RBG-47006, Revisions to the Technical Requirements Manual and the Technical Specification Bases

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Revisions to the Technical Requirements Manual and the Technical Specification Bases
ML100541832
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/17/2010
From: Roberts J
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
G9.5, RBF1-10-0021, RBG-47006
Download: ML100541832 (37)
v • d • e


Text

Entergy Operations, Inc.

River Bend Station 5485 U. S. Highway 61 N St. Francisville, LA 70775 Tel 225 381 4149 L:!IEtt1W~ Fax 225 635 5068 jrober3@entergy.com Jerry C. Roberts Director, Nuclear Safety Assurance RBG-47006 February 17, 2010 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Revisions to the Technical Requirements Manual and the Technical Specification Bases River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 File No.: G9.5 RBF1 0021

Dear Sir or Madam:

Pursuant to 10CFR50.71 (e), Entergy Operations, Inc., (EOI) herein submits changes to the River Bend Station (RBS) Technical Requirements Manual (TRM). The revised pages cover the changes made during the period of August 29, 2008, through February 17, 2010. This includes TRM revisions 118 through 122.

Pursuant to RBS Technical Specification (TS) 5.5.11, revised pages for the Technical Specification (TS) Bases pages are included. The revised pages cover the changes made during the same period stated above. This includes TS Bases revisions 135 through 139 As required by 10CFR50.71 (e), the below affirmation certifies that the information in this submittal accurately reflects changes made since the previous submittal, as necessary to represent information and analyses submitted or prepared pursuant to NRC requirements.

4-oc

RBG-47006 February 17, 2010 Page 2 of 2 If you have any questions, please call David Lorfing at 225-381-4157.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February 17, 2010.

Sincerely Jerry C. Roberts Director - Nuclear Safety Assessment

Enclosure:

Technical Requirements Manual Revision Pages Technical Specifications Bases Revision Pages cc: U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 (w/o enclosure)

Senior Resident Inspector River Bend Station

Enclosure RBG-47006 Technical Requirements Manual Revision Pages Technical Specifications Bases Revision Pages

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES PAGE NUMBER I REV PAGE NUMBER I REV- PAGE NUMBER I REV TR 3.6-7 (20iii) 108 TR 3.7-28 (15xxi) 58 TR 3.11-6 18 TR 3.6-8 (20iv) 68 TR 3.7-29 (15xxii) 95 TR 3.11-7 14 TR 3.6-9 (20v) 108 TR 3.7-30 (15xxiii) 5 TR 3.11-8 5 TR 3.6-10 (20vi) 108 TR 3.7-31 (15xxiv) 5 TR' 3'11-9 5 TR 3.6-11 (20vii) 69 TR 3.7-32 (15xxv) 18 TR 3.11-10 75 TR 3.6-12 (22i) 12 TR 3.7-33 (15xxvi) 5 TR 3.11-11 5 TR 3.6-13 (28i) 90 TR 3.7-34 (15xxvii) 5 TR 3.11-12 5 TR 3.6-14 (28ii) 35 TR 3.7-35 (15xxviii) 5 TR 3.I1-13 5 TR 3.6-15 (30i) 5 TR 3.8-1 (15i) 76 TR 3.11-14 5 TR 3.6-16 (35i) 77 TR 3.8-2 (15ii) 65 TR 3.11-15 5 TR 3.6-17 (36i) 77 TR 3.8-3 (15iii) 76 TR 3.11-16 5 TR 3.6-18 (40i) 100 TR 3.8-4 (19i) 5 TR 3.11-17 5 TR 3.6-19 (50i) 107 TR 3.8-5 (20i) 76 TR 3.12-1 5 TR 3.6-20 (52i) 63 TR 3.8-6 (23i) 114 TR 3.12-2 5 TR 3.6-21 (54i) 98 TR 3.8-7 (27i) 55 TR 3.12-3 77 TR 3.8-8 (42i) 81 TR 3.12-4 77 TR 3.6-23 (59i) 5 TR 3.8-9 (42ii) 81 TR 3.12-5 59 TR 3.6-24 (61i) 18 TR 3.8-10 (42iii) 81 TR 3.12-6 41 TR 3.6-25 (70i) 96 TR 3.8-11 (42iv) 118 TR 3.12-7 41 TR 3.6-26 (70ii) 96 TR 3.8-12 (42v) 5 TR 3.12-8 5 TR 3.6-27 (72i) 5 TR 3.8-13 (42vi) 95 TR 3.12-9 5 TR 3.7-1 (4i) 5 TR 3.8-14 (42vii) 95 TR 3.12-10 41 TR 3.7-2 (4ii) 5 TR 3.8-15 (42viii) 95 TR 3.12-11 41 TR 3.7-3 (4iii) 5 TR 3.8-16 (42ix) 95 TR 3.12-12 77 TR 3.7-4 (4iv) 5 TR 3.8-17 (42x) 95 TR 5-1 87 TR 3.7-5 (8i) 90 TR 3.8-18 (42xi) 113 TR 5-2 117 TR 3.7-6 (11i) 26 TR 3.8-19 (42xii) 5 TR 5-3 5 TR 3.7-7 (14i) 5 TR 3.8-20 (42xiii) 5 TR 5-4 53 TR 3.7-8 (15i) 94 TR 3.8-21 (42xiv) 5 TR 5-5 65

,TR 3.7-9 (15ii) 109 TR 3.8-22 (42xv) 30 TR 5-6 94 TR 3.7-10 (15iii) 5 TR 3.8-23 (42xvi) 88 TR 5-7 23 TR 3.7-11 (15iv) 93 TR 3.9-1 (7i) 84 TR 5-8 .. 5 TR 3.7-12 (15v) 5 TR 3.9-2 (7ii) 72 TR 5-9 5 TR 3.7-13 (15vi) 5 TR 3.9-3 (13i) 85 TR 5-10 5 TR 3.7-14 (15vii) 15 TR 3.9-4 (13ii) 5 TR 5-11 77 TR 3.7-15 (15viii) 5 TR 3.9-5 (13iii) 70 TR 5-12 5 TR 3.7-16 (15ix) 5 TR 3.9-6 (13iv) 5 TR 5-13 94 TR 3.(7-17 (15x) 58 TR 3.9-7 (13v) 5 TR 5-14 33 TR 3.7-18 (15xi) 5 TR 3.9-8 (13vi) 5 TR 5-15 53 TR 3.7-19 (15xii) 79 TR 3.9-9 (13vii) 54 TR 5-16 53 TR 3.7-20 (15xiii) 5 TR 3.9-10 (13viii) 103 TR 5-17 87 TR 3.7-21 (15xiv) 15 TR 3.9-11 (13ix) 103 TR 5-18 53 TR 3.7-22 (15xv) 58 TR 3.9-12 (13x) 104 TR 5-19 53 TR 3.11-1 83 TR 3.7-23 (15xvi) 5 TR 3.11-2 5 TR 5-20 53 TR 3.7-24 (15xvii) 5 TR 3,.11-3 5 TR 5-21 94 TR 3.7-25 (15xviii) 58 TR 3.11-4 5 TR 5-22 8 TR 3.7-26 (15xix) 5 TR 3.11-5 5 TR 3.7-27 (15xx) 5 RIVER BEND TR-b Revision 118

I I Electrical Equipment Protective, Devices TR 3.8..11 SURVEILLANCE REQUIREMENTS (continued) "__...*........

SURVEILLANCE',. FREQUENCY TSR 3..8.11.4 ,: NOTES --------------------- . .-.---

Testing of .these'. mtor: starters shall .

consist of injecting a: current -in.:,

accordance with the' manufacturer, recommendations,' and.verifying: that the.

.. motor starter.. operates "to interupt the current within. the associat ed thermal-overload time delayb.and width."for thdtý current'. as specified by th.,

manuf acturer.

Motor starters found inope/able ',during

-functional'. testing shall be restored. to.

OPERABLE'ý status prior to resumin'gý "

oeaion.

Func*i..anay test a presentati8* ' , 1.8 months:on a'

..sampie'ofo at least 10% o'f each type of' STAGGERED TEST motobr.starter used for.penetration ' BA'SIS' redundant'. overcurrent protection.

TS"R 3. 11.5 ' Subject each circuit breaker to a60: mont.hs inspectiionh; and preventive maintenanceL J, progirtam!;:-in., accordance with procedures...

reparad'r:in. onjunction with its.

manufacturer'~s recommendations.

RIVER BEND -. TR:3.8-11 'Revision 118 (42 iv):

