) and the text invoking 11 it in TS 5.7.2.19.

CNL-19-038 E2 of 7

3.7.16 Component Cooling System (CCS) - Shutdown . . . . . . . . . . . . 3.7-33 3.7.17 Essential Raw Cooling Water (ERCW) System - Shutdown . . . 3.7-36 Replace this page TABLE OF CONTENTS in Attachment 1 to the LAR 3.7 PLANT SYSTEMS (continued) 3.7.3 Main Feedwater Isolation Valves CMFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves . . . . . . 3.7-7 3.7.4 Atmospheric Dump Valves CADVs) . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST) . . . . . . 3.7-15 3.7.7 Component Coo1i ng System CCCS) . . . . . . . . . . 3.7-17 3.7.8 Essential Raw Cooling Water CERCW) System . . . . 3.7-19 3.7.9 Ultimate Heat Sink (UHS) . . . . . . . . . . . . 3.7-21 3.7.10 Control Room Emergency Ventilation System CCREVS) . 3.7-22 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) . . . . . . . . . . . . . . 3.7-25 3.7.12 Auxiliary Building Gas Treatment System CABGTS) 3.7-27 3.7.13 Fuel Storage Pool Water Level 3.7-29 3.7.14 Secondary Specific Activity 3.7-30 3.7.15 Spent Fuel Assembly Storage 3.7-31 3.8 ELECTRICAL POWER SYSTEMS . . . . 3.8-1 3.8.1 AC Sources -Operating .. . 3.8-1 3.8.2 AC Sources - Shutdown . . . . . . . . . . . 3.8-18 3.8.3 Diesel Fuel Oil. Lube Oil. and Starting Air 3.8-21 3.8.4 DC Sources - Operating . 3.8-24 3.8.5 DC Sources - Shutdown . . . . . . 3.8-30 3.8.6 Battery Cell Parameters . . . . 3.8-33 3.8.7 Inverters - Operating . . . . . . 3.8-37 3.8.8 Inverters -Shutdown . . . . . . 3.8-39 3.8.9 Distribution Systems-Operating 3.8-41 3.8.10 Di stri but ion Systems - Shutdown . 3.8-43 3.9 REFUELING OPERATIONS . . . . . . . . 3.9-1 3.9.1 Boron Concentration . . . . . . . . . 3.9-1 3.9.2 Unborated Water Source Isolation Valves 3.9-2 3.9.3 Nuclear Instrumentation . . . . . . . . . 3.9-4 3.9.4 Containment Penetrations . . . . . . . . 3.9-6 3.9.5 Residual Heat Removal CRHR) and Coolant Circulation-High Water Level . . . . 3.9-8 3.9.6 Deleted Residual Heat Removal CRHR) and Coolant Ci rcu1at ion - Low Water Leve1 . . . . 3.9-10 3.9.7 Refueling Cavity Water Level . . . . . . . . . . 3.9-12 3.9.8 Reactor Building Purge Air Cleanup Units .. 3.9-14 3.9.9 Spent Fuel Pool Boron Concentration .. 3.9-16 4.0 DESIGN FEATURES 4.0-1 4.1 Site . . . . . 4.0-1 3.9.10 Decay Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.9-17 4.2 Reactor Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.0-1 4.3 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.0-2 (continued)

Replace this page in Attachment 1 to the LAR SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. In addition, for each of the SRs listed in Table SR 3.0.2-1 the specified Frequency is met if the Surveillance is performed on or before the date listed on Table SR 3.0.2-1. The Surveillance Frequency extension limits expire on the dates listed in Table SR 3.0.2-1 or when the unit enters MODE 5, whichever occurs first.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

Watts Bar-Unit 1 3.0-4 Amendment42, 114,121

Replace this page in Attachment 1 to the LAR SR Applicability Delete this page 3.0 Table SR 3.0.2-1 (continued)