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES PAGE NUMBER I REV +

PAGE NUMBER I REV PAGE NUMBER I REV i 77 TR 3.3-28 (52ii) 5 'TR 3.3-74 (74i) 105 ii 100 TR 3.3-29 (52iii) 5 TR 3.3-75 (77i) 90 iii 98 TR 3.3-30 (52iv) 116 TR 3.3-76 (77ii) 5 iv 104 TR 3.3-31 (52v) 5 TR 3.3-77 (77iii) 44 v 77 TR 3.3-32 (57i) 80 TR 3.3-78 (77iv) 44 vi 77 TR 3.3-33 (57ii) 97 TR 3.3-79 (77v). 44 TR 1-1 77 TR 3.3-34 (57iii) 40 TR 3.3-80 (77vi) 5 TR 1-2 77 TR 3'.3-35 (57iv) 123' TR 3.3-81 (77vii) 5 TR 1-3 77 TR 3.3-36 (57v) 13 TR 3.3-82 (77viii) 5 TR 1-4 77 TR 3.3-37 (57vi) 87 TR 3.3-83 (77ix) 5 TR 3 .0-1 115 TR 3.3-38 (57vii) 16 TR 3.3-84 (77x) 5 TR 3 .0-2 115 TR 3.3-39 (57viii) 28 TR 3.3-85 (77xi) 5 TR 3.0-3 92 TR 3.3-40 (601) 62 TR 3.3-86 (77xii) 77 TR 3.0-4 115 TR 3.3-4i (60ii) 62 TR 3.3-87 (7.7xiii) .5 TR 3.1-1 (10i) 5 TR 3.3-42 (61i) 62 TR 3.3-88 86 TR 3 .1-2 (17i) .84 TR 3.3-43 (61ii) 98 TR 3,.3-89 90 TR 3 .1-3 (17ii) 90 TR 3.3-44 (65i) 9 TR 3.3-90 (40i) 103 TR 3 .1-4 (25i) 5 TR 3.3-45 (67i) 72 TR 3.4-1 (41) 5 TR 3.2-1 (6i) 74 TR 3.3-46 (67ii) 75 TR 3.4-2 (5i) 48 TR 3.3-1 (6i) 5 TR 3.3-47 (67iii) 75 TR 3.4-3 (5ii) 86 TR 3.3-2 (9i) 48 TR 3.3-48 (71i) 85 *TR 3.4-4 (11i) 5 TR 3.3-3 (9ii) 72 TR 3.3-49 (71ii) 91 TR 3.4-5 (13i) 5 TR 3.3-4 (9iii) 78 TR 3. 3-50 (711iii) 5 TR 3.4-6 (16i) 49 TR 3.3-5 (15i) 5 TR 3.3-51 (7liv) 38' TR 3.4-7 (16ii) 107 TR 3.3-6 (15ii) 5 TR 3.3-52 (71v) 38 TR 3.4-8 (16iii) 75 TR 3.3-7 (17i) 5 TR 3.3-53 (71vi) 77 TR 3.4-9 (19i) 5 TR 3.3-8 (17ii) 18 TR 3.3-54 (71vii) 114 TR 3.4-10 (32i) 101 TR 3.3-9 (17iii) 18 TR 3.3-55 (71viii) 5 TR 3.4-11 (32ii) 71 TR 3.3-10 (18i) 61 TR 3.3-56 (71ix) 79 TR 3. 4-12. (32iii) 5 TR 3.3-11 (18ii) 86 TR 3.3-57 (71x) , 5 TR 3.4-13 (33i) 5 TR 3.3-12 (24i) 5 TR 3.3-58 (71Xi) 40 TR 3.4-14 (33ii) 5 TR 3 .3-13 (24ii) 109 TR 3.3-59 (71xii) 5 TR 3.4-15 .(33iii) 39 TR 3.3-14 (24iii) 109 TR 3.3-60 (71xiii) 40 TR 3.4-16 (33iv) 5 TR 3.3-15 (24iv) 109 TR 3.3-61 (71xiv) 40 TR 3.4-17 (33v) 5 TR 3.3-16 (28i) 78 TR 3.3-62 (7 1xv) 106 TR 3.5-1 (51) 5 TR 3.3-17 (31i) 72 TR 3.3-63 (7 lxvi) 119 TR 3.5-2 '(5ii) 5 TR 3.3-18 (37i) 5 TR 3.3-64 (7 lxvii) 119 TR 3.5-3 (12i) 77 TR 3.3-19 (43i) 9 TR 3.3-65 (7 lxviii) 67 TR 3.5-4 (12ii) 77 TR 3.3-20 (43ii) 9. TR 3.3-66 (7ixix) 96 TR 3.6-1 (2i) 11 TR 3.3-2-1 (43iii) 9 TR 3.3-67 (71,x) 51 TR 3.6-2 (2ii) 108 TR. 3.3-22 (43 iv) 9 TR 3.3-68 (71xxi) 51 TR 3.6-3 (8i) 73 TR 3.3-23 (43v) 9 TR 3.3-69 (71xxii) 78 TR 3.6-3a (8ii) 13 TR 3.3-24 (43vi) 77 TR 3.3-70 (71xxiii) 75 TR 3.6-4' (8iii) 73 TR 3.3-25 (43vii) 5 TR 3.3-71 (7 lxxiv) 90 TR 3.6-5 (20i), 11 TR 3.3-26 (47i) 9 TR 3.3-72 (7 lxxv) 26 TR 3.6-6 (20ii) 77 TR 3.3-27 (52i) 116 TR 3.3-73 (7lxxvi) 5 RIVER BEND TR-a' Revision 119

Seismic Monitoring Instrumentation TR 3.3.7.5 SURVEILLANCE REQUIREMENTS

--------------------- NOTE----------------------------------------

Refer to Table,3.3.7.5-1 to determine which TSRs apply for each instrument SURVEILLANCE FREQUENCY TSR 3.3.7.5.1 Perform a CHANNEL CHECK. 3,1 days TSR 3.3.7.5.2 Perform a CHANNEL FUNCTIONAL TEST. 6 months TSR 3.3.7.5.3 Perform a CHANNEL CALIBRATION. 18 months*

TSR 3.3.7.5.4 ---------------- NOTE---------------------

Not required to be performed until instrument is actuated by a seismic event

ý 0.01 g.

Restore to OPERABLE. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND j Perform a CHANNEL CALIBRATION.' 5 days AND Initiate action to retrieve and analyze Immediately data from actuated instruments to after event determine the magnitude of vibratory ground motion AND Initiate action to prepare and submit a Immediately Special Report to the Commission, after event pursuant to Technical Requirement 5.6.9, within.40 days describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety.

  • For Cycle 15, the FREQUENCY of TSR 3.3.7.5.3 as applied to ERS-NMEIB / FERS-NBR2I shall be 20 months.

RIVER BEND TR 3.3-63 Revision 119 (71xvi)

Seismic Monitoring Instrumentation TR 3.3.,7.5 TABLE 3.3.7.5-1 (Page 1 of 1)

SEISMIC MONITORING INSTRUMENTATION MINIMUM SURVEILLANCE MEASUREMENT INSTRUMENTS REQUIREMENTS RANGE OPERABLE

1. Triaxial Time-History Acceler6graphs
a. Reactor Bldg Mat EL 70' 0" TSR 3 .3.7.5.1 0 + 1.0 g TSR 3.3.7*.5'.2 (ERS-NBEIA / ERS-NBR2H) TSR 3.3.7. 5.3 TSR 3.3.7.5.4
b. Reactor Bldg Ext Shield Wall EL TSR 3.3.7.5.1 0 + 1.0 g 232' 0" TSR 3.3 .7.5.2 TSR 3. 3. 7. 5. 3 (ERS-NBEIB / ERS-NBR21)

TSR 3. 3. 7 5. 4

c. Reactor Bldg Drywell EL 151' 0" TSR 3.3.7.5.1 0 +/- 1.0 g TSR 3.3.7.5.2 (ERS-NBEIC / ERS-NBR2J) TSR 3.3.7.5.3 TSR 3.3.7.5.4
d. Free Field - Grade Level TSR 3.3.7.5.1 0 + 1.0 g TSR 3.3.7.5.2 (ERS-NBElD I ERS-NBR2K) TSR 3.3.7.5.3 TSR 3.3.7.5.4
2. Triaxial Peak Accelerographs
a. Reactor Bldg SLCS Storage Tank 1 TSR 3.3.7..5.3 0 + 10.0 g (ERS-NBR2A) TSR 3.3.7.5.4
b. Reactor Bldg - RHR Inj. Piping 1 TSR 3.3.7.5.3 0 + 10.0 g (ERS-NBR2B) TSR 3.3.7.5.4
c. Aux. Bldg Service Water Piping 1 TSR 3.3.7.5.3 0 10.0 g (ERS-NBR2C) TSR 3.3.7.5.4
3. Triaxial Seismic Switches
a. Reactor Bldg Mat EL 70' 0' (a) (b)

TSR 3.3.7.5.1 0.025 to (ERS-NBS4B)

TSR 3.3.7.5.2 0.25g TSR 3.3.7.5.3 TSR 3.3.7.5.4

b. Free Field EL 95' (ERS-NBS4A) (d) TSR 3.3.7.5.1(b) 0.005 to TSR 3.3.7.5.2 0.05 g TSR 3.3.7.5.3 TSR 3.3.7.5.4
4. Triaxial Response - Spectrum Recorders
a. Reactor Bldg Mat EL 70' 0" (c) TSR 3.3.7.5.1 0+/-2g (ERS-NBS2D) TSR 3.3.7.5.2 TSR 3.3.7.5.3 TSR 3.3 .7.5.4

'TSR

b. Reactor Bldg Floor EL 141' 0" 1 TSR 0+/-2g 3.3.7.5.3 (ERS-NBS2F) TSR 3.3.7.5.4 0+2,g
c. Auxiliary Bldg Mat EL 70' 0" 1 TSR 3.3.7.5.3 (ERS-NBS2G) TSR 3.3.7.5.4
d. Auxiliary Bldg Floor EL 141' 0" 1 TSR 3.3.7.5.3 0 +/- 2 g (ERS-NBS2E) TSR 3.3.7.5.4 (a) With control room indication and annunciation (SEISMIC EVENT HIGH).

(b) Except seismic trigger.

(c) With control room indication and annunciation (SEISMIC EVENT HIGH-HIGH).

(d) With control room indication and annunciation (SEISMIC TAPE RECORDING SYS START).

RIVER BEND TR 3 .3-64 Revision 119 (71xvii)

TECHNICAL REQUIREMENTS MANUAL

'LIST OF EFFECTIVE PAGES PAGE NUMBER I REV I PAGE NUMBER I REV PAGE NUMBER I REV TR 3 6-7 (20iii) 108 TR 3.-7-28 (15xxi) 58 TR 3.11-6 18 TR 3.6-8 (20iv) 68 TR 3.7-29 (15xxii) 95 TR 3.11-7 14 TR 3.6-9 (20v) 108 TR 3.7-30 (15xxiii) 5 TR 3.11-8 5..

TR 3.6-10 (20vi) 108 TR 3.7-31 (15xxiv) 5 TR 3.11-9 5 TR 3.6-11 (20vii) 69 TR 3.7-32 (15xxv) 18, TR 3.11-10 75 (

TR 3.6-12 (22i) 12 TR 3.7-33 (15xxvi) 5 TR 3.11-11 5 TR 3.6-13 (28i) 90 TR 3.7-34 (15xxvii) 5 TR 3.11-12 5

'TR 3.6-14 (28ii) 35 TR 3.7-35 (15xxviii) 5 TR 3 .11-13 5 TR 3.6-15 (30i) 5 TR 3.8-1 (15i) 120 TR 3 .11-14 5 TR 3.6-16 (35i) 77 TR 3.8-2 (15ii) 65 TR 3.11-15 5 TR 3.6-17 (36i) 77 TR 3.8-3 (15iii) 76 TR 3.11-16 5 TR 3.6-18 (40i) 100 TR 3.8-4 (19i) 5 TR 3.11-17 5 TR 3.6-19 (501) 107 TR 3.8-5 (20i) 76 TR 3.12-1 5

,TR 3.6-20 (52i) 63 TR 3.8-6 (23i) 114 TR. 3.12-2 5 TR 3 . 6-21 (54i) 98 TR 3.8-7 (27i) 55 TR 3.12-3 77 TR 3.8-8 (42i) 81 TR 3.12-4 77 TR 3.6-23 (59i) 5 TR 3.8-9 (42ii) 81 TR 3.12-5 59 TR 3.6-24 (61i) 18 TR 3.8-10 (42iii) 81 TR 3.12-6 41 TR 3.6-25 (70i) 96 TR 3.8-11 (42iv) 118 TR 3 .12-7 41 TR 3.6-26 (70ii) 96 TR 3.8-12 *(42v) 5 TR 3.12-8 5 TR 3 .6-27 (72i) 5 TR 3.8-13 (42vi) 95 TR 3.12-9 5 TR 3.7-1 (4i) 5 TR 3.8-14 (42vi) 95. TR 3.12-10 41 TR 3.7-2 (4ii) 5 TR 3.8-15 (42viii) 95 TR 3.12-11 41 TR 3 .7-3 (4iii) 5 TR' 3.8-16 (42ix) 95 TR 3 .12-12' 77 TR 3 .7-4 (4iv) 5 TR 3.8-17 (42x) 95 TR 5-1l 87 TR 3 7-5 (8i) 90 TR 3.8-18 (42xi) 113 TR 5-2 117 TR 3 7-6 (11i) 26 TR 3.8-19 (42xii) 5 TR 5.- 3 .5 TR 3.7-7 (14i) 5 TR 3.8-20 (42xiii) 5 TR 5-4 53 TR 3.7-8 (15i) 94 TR 3.8-21 (42xiv) .5 TR 5-5 65 TR 3.7-9 (1511) 109 TR 3.8-22 (42xv) 30 TR 5-6 94 TR 3.7-10 (15iii) 5 TR,3.8-23 (42xvi) 88 TR 5-7 23 TR 3.7-11 (15iv) 93 TR 3.9-1 (7i) 84 TR 5-8 5 TR 3.7-12 (15v) 5 TR 3.9-2 (7ii) 72 TR 5-9 5 TR 3 7-13 (15vi) 5 TR 3.9-3 (13i) 85 TR 5-10 .5 TR 3 7-14 (15vii) 15 TR 3.9-4 (13ii) 5 TR 5-11 77 TR 3 7-15 (15viii) 5 TR 3.9-5 (13iii) 70 TR 5-12 5 TR 3 7-16 (15ix) 5 TR 3.9-6 (13iv) 5 TR 5-13 94 TR 3 7-17 (15x) 58 TR 3.9-7 (13v) 5 TR 5-14 33 TR 3 7-18 (15xi) 5 TR 3.9-8 (13vi) 5 TR 5-15 53 TR 3 7-19 (15xii) 79- TR 3.9-9 (13vii) 54 TR 5-16 53 TR 3 7-20 (15xiii) 5 TR 3.9-1-0 (13viii) 103 TR 5-17 87 TR 3 7-21 (15xiv)' 15 TR 3.9-11 (13ix) 103 TR: 5-18 53 TR 3 .7-22 (15xv) 58 TR 3.9-12 (13x) 104 TR 5-19 53 TR 3.11-1 83 TR 3.7-23 (15xvi) 5 TR 3.11-2 5 TR 5-20 53 TR 3.7-,24 (15xvii) 5 TR 3.11-3 5 TR 5-21 94 TR 3 7-'25 (15xviii) 58 TR 3.11-4 5 TR 5-22 8 TR 3.7-26 (15xix) 5 TR 3.11-5 5 TR 3.7-27 (15xx) .5 RIVER BEND TR-b Revision 120

AC Sources Operating TR 3:.8:.I TR 3.8 ELECTRICAL POWER SYSTEMS TRý 3.88.11 AC Sources Operating.

-- --- - - - - --- - - - - - -NOT-----------------

1. The.: following surveil lance requil:rements ,'iapply. .to0 Technicai
.-.Specification LCO 3.8.1
. Failure to meet. these- surveillance requirements requires entry into Technical Specification LCO 3.8.1*:.,

2 ::When a: modified DG: start procedure. is not used to. satisfy SR

.. 1.2," TSR 3.8."1.7 must .be performe d.--

SURVEILLANCE REQUIREMENTS * - "'.'.:: -. ,..-

SURVEILLANCE FREQUENCY TSR- 8. 1. 1,1 TSR 3."8. 1._6 (Not Used)):

TSR:: 3,.8.l.ý-7_:j...----.----NOTEý-:.--

All:, DG, starts may be preceded by anh..

engine plrelube period and followed.,by] a

_warmup .period prior :to loading.-

When each s.DG ststared 'from: standby As specified..

' oTechni...

"clonditions'.for cal!:. Specification for SR 3.8.1B.7 SR 3.8.11.7:

a. For..DO lA,'and DG1B:, record: -Whether

,the-,DG.. achieves at least .450 rpm[ in

  • `1'0 seconds for trending'.
b. For DG 1C re'o'rd *whether the DG "aqchie.ves, at! least:,: 882 rpm in < 13 secondsfo6r.trendihg TSR. 3.8.1.8 - TSR 381. 1.1.(Not Used)
(continued):

3.8-1 Revision:

RIVER BEND ' 120, TR(15i).  : "* . "' ,'.}{ : ,

TECHNI CAL REQUIREMENTS, MANUAL LIST OF EFFECTIVE PAGES PAGE NUMBER I REV I PAGE NUMBER IREV 'I PAGE NUMBER 2

-~

'I REV

,TR 3.6 -7 (20iii) :08 108.

TR 3 .7-2~

58 TR 3 11-6

. .TR 3 .6-8 68 9 (lsxxii) 295 TR3. 11 -7 2

(20iv) TR 3.7-30 TR 3 .6,-9 108' ) (i5xxii i), 25 (20"') TR 3 7 -3(1 'rR 3 .11-9 TR 3.6- 10 108~ L2(1sxxiV')'~ 52 TR 3.11-1 (12vii) TR 3 .7-32 225 TR 3ý6-1~1 69 )"(l5xxv) 18 TR 3.1310 -11 TR 3.7-3'3 5 '

TR 3.6-12 (22i)' 12 5 T R 3.11-11 '"'752 TR 3-13.6 290 TR 3 2.-3 (l5xxvii) 5

..... 2'2"TR' 3. 6 -14 (28ii')" *35 "TR 3 . 73 2(lsxxvlll')2 "TR 3.11-13" 5

TR 3 .6-15 (30i) '5 'TR 3.8-1 (15i) 120 .TR 3.11-14<

5 TR. 3.6-16 (35i) 77 TR' 3.8- 2 (1511) 65< TR 3 .11-15

  • ,:* 7.

TR,3 .66-17 (36i) 77 TR 3 .8-3 (15111) .. 76 TR 3'.11-16 '2 5

'TR 3 .6-18' (40i) ,::,-";-i100C TR 3.8-4 (191) 5 TR 31.11-17 5 TR 3.6-19' (501) 107 TR 3.8-5 S(20i) 76 TR 3.12-13, TR 3 .6-'20'2 (52i) ; <' 63 222 2(23i)'< 2 114 TR 3.12-432, 2

TR 3.6-21' (541) 98 2TR' 3.8-'7 (27i) 55

< ::L] :9*<*: <rR 3.8-8 (42i) 81 TR 3.12-*) 41 4 TR 3.8-TR 3.6-23 (59i) 5 (4211) 81 TR '3.

3 .12-8 12<624 52, TR' 3.8-90 TR 3.6-24 (611i) I:?L!91 18 TR 3.8-11 (42111) 22 .TR3,1'2

. 9 67 TR 3 .6-25 (70i) 31)2:.: 96 (42iv) 118 59 TR 3.8-12 TR 3.6-26 (7011) 96 (42v) 41 TR 3.8 -13 TR 3.3'12'-7 TR 3.6-27 (72i) 5 (42vi) 95 ' "2 41 '

TR 3. 8-14

/TR 13.17-1 (4i), (42vii) 95 TR 3.12-91 TR 23.18-15 TR,3.7-'2 (4ii) 24 ~f(42viii) 121 2 5 ,

TR 3.7-3 (4iii TR '3 .8-16 .222(4 2 ix).4 2 952 TR 3.12-12' 53 TR 3.7-4 (4iv)'< ('4 2x) 95 TR 5-1 TR .3.8-18 2'2 TR 3.7.-5 (8i) 5 (42xi) 113 TR 5-2 941 ' 22 '2 TR 3.8-19 22

"ŽTR 3.7-6< (Ili) (42xi1) 5 TR 5-3 2 413 2 2'2'2 TR 3.8-i0 109 (,42xiia,) 5 TR 53,1-;105 5-4 TR 3.8-2C TR 3 .7-782 (15i)'.2 (42xiv) 25 TP5-5 2.27.2< '2 '22 2 5 TR. 3 .'8-,22 77 22 TR 3.7-9 (15ii) (4 2xv) TR~ 5-~6 TR 3.7-1(15iii) 94 (42xvi) TR 5'-7 TR 3 . 9-22 '284 TR 3.7-11 (15iv) ' 22(7i) TR 5:-8

'109 ,TR 3'2.9-~3 2 5 2 TR 3.7-12 (15v) 22'(7ij') 2 72 TR 5-9 52 TR '3 .9 -42 94

~ < TR 3.7-13 (l5vi) 25. 3<2 .9-5 2 85 TR 5-10 -;

233 22 2

'22

,'2'2 22 2

4 .Ž4'TR 2 23:.7~-14 (15vii) TR 3."9-6' '252 TR 5 -11 2 22 2222 2582 53 2

'TR 3.7-15 (l5viii) 'TR 3 .9-7 (13iv) ' 70 TR 5-12 2 TR 3.7-16 (i5ix) 15 ,TR '3. 9-8 5 TR 5-13 (13iv) 22 2 TR 3.7-17 (15x) TR 3 .9-5 5 'TR 5-14 5 (13v1)

TR 3.7-1i8 (l5xa) TR 3 .9-60 25 TR 5-15 22 is 2.. (1.3v11) '

>2<'TR 3.77.19 (15xii)/ TR 3 .9-71 54 TR 5-16 2

58. 2 53 TR 3.7-20 (l5xiii) TR 3.39-12 (l3viii) 103 TR ,5-17 94 2 TR 3.7-21 (15xiv) JR. 3.11-9 (l3ix) 222 1,03 ' TR, ,5 - 18 22 R 3.7-22 (l5xv) , (13x)2 2 '104 TR 1 TR 3.' 2 '22

'83 '2, 2 '2 2 (15xv1)' 5 TR 3 .'11"-3 5 TR 5-20 TR 3'.7-23 22 2 24 (1 Sxvii) 5 TR 3.11-24 5 TR 5-~21 2 TR ,3 .7-24 (l5xviii) 5 TR 5-22 ) 22 TR 3.7-26 (l5xix) TR 3.11- 5 5

ýTR 3Ž.7-27 (lsxx)'2 5 2.