Frequency Surveillance Requirement (SR) Description of SR Requirement Extension Limit Perform RTS Instrumentation Actuation Logic Test of 10/1/18 3.3.1.5, Table 3.3.1-1, Function 19 Automatic Trip Logic Perform Engineered Safety Feature Actuation System 10/1/18 3.3.2.2, Table 3.3.2-1, Function 1.b (ESFAS) Instrumentation Actuation Logic Test of Safety lniection - Automatic Actuation LoQic and Actuation Relays 3.3.2.2, Table 3.3.2-1, Function 2.b Perform ESFAS Instrumentation Actuation Logic Test of 10/1/18 Containment Spray - Automatic Actuation Logic and Actuation Relays 3.3.2.2, Table 3.3.2-1, Function 3.a(2) Perform ESFAS Instrumentation Actuation Logic Test of 10/1/18 Containment Isolation - Phase A Isolation 3.3.2.2, Table 3.3.2-1, Function 3.b(2) Perform ESFAS Instrumentation Actuation Logic Test of 10/1/18 Containment Isolation - Phase B Isolation 3.3.2.2, Table 3.3.2-1, Function 4.b Perform ESFAS Instrumentation Actuation Logic Test of 10/1/18 Steam Line Isolation - Automatic Actuation Logic and Actuation Relays 3.3.2.2, Table 3.3.2-1, Function 5.a Perform ESFAS Instrumentation Actuation Logic Test of 10/1 /18 Turbine Trip and Feedwater Isolation - Automatic Actuation LoQic and Actuation Relays 3.3.2.2, Table 3.3.2-1, Function 6.a Perform ESFAS Instrumentation Actuation Logic Test of 10/1 /18 Auxiliary Feedwater - Automatic Actuation Logic and Actuation Relays 3.3.2.2, Table 3.3.2-1, Function 7.a Perform ESFAS Instrumentation Actuation Logic Test of 10/1/18 Automatic Switchover to Containment Sump - Automatic Actuation Loaic and Actuation Relays 3.3.6.2, Table 3.3.6-1, Function 2 Perform Containment Vent Isolation Instrumentation 10/1/18 Actuation Logic Test of Automatic Actuation Logic and Actuation Relays Watts Bar-Unit 1 3.0-6 Amendment 114, 121

Delete this page in Attachment 1 to the LAR Delete this page SR Applicability 3.0 Table SR 3.0.2-1 Frequency Surveillance Requirement (SR) Description of SR Requirement Extension Limit Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in s 1O seconds, 3.8.1.19 11/30/17

2. energizes auto-connected emergency loads through load sequencer,

3. achieves steady state voltage: 21! 6800 V and s 7260 V,

4. achieves steady state frequency 21! 59.8 Hz and s 60.1 Hz, and

5. supplies permanently connected and auto-connected emergency loads for 21! 5 minutes.

Watts Bar-Unit 1 3.0-7 Amendment 114

Delete this page in Shield Building Attachment 1 to S.6.15 the LAR 3.6 CONTAINMENT SYSTEMS 3.6.15 Shield Building LCO 3.6.16 The Shield Bulldlng shall be OPERABLE.

APPLICABILITY: MODES 1, 2, S, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shield building Inoperable; A.1 Restore shield bullding to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

B. ----NOTE------ 8.1 Restore annulus pressure B hours Annulus pressure within limits.

requirement Is not applicable during venting operations, required annulus entries, or AuxHiary Building Jsolallons not exceeding 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> In duration. or while Penetration 1-EQH-271-0010 or 1 *EOH*

271*0011 In the Shield ,.

Building dome fs open until annulus pressure Is restored.*

Annulus pressure not within limlts.

C. Required Action and C.1 Be lnMODE3. 6hours associated Completion Time not met.

0.2 Bein MOOE 5. S6hours The combined opening time of Penetrations 1-EQH-271-0010 or 1-EQH-271-00111s limited to a total time of five hours a day, six days a week during Cycle 7 operation.

2. Penetrations 1-EQH-271-0010 or 1-EOH-271*0011 In the Shield Building Dome may not be opened If In Action Conditions LOO 3.6.9A or 3.8.1 B.

3 Upon opening Penetration 1-EQH-271-0010 or 1-EOH-271-0011 In the Shield Bufldfrig Dome", both

. *eGTS control loop shall be placed lri ihe*A.:AutoStand-by posftion and returned to normal position following closure of penetration. . *- * ,. . ,

Walls Bar-Unit 1 3.6-40 Amendment No. 59

Delete this page in Shield Building Attachment 3 to 3.6.15 the LAR 3.6 CONTAINMENT SYSTEMS 3.6.15 Shield Building LCO 3.6.15 The Shield Building shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shield Building inoperable. A.1 Restore Shield Building to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

B. ------------NOTE------------------ B.1 Restore annulus pressure 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Annulus pressure requirement within limits.

is not applicable during ventilating operations, required annulus entries, or Auxiliary Building isolations not exceeding 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in duration.

Annulus pressure not within limits.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Watts Bar-Unit 1 3.6-40 Amendment 59, ___

Delete this page in Attachment 5 to Shield Building the LAR B 3.6.15 BASES ACTIONS A.1 In the event shield building OPERABILITY is not maintained, shield building OPERABILITY must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours is a reasonable Completion Time considering the limited leakage design of containment and the low probability of a Design Basis Accident occurring during this time period.