22'2 <22

'2 2 2

'2 22 '2 22 . '2 RIVER PBEND:

TR- b TP Revision 121

Electrical Equipment Protective, Devices TR 3. 8.,11 7 TABLE 3.8.11-1 (page 4,7,of 7)

PRIMARY CONTAINMENT PENETRATION CONDUCTORP... -

OVERCURRENT. PROTECTION DEVICES'I C. 480 VAC Molded Case circuit Breakers (continued),

2:' Gould -Circuit Breaker Type 'A822 with-Gould Starter/Controller 7Ty'e ,FVR Lo cation' Cubicle ý.Ecilip; No'.

7 1EHS*MCC2A. 2A 1C4itMOVF~oiAlA.

1EHS*MCC2A - 5A: " 1lSWP*MMVAI/

-" EHS*MCC2A- - 5a, 1SWP,*MOV5B,

.".. EHS*MCC2A  : lSWPtMOVS,62A~>.

1EHS*MCCA, '6A, 1RCS*MOV58A~

1EHS*MCC2AB 6B IRCS*MOV59A

- - . IEHS*MCC2AB,: lSWP4M6VSd3A 1EHS*MCC2B' 1B, 1SFC*MOVl-26O.

1EHS*MCC2B 10, 1 SIFC'M0V139

.. IEHS*MCC2B lC41,*MOVF001B~

l swp*MOV4B.

1EHS*MCC2B.' ..

~SC j1SWP*MOV5SO2B7 1EHS*MCC2B '.- !RCs~MOvS8B.

.EH.S*MCC2B 1EHS*MCC2B,, 6B - ~ RCS*OV59B .

1EHS*tMCC2B,, 6C ;lSWP*MbVSO3B7.

lCCP*MOVi42K ii*.s*MCC2CB 2C >

lCCPWM0V14A

-"EHS*M6C2C 2D' 3A -, CPM*.MOV2A IEHS*MCC2C 3B 1,CPM*MOV3A.

1EHS*MCC2C lEHS*MCC2C 3C, 71E12*MOVFO,37A'.

4A IE,12'*MOVF042A 1iEHS*MCC2C 4B 1HVN*MOV22A.

.IEHS *MCC2C 4C IRCS*MOV60A

' 1EHS*MCC2D 5B 1RcslrMOV61A 1EHS.*MCC2C ~2 -

IEHS*MCC2C 1CPMMMOVA 5C 1B2l1*MOVF016>,"

1EHS*MCC2D .

1EI4*'MdC'2D., 1CPM*MIV2B~

1EHS*MCC2 2 " 2C, 4<1EHS*MCC2D 2D 1lCPM*MOV3B

< 1EHS*MCC2D, 3A ICPMI*MOV4B 71EHS*MCC2D, 3B 7lCPIP*MOV1O4, 1EHS*MC:C2D',

3C 1ESl*MOVFO,63

_1EHS*MCC2iD 4A 1lE5.11,MOVF07-6.

- G33*MOVF00l1.

1EýHS*MCC2Dý lEHS*,MCC2D , i G33*M0VFO28

.1EHS*kMCC2D iE51-MOVF063-1D, ,lCCPiMOVi44~

  • Alternatea Su~p-ply (continued)

ýRIVER-, BEND - TR 3.8'-15" Rkevi'siori. 121,

-  :-(42viii)

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES PAGE NUMBER I REV PAGE NUMBER I REV PAGE NUMBER I REV 77 TR 3.3-28 (52ii) 5 TR 3.3-74 (74i) 105 ii 100 TR 3.3-29 (52iii) 5 TR 3.3-75 (77i) 90 iii 98 TR 3.3-30 (52iv) 116 TR 3.3-76 (77ii) 5 iv 104 TR 3.3-31 (52v) 5 TR 3.3-77 (77iii) 44 v 77 TR 3 .3-32 (571) 80 TR 3.3-78 (77iv) 44 vi 77 TR 3 .3-33 (57ii) 97 TR 3.3-79 (77v) 44 TR 1-1 77 TR 3 .3-34 (57iii) 40 TR 3 .3-80 (77vi) 5 TR 1-2 77 TR 3.3-35 (57iv) 13 TR 3.3-81 (77vii) 5 TR 1-3 77 TR 3.3-36 (57v) 13 TR 3.3-82 (77viii) 5 TR 1-4 77 TR 3.3-37 (57vi) 87 TR 3.3-83 (77ix) 5 TR 3.0-1 115 TR 3.3-38 (57vii) 16 TR 3.3-84 (77x) 5 TR 3.0-2 115 TR 3.3-39 (57viii) 28 TR 3.3-85 (77xi) 5 TR 3.0-3 92 TR 3.3-40 (60i) 62 TR 3.3-86 (77xii) 77 TR 3.0-4 115 TR 3.3-41 '(60ii) 62 TR 3.3-87 (77xiii) .5 TR 3.1-1 (10i) 5 TR 3.3-42 (61i) 62 TR 3.3-88 86 TR 3.1-2 (17i) 84 TR 3.3-43 (61ii) 98 TR 3.3-89 90 TR 3.1-3 (17ii) 90 TR 3.3-44 (65i) 9 TR 3.3-90 (40i) 103 TR 3.1-4 (25i) 5 TR 3.3-45 (67i-) 72 TR 3.4-1 (4i) 5 TR 3.2-1 (6i) 74 TR 3.3-46 (67ii) 75 TR 3.4-2 (5i) 48 TR 3.3-1 (6i) 5 TR 3.3-47 (67iii) 75 TR 3.4-3 (5ii) 86 TR 3.3-2 (9i) 48 TR 3.3-48 (71i) 85 TR 3.4-4 (11i) 5 TR 3.3-3 (9ii) 72 TR 3.3-49 (71ii) 91 TR 3.4-5 (13i) 5 TR 3.3-4 (9iii) 78 TR 3'.3-50 (71iii) 5 TR 3.4-6 (16i) 49 TR 3.3-5 (15i) 5 TR 3.3-51 (71iv) 38 TR 3.4-7 (16ii) 107 TR 3.3-6 (15i!) 5 TR 3.3-52 (71v) 38 TR 3.4-8 (16iii) 75 TR 3.3-7 (17i) 5 TR 3.3-53 (71vi) 77 TR 3.4-9 (19i) 5 TR 3.3-8 (17ii) 18 TR 3.3-54 (71vii) 114 TR 3.4-10 (32i) 101 TR 3.3-9 (17iii) 18 TR 3.3-55 (71viii) 5 TR 3.4-11 (32ii) 71 TR 3.3-10 (18i) 61 TR 3.3-56 (71ix) 79 TR 3.4-12 (32iii) 5 TR 3.3-11 (18ii) 86 TR 3.3-57 (71x) 5 TR 3.4-13 (33i) 5 TR 3.3-12 (24i) 5 TR 3.3-58 (71xi) 40 TR 3.4-14 (33ii) 5 TR 3.3-13 (24ii) 109 TR 3 .3-59 (71xii) 5 TR 3.4-15 (33iii) 39 TR 3.3-14 (24iii) 109 TR 3.3-60 (71xiii) 40 .TR 3.4-16 (33iv) 5 TR 3.3-15 (24iv) 109 TR 3.3-61 (71xiv) 40 TR 3.4-17 (33v) 5 TR 3.3-16 (28i) 78 TR 3.3-62 (71xv) 106 TR 3.5-1 (5i) 5 TR 3.3-17 (31i) 72 TR 3.3-63 (71xvi) 119 TR 3.5-2 (5ii) 5 TR 3.3-18 (37i) 5 TR 3.3-64 (71xvii) 119 TR 3.5-3 (12i) 77 TR 3:3-19 (43i) 9 TR 3.3-65 (71xviii) 67 TR 3.5-4 (12ii) 77 TR 3.3-20 (43ii) 9 TR 3.3-66 (71xix) 122 TR 3.6-1 (2i) 11 TR 3.3-21 (43iii) 9 TR3.3-67 (71xx) 51 TR 3.6-2 (2ii) 108 TR 3.3-22 (43iv) 9 TR 3.3-68 (71xxi) 51 TR 3.6-3 (8i) 73 TR 3.3-23 (43v) 9 TR 3.3-69 (71xxii) 78 TR 3.6-3a (8ii) 13 TR 3.3-24 (43vi) 77 TR 3.3-70 (71xxiii) 75 TR 3.6-4 (8iii) 73 TR 3.3-25 (43vii) 5 TR 3.3-71 (71xxiv) 90 TR 3.6-5 (20i) 11 TR 3.3-26 (47i) 9 TR 3.3-72 (71xxv) 26 TR 3.6-6 (20ii) 77 TR 3.3-27 (52i) 116 TR 3.3-73 (71xxvi) 5 RIVER BEND TR- a Revision 122

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES PAGE NUMBER I REV PAGE NUMBER I REV PAGE NUMBER I REV TR 3.6-7 (20iii) 108 TR 3.7-28 (l5xxi) 58 TR 3.11-6 18 TR 3.6-8 (20iv) 68 TR 3.7-29 (15xxii) 95 TR 3.11-7 14 TR 3.6-9 (20v) 108 TR 3.7-30 (15xxiii) 5 TR 3.11-8 5 TR 3.6-10 (20vi) 108 TR 3.7-31 (15xxiv) 5 TR 3.11-9 5 TR 3.6-11 (20vii) 69 TR 3.7-32 '(15xxv) I8 TR 311-10 75 TR 3.6-12 (22i) 12 TR 3 .7-33 (15xxvi), 5 TR 3.11-11 5 TR 3.6-13 (28i) 90 TR 3.7-34 (15xxvii) 5 TR 3.11-12 5 TR 3.6- 1 4 (28ii) 35 TR 3.7-35 (15xxviii) 5 TR 3.11-13 5 TR 3.6-15 (30i) 5 TR 3.8-1 (iSi) 120 TR 3.11-14 '5 TR 3.6-16 (35i) . 77 TR 3.8-2 (15ii) 65 TR 3.11-15 5 TR 3.6-17 (36i) 77 TR 3 .8-3 (15iii) 76 TR 3.11-16 5 TR 3.6-18 (40i) 100 TR 3.8-4 (19i) 5 TR 3.11-17 5 TR 3.6-19 (50i) 107 TR .3.8-5 (20i) 76 TR 3.12-1 S TR 3.6-20 (52i) 63 TR 3.8-6 (23i) 114 TR 3.12-2 5 TR 3.6-21 (54i) 98 TR 3.8-7 (27i) 55 TR 3.12-3 77 TR 3.8-8 (42i) 81 TR 3.12-4 77 TR 3.6-23 (59i) 5 TR 3.8-9 (42ii) 81 TR 3.12-5 59 TR 3.6-24 (61i) 18 TR 3.8-10 (42iii) 81 TR 3.12-6 41 TR 3.6-25 (70i) 96 TR 3.8-11 (42iv) o118 TR 3.12-7 41 TR 3.6-26 (70ii) 96 TR 3.8-12 (42v) 5 TR 3.12-8 5 TR 3.6-27 (72i) 5 TR 3.8-13 (42vi) 95 TR 3.12-9 5 TR 3.7-1 (4i) 5 TR 3.8-14 (42vii) 95 TR 3.12-10 41 TR 3.7-2 (4ii) 5 TR 3.8-15 (42viii) 121 TR 3.12-11 41 TR 3,7-3 (4iii) 5 TR 3.8-16 (42ix) 95 TR 3.12-12 77 TR 3.7-4 (4iv) 5 TR 3.8-17 (42x) 95 TR 5-1 87 TR 3,7-5 (8i) 90 TR 3.8-18 (42xi) 113 TR 5-2 117 TR 3,7-6 (11i) 26 TR 3.8-19 (42xii) 5 TR 5-3 5 TR 3,7-7 (14i) 5 TR 3.8-20 (42xiii) 5 TR 5-4 53 TR 3.7-8 (15i) 94 TR 3.8-21 (42xiv) 5 TR 5-5 65 TR 3,7-9 (15ii) 109 TR 3.8-22 (42xv) 30 TR 5-6 94 TR 3.7-10 (15iii) 5 TR 3.8-23 (42xvi) 88 TR 5-7 23 TR 3.7-11 (15iv) 1.22 TR 3.9-1 (7i) 84 TR 5-8 5 TR 3,7-12 (15v) :1.22 TR 3.9-2 (7ii) 72 TR 5-9 .5 TR 3,7-13 (15vi) 5 TR 3.9-3 (13i) 85 TR 5-10 5 TR 3,7-14 (15vii) 15 TR 3.9-4 (13ii) 5 TR 5-11 77 TR 3,7-15 (15viii) 5 TR 3 .9-5 (13iii) 70 TR 5-12 5' TR 3.7-16 (15ix) 5 TR 3 .9-6 (13iv) 5 TR 5-13 94 TR 3.7-17 (15x) 58 TR 3.9-7 (13v) 5 TR 5-14 33 TR 3.7-18 (15xi) 5 TR 3 .9-8 (13vi) 5 TR 5-15 53 TR 3.7-19 (15xii) 79 TR 3 .9-9 (13vii) 54 TR 5-16 53 TR 3.7-20 (15xiii) 5 TR 3.9-10 (13viii) 103 TR 5-17 87 TR 3.7-21 (15xiv) 15 TR 3.9-11 (13ix) 103 TR 5-18 53 TR 3.7-22 (15xv) 58 TR 3.9-12 (13x) 104 TR 5-19 53 TR 3.11-1 83 TR 3.7-23 (15xvi) 5 TR 3.11-2 5 TR 5-20 53 TR 3.7-24 (15xvii) 5 TR' 3.11-3 5 TR 5-21 94 TR 3.7-25 (15xviii) 58 TR 3.11-4 5 TR 5-22 8 TR 3.7-26 (15xix) 5 TR 3.11-5 5 TR 3.7-27 (15xx) 5 RIVER BEND TR-b Revision 122

Traversing In-core Probe System TR 3.3.7.7 TR 3.3.7.7 Traversing In-core Probe System TLCO. 3.3.7.7 The.."traversing incore probe system (TIP) shall be' OPERABLE with:

Az TIP detector information for TIP channels that

..correspond with operable LPRMs.

OR, b , failhue of one Ie rnihie i ec*iL ivalent n mber ofM TP channels)

~D:

c.* data collected to support TIP subs ituui:n per Technical':

ec.ication

.S--o .6-(b).

APPLICABILITY: When the traversing in-core probe is used for recalibration of' the LPRM detectors.

ACTIONS CONDITION ' REQUIRED-ACTION .ýCOMPLETION TIME

.A.' The, traversing' in-core A.l Do not, use,, the ',system for Imdiatel probe[ system ,,' ' the above applicable inoperable." ' ' monitoring -or calibration. . .....

SURVEILLANCEREQUIREMENTS._________

S CSURVEILLANCE FREQUENCY TSR !33.3.7.'7.1---------- ----NOTE----------------------

Only required. to.. be.met during use for LPRM

calibration.

.,Normalizing each of the-abve required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> detector :outputs. prior to use:' for LPRM.

,calibrat ion.

RIVER BEND:' TR 3.3-66 Revision 122 (71xix),

Fire Suppression-Systems TR 3.7.9.1 3.7.9.1. Fire Suppression Systems,

_-- -- ---------------- NOTE_ - ----------- ------ ------

The Operating LiceInse, NPF-47, may require-prior NRC approval ;ýfor changes :to this Technicali Requirement. .

-- -- ------ ----- 2,. 7 L

- ----------- - P -'2 =-:T -

    • [

7--- -- -* ----

  • -! -.- -. 7---. - -- ---

TLCO 3.7..9.1 The.'fire suppression water system shall be OPERABLE with:

a., Three fire suppression pumps, each with a capacity of .1500 'gpm,,

with their discharges.:aligned to the fire 'suppressibon header, and for the diesel-`pumps - -

1. 300"ýgallons of: fuel..in the :fuel day tank, and.,
2. :Two starting.24 Volt battery banks and :two chargers OPERABLE for each diesel engine,
b. Two separate fire, water tanks, each w ith .a, 'aminimum contained volume of 253, 000 gallons, and
c. An.OPERABLE: flow path capable of' takinggisUctior from both:watdr storage tanks ahd transferring the' water: through distribution.

piping with OPERABLE.."ect ionalizing contol. or. isolation valves to- the yard hydrantE curb valves, the-.last Valve.'ahead of the water flow alarm device on each sprinkler or, hose standpipe, and the last valve ahead .of the :deluge valve .on each deluge or,,

spray.:system, required .. 'tobe 0PERABLE. per, Requirements 3 .).7.9.5, 3 .q9 4 , .*an d :!3 .7 .*9.2.... .. . .*,'i,.:,::-*,. . .. . .. .

APPLICABILITY: At all timesi

-- - --.-- - ---I - -- --N O T E - - -- - -- - - - -- _7_- - ----- - - -- ----- - - -- - - -- -

The provisions of TLCO .3.0O.:4. arenot 'applicable tC I O Ar

.CONDITION. ' REQUIRED ACTION ,' COMPLETION TIME' A. One.apump inoperable A.1 Restore' the inoperable' 7 days" pOpEto, OPERABLE status""

A.;:21. Provide an alternate .7.days

________,:"_backup pump OR  :,: " '  :': ., : * .- " < '

B.:. One water supply B.- Restore the. inoperable 7 days (

inoperable water, supply% t'o OPERABLE status OR

B. 2 Provide an alternate 7.days'

_____________________ I backup_.supply _________

- (continued):

RIVER..BEND TR 3.7-il1 Revisioff 122 (15iv)

Fire Suppression Systems

... , . .. i *TR 3 .7 .9 .1 ACTIONS (continued) ._._,. . * .- .. . . " .*

CONDITION REQUIRED ACTION COMPLETION::TIME C. Fire suppressi on C.1, Establish .a backup fire 24 -hours S waer system Suppression water -  :

otherwise inoperable system D,. RequiredAction and------------ _NOTE-"

associated TLC0 3.,0.3 .shall not.be.

Completion. Time of applied to this Condition,,

Condition C not:. :met .- ___ -_.--- 7 - ....

D.l: Be in MODE 3 .12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D.2 Be in MODE 4 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />s-. .....