B.1 The Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is based on engineering judgment. The normal alignment for both EGTS control loops is the A-Auto position. With both EGTS control loops in A-Auto, both trains will function upon initiation of a Containment Isolation Phase A (CIA) signal. In the event of a LOCA, the annulus vacuum control system isolates and both trains of the EGTS pressure control loops will be placed in service to maintain the required negative pressure. If annulus vacuum is lost during normal operations, the A-Auto position is unaffected by the loss of vacuum. This operational configuration is acceptable because the accident dose analysis conservatively assumes the annulus is at atmospheric pressure at event initiation. (Ref. 3)

A Note has been provided which makes the requirement to maintain the annulus Note: pressure within limits not applicable for a maximum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during: Ventilating The highlighted text on operations, Required annulus entries, or Auxiliary Building isolations. Ventilating this page and the operations include containment venting, the Reactor Building Purge Ventilating following page was ystem alternate containment pressure relief function, and testing of the incorporated as part of Emergency Gas Treatment system. In addition to Note makes the requirement to Amendment 59. This maintain the annulus pressure within limits not applicable while Penetration 1-amendment also added a EQH-271-0010 or 1-EQH-271-0011 in the Shield Building dome is open until series of notes to annulus pressure is restored. Allowing one of the Shield Building dome Technical Specification penetrations to be open is based on provisions being in place to close it within 3.6.15. As stated in fifteen minutes of LOCA initiation. Limiting the time for opening either of the NRCs Safety Evaluation penetrations to a combined total of five hours a day, six days a week keeps the for Amendment 59 amount of time the Shield Building is inoperable to approximately 60 percent of (NRCs letter dated the eight hour completion time for LCO B.

January 6, 2006), these controls were only During normal plant operation, the Annulus is maintained at a negative pressure applicable until WBN equal to or more negative than -5 inches water gauge (wg) by the Annulus Unit 1 entered Mode 5 at Vacuum Control subsystem (non-safety related) of the Emergency Gas the start of the Cycle 7 Treatment System (EGTS). One train (loop) of the Annulus Vacuum Control refueling outage. The subsystem is operating (controls in A-Auto) and one train is in standby (controls in highlighted text in this A-Auto Stand-by).

Bases section and the notes in Technical Opening Shield Building dome Penetration 1-EQH-271-0010 or 1-EQH-271-0011 Specification 3.6.15 will be during Modes 1-4 will result in the Annulus pressure becoming more positive than deleted via a future the -5 inches wg required by Technical Specification 3.6.15. When the Annulus amendment to the pressure becomes more positive than -0.812 inches wg, the EGTS control Technical Specifications. system perceives that the loop in A-Auto (i.e., the operating train) has failed.

Control of Annulus pressure is then transferred to the loop in A-Auto Stand-by (i.e., the train in standby). Since the loop originally controlling Annulus pressure is (continued)

Watts Bar-Unit 1 B 3.6-97 Revision 15, 29, 101, 129

Delete this page in Attachment 5 to Shield Building the LAR B 3.6.15 BASES ACTIONS B.1 (continued) perceived to have failed, only one control loop (the controller originally in A-Auto Stand-by) remains functional. If a single failure of the remaining control loop were to occur, this would result in both control loops failing and would render the safety-related portion of EGTS inoperable. To prevent this situation, operator action will be taken to place both EGTS control loops in the A-Auto Stand-by position when the annulus differential pressure is more positive than a -5 inches wg. If EGTS is subsequently initiated in this configuration, both trains of EGTS will start. Absent a single failure, one EGTS control loop train will manually be returned to the A-Auto position when the Annulus differential pressure becomes more negative than -0.812 inches wg. In addition, the remaining EGTS control loop train will be turned off, then immediately placed in the A-Auto Stand-by position (i.e., the associated isolation valves shall be closed by means of the MCR hand switch). This action is in the design and is necessary to restore the EGTS to the normal operational configuration and to prevent excess EGTS exhaust and Annulus in-leakage.

Additional assurance is administratively provided of support system operability by restricting the opening of Penetration 1-EQH-271-0010 or 1-EQH-271-0011 if in Actions for LCO 3.6.9.A EGTS, or 3.8.1.B, AC Sources - Operating. If a hatch is opened and one of the above systems becomes inoperable, the hatch will be closed.

C.1 and C.2 If the shield building cannot be restored to OPERABLE status within the required Completion Time, 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 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 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.

SURVEILLANCE SR 3.6.15.1 REQUIREMENTS Verifying that shield building annulus negative pressure is within limit (equal to or more negative than - 5 inches water gauge, value does not account for instrument error, Ref. 2) ensures that operation remains within the limit assumed in the containment analysis. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency of this SR was developed considering operating experience related to shield building annulus pressure variations and pressure instrument drift during the applicable MODES.

SR 3.6.15.2 Maintaining shield building OPERABILITY requires maintaining each door in the access opening closed, except when the access opening is being used for normal transient entry and exit. The 31 day Frequency of this SR is based on engineering judgment and is considered adequate in view of the other indications Watts Bar-Unit 1 B 3.6-98 Revision 15, 29, 101, 129