/

r)

RIVER-BEND TR. 3.7-12 Revision 122' (15v) -

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REV PAGE REV PAGE REV PAGE REV NUMBER NUMBER NUMBER NUMBER I 3.6-90 6-5 3.6-130 2-4 3.7-28 0 3.8-36 0 3'. 6-91 115 3.6-131 2-4 3.7-29 115 3 .8-37 115 3 .6-92 6-5 3.6-132 3-4 3.7-30 0 3.8-38 110 3 .6-93 115 3.6-133 3-4 3.7-31 115 3 .8-39 102 3.6-94 6-5 3.6-134 2-8 3.8-1 0 3 .8-40 102 3.6-95 6-5 3.6-135 2-8 3.8-2 5-3 3 .8-41 3-2 3 .6-96 0 3.6-136 6-2 3.8-3 0 3 .8-42 0 3 .6-97 1 3.6-137 2-8 3.8-4 133 3 .8-43 0 3.6-98 0 3.6-138 2-8 3.8-5 105 3 .8-44 0 3.6-99 0 3.6-139 2-8 3.8-6 0 3 .8-45 0 3.6-100 0 3.6-140 2-8 3 .8-7 0 3 .8-46 0 3.6-101 121 3.6-141 2-8 3 .8-8 105 3 .8-47 0 3.6-102 121 3 .6-142 2-8 3 .8-8a 105 3 .8-48 3-2 3.6-103 121 3.7-1 110 3 .8-9 105 3 .8-49 134 3.6-104 6-5 3.7-2 \110 3 8-10 0 3 .8-50 0 3.6-105 110 3.7-3 110 3.8-11 0 3.8-51 125 3.6-106 0 3.7-4 1 3.8-12 0 3. 8-51a 125 3.6-107 6-5 3.7-5 1 3.8-13 0 3,.8-52 125 3.6-108 6-5 3.7-6 0 3.8-14 127 3. 8-52a 125 3.6-109 6-5 3.7-7 3-1 3.8-15 102 3. 8-52b 125 3.6-110 6-5 3.7-8 1 3 .8-16 102 3 .8-53 125 3 .6-111 6-5 3.7-9 '0 3 .8-17 102 3.8-54 125 3 .6-112 0 3.7-10 132 3 .8-18 127 3.8-55 0 3 .6-113 110 3.7-11 132 3.8-19 117 3.8-56 120 3 .6-114 6-5 3.7-12 132 3.8-20 117 3 .8-57 120 3.6-115 0 3 .7-12a 132 3.8-21 102 3.8-58 120 3.6-116 0 3.7-13 132 3 .8-22 113 3.8-59 110 3.6-117 0 3.7-14 132 3 . 8*-23 113 3.8-60 110 3.6-118 0 3.7-15 132 3 .8-24 113 3 .8-61 115 3.6-119 110 3.7-16 132 3.8-25 102 3.8-62 0 3.6-120 135 3.7-17 4-4 3.8-26 102 3.8-63 0 3.6-121 119 3.7-18 110 3.8-27 113 3.8-64 0 3.6-122 2-4 3.7-19 6-13 3.8-28 113 3 .8-65 0 3.6-123 2-4 3.7-20 115 3.8-29 113 3.8-66 1 3.6-124 2-4 3.7-21 6-13 3.8-30 113 3.8-67 4-5 3.6-125 2-4 3.7-22 0 3 .8-31 102 3 .8-68 4-5 3.6-126 2-4 3..7-23 0 3 .8-32 3-1 3.8-69 1 3.6-127 2-4 3.7-24 1 3 .8-33 3-1 3.6-128 110 3.7-25 6-14 3.8-34 110 3.6-129 3-4 3.7-26 6-7 3 .8-35 0 3.7-27 0-f RIVER BEND TSB-d Revision No. 135

Drywell B 316.5.1 BASES SURVEILLANCE SR 3.6.5.1.3 REQUIREMENTS (continued) The analyses in Reference 1 are based on a maximum drywell bypass leakage.' This Surveillance ensures that the actual drywell bypass leakage is less than or equal to the acceptable A/Ik design value of 0.81 ft. As left drywell bypass leakage, prior to the first startup after performing a required drywell bypass leakage test, is required to be

_<10% of the drywell bypass leakage limit. At all other times between required drywell leakage rate tests, the acceptance criteria is based on design A/.k At the design A/Nk the containment temperature and pressurization response are bounded by the assumptions of the safety analysis. Due to NRC Generic Letter 96-06 concerns, integrity of the reactor recirculation flow control valve hydraulic power unit (HPU) penetrations cannot be assumed. For this reason, 0.0164 ft2 is added to the drywell bypass leakage surveillance result (Ref. 3). This surveillance is performed at least once every 10 years on a performance based frequency. This frequency is modified on a one time basis until June 23, 2009. The frequency is consistent with the difficulty of performing the test, risk of high radiation exposure, and the remote possibility that sufficient component failures will occur such that the drywell bypass leakage limit will be exceeded. If during the performance of this required Surveillance the drywell bypass leakage rate is greater than the drywell bypass leakage limit, the Surveillance Frequency is increased to every 48 months. If during the performance of the subsequent consecutive Surveillance the drywell bypass leakage rate is less than or equal to the drywell bypass leakage limit, the 10 year Frequency may be resumed. If during the performance of two consecutive Surveillances the drywell bypass leakage is greater than the drywell bypass leakage limit, the Surveillance Frequency is increased to at least once every 24 months.

The 24 month Frequency is maintained until during the performance of two consecutive Surveillances the drywell bypass leakage rate is less than or equal to the drywell bypass leakage limit, at which time the 10 year Frequency may be resumed. For two Surveillances to be considered consecutive, the Surveillances must be performed at least 12 months apart. Since the frequency is performance based, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.6.5.1.4 The exposed accessible drywell interior and exterior surfaces are inspected to ensure there are no apparent physical defects that would prevent the drywell from (continued)

RIVER BEND B 16-120 Revision No. 135

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REV PAGE REV PAGE REV PAGE REV NUMBER NUMBER NUMBER NUMBER B 2.0-1 0 B 3.1-24 107 B 3.3-1 0 B 3.3-39e 101, B 2.0-2 6-15 B 3.1-25 107 B 3.3-2 6-7 B 3.3-39f 4-8

,B 2.0-3 6-15 B 3.1-26 0 B 3.3-3 0 B 3.3-39g 4-8 B 2.0-4 6-15 B 3.1-27 0 B 3.3-4 0 B 3.3-39h 4-8

.B 2.0-5 115 B 3.1-28 0 B 3.3-5 0 B 3.3-40 0 B 2.0-6 115 B 3.1-29 6-14 B 3.3-6 0 B 3.3-41 6-13 B 2.0-7 0 B 3.1-30 6-14 B 3.3-7 6-4 B 3.3-42 6-6 B 2.0-8 115 B 3.1-31 6-14 B 3.3-8 4-8 B 3.3-43 6-13 B 2.0-9 115 B 3.1-32 0 B 3.3-8a 4-8 B 3.3-44 0 B 3.0-1 0 B 3.1-33 6-13 B 3.3-8b 4-8 B 3.3-45 0 B 3.0-2 0 B 3.1-34 6-13 B 3.3-9 4-8 B 3.3-46 0 B 3:0-3 0 B 3.1-35 6-13 B 3.3-10 4-8 B 3.3-47 0 B 3.0-4 0 B 3.1-36 0 B 3.3-11 1 B 3.3-48 6-13 B 3.0-5 133 B 3.1-37 0 B 3.3-12 0 B 3.3-49. 1 B 3.0-5a 133 B 3.1-38 0 B 3.3-13 6-4 B 3.3-50 0 B 3.0-5b 133 B 3.1-39 0 B 3.3-14 0 B 3.3-51 1 B 3.0-6 133 B 3.1-40 0 B 3.3-15 0 B 3.3-52 116 B 3.0-7 0 B 3.1-41 5-6 B 3.3-16 0 B 3.3-53 6-2 B 3.0-8 0 B 3.1-42 1 B 3.3-17, 2-7 B 3.3-54 122 B 3.0-9 0 B 3.1-43 6-14 B 3.3-18 1 B 3.3-55 133 B 3.0-10 0 B 3.1-44 1 B 3.3-19 1 B 3.3-56 133 B 3.0-11 0 B 3.1-45 115 B 3.3-20 1 B 3.3-57 0 B 3.0-12 108 B 3.1-46 118 B 3.3-21 1 B 3.3-58 0 B 3.0-13 108 B 3.1-47 118 B 3.3-22 1 B 3.3-59 1 B 3T.0-13a 108 B 3.1-48 0 B 3.3-23 1 B 3.3-60 0 B 3.0-14 133 B 3*.1-49 115 B 3.3-24 1 B 3.3 0 B 3.0-15 133 B 3.2-1 0 B 3.3-25 6-4 B 3.3-62 133 B 3.1-1 0 B 3.2-2 6-4 B 3.3-25a 4-8 B 3.3-63 0 B 3.1-2 0 B 3.2-3 6-4 B 3.3-26 4-8 B 3.3-64 0 B 3.1-3 0 B 3.2-4 3-7 B 3.3-27 6-15 B 3.3-65 0 B 3.1-4 0 B 3.2-5 0 B 3.3-28 1 B 3.3-66 124 B 3.1-5 0 B 3.2-6 6-15 B 3.3-29 5-1 B 3.3-67 124 B 3.1-6 0 B 3.2-7 6-4 B 3.3-30 4-8 B 3.3-68 1 B 3.1-7 3-10 B 3.2-8 6-15 B 3.3-31 4-8 B 3.3-69 1 B 3.1-8 3-10 B 3.2-9 '0 B 3.3-31a 4-8 B 3.3-70 124 B 3.1-9 3-10 B 3.2-10 6-4 B 3-.3-32 0 B 3.3-71 124 B 3.1-10 3-10 B 3.2-11 6-4 B 3.3-33 0 B 3.3-72 1 B 3.1-11 3-10 B 3.2-12 4-8 B 3.3-34 0 B 3.3-73 11 B 3 1-'12 0 B 3.2-13 4-8 B 3.3-35 0 B 3.3-74 2-1 B 3.1-13 0 B 3.2-14 4-8 B 3.3-36 136 B 3.3-75 2-1 B 3.1-14 0 B 3.2-15 4-8 B 3.3-37 0 B 3.3-76 0 B 3.1-15 136 B 3.2-16 4-8 B 3.3-38 0 B 3.3-77 106 B 3.1-16 0 B 3.2-17 4-8 B 3.3-39 0 B 3.3-78 0 B 3.1-17 6-13 B 3.2-18 4-8 B 3.3-39a 4-8 B 3.3-79 0 B 3.1-18 136 B 3.3-39b 4-8 B 3.1-19 1 B 3.3-39c 4-8 B 3.1-20 0 B 3.3-39d 4-8 B 3.1-21 0 B 3.1-22 5-2 B 3.1-23 0 RIVER BEND TSB-a Revision No. 136

Control Rod OPERABILITY B 3.1.3 BASES ACTIONS A.1, A.2, and A.3 (continued) control rod can be isolated from scram by isolating the hydraulic control unit from scram and normal drive pressure, yet still maintain cooling water to the CRD.

Monitoring of the insertion capability for each withdrawn control rod must also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. SR 3.1.3.3 performs periodic tests of the control rod insertion capability of withdrawn control rods. Testing each withdrawn control, rod ensures that a generic problem does not exist. The allowed Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provides a reasonable time to test the control rods, considering the potential for a need to reduce power to perform the tests. Required Action A.2 has a modified time zero Completion Time. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time for this Required Action starts when the withdrawn control rod is discovered to be stuck and THERMAL POWER is greater than the actual low power setpoint (LPSP) of the rod pattern controller (RPC), since the notch insertions may not be compatible with the requirements of rod pattern control (LCO 3.1.6) and the RPC (LCO 3.3.2.1, "Control Rod Block Instrumentation").

To allow continued operation with a withdrawn control rod stuck, an evaluation of adequate SDM is also required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Should a DBA or transient require a shutdown, to preserve the single failure criterion an additional control rod would have to be assumed to have failed to insert when required. Therefore, the original SDM demonstration may not be valid. The SDM must therefore be evaluated (by measurement or analysis) with the stuck control rod at its stuck position and the highest worth OPERABLE control rod assumed to be fully withdrawn.

The allowed Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to verify SDM is adequate, considering that with a single control rod stuck in a withdrawn position, the remaining OPERABLE control rods are capable of providing the required scram and shutdown reactivity. Failure to reach MODE 4 is only likely if an additional control rod adjacent to the stuck control rod also fails to insert during a required scram. Even with the postulated additional single failure of an adjacent control rod to insert, sufficient reactivity control remains to reach and maintain MODE 3 conditions (Ref. 7).

(continued)

RIVER BEND B 3.1-15 Revision No. 136

Control Rod OPERABILITY B 3.1.3 BASES (continued)

SURVEILLANCE SR 3.1.3.1 REQUIREMENTS The position of each control rod must be determined, to ensure adequate information on control rod position is available to the operator for determining control rod OPERABILITY and controlling rod patterns.

Control rod position may be determined by the use of OPERABLE position indicators, by moving control rods to a position with an OPERABLE indicator, or by the use of other appropriate methods. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is based on operating experience related to expected changes in control rod position and the availability of control rod position indications in the control room.

SR 3.1.3.2 Deleted SR 3.1.3.3 Control rod insertion capability is demonstrated by inserting each partially or fully withdrawn control rod at least one notch and observing that the control rod moves. The control rod may then be returned to its original position. This ensures the control rod is not stuck and is free to insert on a scram signal. This Surveillance is modified by a Note identifying that the Surveillances are not required to be performed when'THERMAL POWER is less than or equal to the actual LPSP of the RPC since the notch insertions may not be compatible with the requirements of the BPWS (LCO 3.1.6) and the RPC (LCO 3.3.2.1). This Note also provides a time allowance such that the Surveillance is not required to be performed until the next scheduled control rod testing . Partially withdrawn control rods are tested at a 31 day Frequency, based on the potential power reduction required to allow the control rod movement, and considering the large testing sample of SR 3.1.3.2. Furthermore, the 31 day Frequency takes into account operating experience related to changes in CRD performance. At any time, if a control rod is immovable, a (continued)

RIVER BEND B 3.1-18 Revision No. 136

SRM Instrumentation B 3.3.1.2 BASES ACTIONS D.1 and D.2 (continued)

Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is sufficient to accomplish the Required Action, and takes into account the low probability of an event requiring the SRM occurring during this time.

E.1 and E.2 With one or more required SRMs inoperable in MODE 5, the capability to detect local reactivity changes in the core during refueling is degraded.

CORE ALTERATIONS must be immediately suspended, and action must be immediately initiated to fully insert all insertable control rods in core cells containing one or more fuel assemblies. Suspending CORE ALTERATIONS prevents the two most probable causes of reactivity changes, fuel loading and control rod withdrawal, from occurring. Inserting all insertable control rods ensures that the reactor will be at its minimum reactivity, given that fuel is present in the core. Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe, conservative position.

Action (once required to be initiated) to insert control rods must continue until all insertable rods in core cells containing one or more fuel assemblies are inserted.

SURVEILLANCE The SRs for each SRM Applicable MODE or other specified condition are REQUIREMENTS found in the SRs column of Table 3.3.1.2-1.

SR 3.3.1.2.1 and SR 3.3.1.2.3 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to the same parameter indicated on other similar channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

(continued)

RIVER BEND B 3.3-36 Revision No. 136

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REV PAGE REV PAGE REV PAGE REV NUMBER NUMBER NUMBER NUMBER 3.6-90 6-5 3.6-130 2-4 3.7-28 0 3.8-36 0 3.6-91 115 3.6-131 2-4 3.7-29 115 3.8-37 115 3.6-92 6-5 3.6-132 3-4 3.7-30 0 3.8-38 110 3.6-93 115 3.6-133 3-4 3.7-31 115 3.8-39. 102 3 .6-94 6-5 3 .6-134 2-8 3 .8-1 0 3.8-40 102 3.6-95 6-5 3.6-135 2-8 3 .8-2 5-3 3.8-41 3-2 3.6-96 0 3.6-136 6-2 3 .8-3 0 3.8-42 0 3.6-97 1 3.6-137 2-8 3 .8-4 133 3.8-43 0 3.6-98 0 3.6-138. 2-8 3.8-5 105 3.8-44 0 3.6-99 0 3.67139 2-8 3.8-6 0 3.8-45 0 3.6-100 0 3.6-140 .2-8 3.8-7 0 3.8-46 0 3.6-101 121 3..6-141 2-8 3.8-8 105 3.8-47 0 3.6-102 121 3 .6-142 2-8 3. 8-8a 105 3.8-48 3-2 3.6-103 121 3 .7-1 110 3.8-9 105 3.8-49 134 3.6-104 6-5 3 .7-2 110 3.8-10 0 3.8-50 0 3 .6-105 110 3 .7-3 110 3.8-11 0 3.8-51 125 3.6-106 0 3.7-4 1 3.8-12 0 3.8-51a 125 3.6-107 6-5 3.7-5 1 3.8-13 0 3.8-52 125 3.6-108 6-5 3.7-6 0' 3.8-14 127 3.8-52a 125 3.6-109 6-5 3.7-7 3-1 3.8-15 102 3 .8-52b 125 3 .6-110 6-5 3..7-8 1 3.8-16 102 3.8-53 125 3 .6-111 6-5 3.7-9 0 3.8-17 102 3.8-54 125 3 .6-112 0 3 .7-10 132 3.8-18 127 3.8-55 0 3 .6-113 110 3.7-11 132 3.8-19 117 3.8-56 120 3.6-114 6-5 3.7-12 132 3.8-20 117 3.8-57 120 3.6-115 0 3. 7-12a 132 3.8-21 102 3.8-58 120

j. 6-116 0 3.7-13 132 3.8-22 113 3.8-59 110 3 .6-117 0 3.7-14 132 3.8-23 113 3
  • 8-60 110 3.6-118 0 3 .7-15 132 3.8-24 113 3 .8-61 115 3.6-119 110 3 .7-16 132 3.8-25 102 3.8-62 0 3.6-120 135 3.7-17 4-4 3.8-26 102 3.8-63 0 3 .6-121 119 3.7-18 110 3.8-27 113 3.8-64 0 3.6-122 2-4 3.7-19 6-13 3.8-28 113 3.8-65 0 3.6-123 2-4 3.7-20 115 3.8-29 113 .3.8-66 1 3.6-124 2-4 3.7-21 6-13 3.8-30 113 3.8-67 4-5 3.6-125 2-4 3.7-22 0 3.8-31 102 3.8-68 4-5
3. 6-126 2-4 3.7-23 0 3.8-32 3-1 3.8-69 1 3.6-127 2-4 3.7-24 1 3.8-33 3-1 3.6-128 110 3.7-25 137 3.8-34 110 3.6-129 3-4 3.7-26 137 3.8-35 0 3.7-27 0 RIVER BEND TSB-d Revision No. 137

Main Turbine Bypass System B 3.7.5 B 3.7 PLANT SYSTEMS B 3.7.5 Main Turbine Bypass System BASES BACKGROUND The Main Turbine Bypass System is designed to control steam pressure when reactor steam generation exceeds turbine requirements during unit startup, sudden load reduction, and cooldown. It allows excess steam flow from the reactor to the condenser without going through the turbine.

The bypass capacity of the system is 10% of the Nuclear Steam Supply System rated steam flow. Sudden load reductions within the capacity of the steam bypass can be accommodated without reactor scram. The Main Turbine Bypass System consists of a two valve chest connected to the main steam lines between the main steam isolation valves and the turbine stop valves. Each of these valves is sequentially operated by hydraulic cylinders. The bypass valves are controlled by the pressure regulation function of the Turbine Pressure Regulator and Control System, as discussed in the USAR, Section 7.7.1.4 (Ref. 1). The bypass valves are normally closed, and the pressure regulator controls the turbine control valves, directing all steam flow to the turbine. If the speed governor or the load limiter restricts steam flow to the turbine, the pressure regulator controls the system pressure by opening the bypass valves. When the bypass valves open, the steam -flows from the bypass chest, through connecting piping, to the pressure breakdown assemblies, where a series of orifices are used to further reduce the steam pressure before the steam enters the condenser.

APPLICABLE The Main Turbine Bypass System is assumed to function during the SAFETY ANALYSES design basis feedwater controller failure, maximum demand event, described in the USAR, Section 15.1.2 (Ref. 2). Opening the bypass valves during the pressurization event mitigates the increase in reactor vessel pressure, which affects the MCPR during the event. An inoperable Main Turbine Bypass System may result in MCPR, APLHGR and LHGR penalties.

The Main Turbine Bypass System satisfies Criterion 3 of the NRC Policy Statement.

(continued)

RIVER BEND B 3.7-25 Revision No. 137

Main Turbine Bypass System B 3.7.5 BASES (continued)

LCO The Main Turbine Bypass System is required to be OPERABLE to limit peak pressure in the main steam lines and maintain reactor pressure within acceptable limits during events that cause rapid pressurization, such that the Safety Limit MCPR is not exceeded.

An OPERABLE Main Turbine Bypass System requires the bypass valves to open in response to increasing main steam line pressure. This response is within the assumptions of the applicable analysis (Ref. 2).

With the Main Turbine Bypass System inoperable, modifications to the APLHGR limits (LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)"), MCPR limits (LCO 3.2.2 "MINIMUM CRITICAL POWER RATIO (MCPR) (including power and flow dependent limits)") and LHGR limits (LCO 3.2.3 "LINEAR HEAT GENERATION RATE (LHGR) (including power and flow dependent limits)") may be applied as applicable to allow continued operation.

APPLICABILITY The Main Turbine Bypass System is required to be OPERABLE or the inoperable Main Turbine Bypass System APLHGR, MCPR, and LHGR limits are required to be implemented at > 23.8% RTP to ensure that the fuel cladding integrity Safety Limit and the cladding 1 % plastic strain limit are not violated during the feedwater controller failure, maximum demand event. As discussed in the Bases for LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," and LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," sufficient margin to these limits exists < 23.8% RTP. Therefore, these requirements are only necessary when operating at or above this power level.

ACTIONS A.1 If the Main Turbine Bypass System is inoperable (one or more bypass valves inoperable), the assumptions of the design basis transient analysis may not be met. Under such circumstances, prompt action should be taken to restore the Main Turbine Bypass System to OPERABLE status, or implement the APLHGR, MCPR and LGHR limits for an inoperable Main Turbine Bypass System. The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Completion Time is reasonable, based on the time to complete the Required Action and the low probability of an event occurring during this period requiring the Main Turbine Bypass System.

B._1 If the Main Turbine Bypass System cannot be restored to OPERABLE status and the APLHGR, MCPR, and LHGR limits for an inoperable Main Turbine Bypass System cannot be implemented within the associated Completion Time, THERMAL POWER must be reduced to < 23.8% RTP.

As discussed in the Applicability section, operation at < 23.8% RTP results in (continued)

RIVER BEND B 3.7-26 Revision No. 137

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~1-3 .4-18 0 3.4-58 0 3.6-10 2-3 3.6-50 6-13 3 .4-19 109 3.4-59 0 3 .6-11 2-3 3 .6-51 110 3.4-20 109 3.4-60 0 3 .6-12 128. 3 .6-52 .110 3.4-21 109 3.4-61 6-13 3 .6-13 6-10 3.6-53 0 3 .4-21a 109 3.4-62 6-14 3 .6-14 110 3.6-54 0 3 .4-22 0 3.4-63 6-14 3.6-15 3-4 3.6-55 0 3.4-23 0 3.5-1 0 3.6-16 0 3.6-56 0 3.4-24 0 3.5-2 0 3.6-17 128 3.6-57 0 3.4-25 0 3.5-3 6-14 3.6-18 3-4 3.6-58 0 3.4-26 0 3.5-4 3-7 3.6-19 3-4 3.6-59 3-4 3.4-27 0 3.5-5 0 3.6-20 128 3.6-60 0 3.4-28 0 3.5-6 133 3.6-21 129 3 .6-61 0 3.4-29 0 3.5-7 0 3.6-22 110 3.6-62 0 3 .4-'30 0 3.5-8 0 3.6-23 0 3.6-63 0 3.4-31 0 3.5-9 0 3.6-24 6-11 3. 6-64 0 3 .4-32 0 3.5-10 134 3 .6-24a 6-11 3.6-65 0 3.4-33 3-4 3.5-11 113 3.6-25 129 3.6-66 122

.3.4-34 138 3.5-12 109 3.6-26 3-9 3.6-67 122

3. 4-35 133 3.5-13 109 3 .6-27 121 3.6-68 122 3.4-36 133 3 .5-13a 109 3 .6-28 110 3.6-69 122 3.4-37 0 3.5-14 109 3 .6-29 2-1 3.6-70 122 3.4-38 0 3.5-15 0 3.6-30 0 3.6-71 122 3.4-39 110 3.5-16 0 3.6-31 0 3.6-72 0 3.4-40 110 3.5-17 0 3.6-32 0 3 .6-73 0 3.4-41 133 3.5-18 0 3.6-33 0 3 .6-74 0 3 .4-42 110 3.5-19 0 3 .6-34 0 3.6-75 133 3 .4-43 0 3.5-20 6-14 3.6-35 109 3.6-76 6-12 3 .4-44 0 3.5-21 133 3.6-36 0 3.6-77 3-3 3.4-45 133 3.5-22 133 3 .6-37 109 3.6-78 122 3.4-46 0 3.5-23 0 3.6-38 109 3 .6-79 0 3.4-47 0 3.5-24 0 3.6-39 0 3.6-80 133 3 .4-48 3.5-25 3 .6-40 0 0 0 3.6-81 2-8 3.4-49 0 3 .6-1 3 .6-41 0 3.6-82 2-8 3.4-50 0 3 .6-2 128 3 .6-42 0 3.6-83 121 3.4-51 0 3 .6-3 2-1 3 .6-43 3-9 3.6-84 6-5 3.4-52 0 3 .6-4 128 3 .6-44 3-9 3.6-85 115 3.4-53 6-4 3.6-5 0 3 .6-45 3-9 3.6-86 6-5 3.4-54 6-13 3.6-6 110 3 .6-46 3-9 3.6-87 110 3.4-55 6-4 3 .6-7 110 3 .6-47 1 3.6-88 6-5 3.4-56 0 3.6-8 2-3 3 .6-48 0 3.6-89 6-5 3.4-57 0 3 .6-9 2-3 3 .6-49 0 N

RIVER BEND TSB-c Revision No. 138

RCS Leakage Detection Instrumentation B 3.4.7 BASES BACKGROUND Condensate from the drywell coolers is routed to the drywell and pedestal (continued) floor drain sump and is monitored by a flow transmitter that provides indication and alarms in the control room. This drywell air cooler condensate flow rate'monitoring system serves as an added indicator, but not quantifier, of RCS unidentified LEAKAGE.

APPLICABLE A threat of significant compromise to the RCPB exists if the barrier SAFETY ANALYSES contains a crack that is large enough to propagate rapidly. LEAKAGE rate limits are set low enough to detect the LEAKAGE emitted from a single crack in the RCPB (Refs. 4 and 5). Each of the leakage detection systems inside the drywell is designed with the capability of detecting LEAKAGE less than the established LEAKAGE rate limits.

Identification of the LEAKAGE allows the operators to evaluate the significance of the indicated LEAKAGE and, if necessary, shut down the reactor for further investigation and corrective action. The allowed LEAKAGE rates are well below the rates predicted for critical crack sizes (Ref. 6).

Therefore, these actions provide adequate response before a significant break in the RCPB can occur.

RCS leakage detection instrumentation satisfies Criterion 1 of the NRC Policy Statement.

LCO The drywell and pedestal floor drain sumps monitoring systems are required to quantify the unidentified LEAKAGE from the RCS. Thus, for the systems to be considered OPERABLE, the sump level monitoring portion of the systems must be OPERABLE. The other monitoring systems provide qualitative indication to the operators so closer examination of other detection systems will be made to determine the extent of any corrective action that may be required. With the leakage detection systems inoperable, monitoring for LEAKAGE in the RCPB is degraded.

APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are rdquired to be OPERABLE to support LCO 3.4.5. This Applicability is consistent.with that for LCO 3.4.5.

(continued)

RIVER BEND B 3.4-34 Revision No. 138

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2.0-1 0 3.1-24 139 3.3-1 0 3.3-39e 101 2.0-2 6-15 3.1-25 107 3.3-2 6-7 3. 3-39f 4-8 2.0-3 6-15 3.1-26 139 3.3-3 0 3 .3-39g 4-8 2.0-4 6-15 3 .1-27 0 3.3-4 0 3.3-39h 4-8 2.0-5 115 3.1-28 0 3.3-5 0 3.3-40 0 2.0-6 115 3.1-29 6-14 3.3-6 0 3.3-41 6-13 2.0-7 0 3.1-30 6-14 3.3-7 6-4 3.3-42 6-6 2.0-8 115 3.1-31 6-14 3.3-8 4-8 3.3-43 6-13 2.0-9 115 3 .1-32 0 3 .3-8a 4-8 3.3-44 0 3.0-1 0 3.1-33 6-13 3.3-8b 4-8 3.3-45 0 3.0-2 0 3.1-34 6-13 3.3-9 4-8 3.3-46 0 3.0-3 0 3 .1-35 6-13 3.3-10 4-8 3.3-47 0 3.0-4 0 3.1-36 0 3.3-11 1 3.3-48 6-13 3.0-5 133 3 .1-37 0 3.3-12 0 3.3-49 1

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TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REV PAGE, REV PAGE REV PAGE REV NUMBER NUMBER NUMBER NUMBER B 3.3-80 0 B 3.3-120 113 B 3.3-160 104 B 3.3-200 0 B 3.3-81 0 B 3.3-121 0 B 3.3-161 0 B 3.3-201 115 B 3.3-82 0 B 3.3-122 0 B 3.3-162 0 B 3.3-202 0 B 3.3-83 0 B 3.3-123 4-1 B 3.3-163 0. B 3.3-203 0 B 3.3-84 0 B 3.3-124 0 B 3.3-164 0 B 3.3-204 3-4 B 3.3-85 131 B 3.3-125 2-6 B 3.3-165 0 B 3.3-205 0 B 3.3-86 131 B 3.3-126 0 B 3.3-166. 0 B 3.3-206 0 B 3.3-87 0 B 3.3-127 0 B-3.3-167 0 B 3.3-207 0 B 3.3-88 0 B 3.3-128 0 B 3.3-168 0 B 3.3-208 0 B 3.3-89 0 B 3.3-129 0 B 3.3-169 0 B 3.3-209 1 B 3.3-90 0 B 3.3-130 0 B 3.3-170 110 B 3.3-210 1 B 3.3-91 0 B 3.3-131 130 B 3.3-171 6-5 B 3.3-211 1.

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TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REV PAGE REV PAGE REV PAGE I REV NUMBER NUMBER NUMBER NUMBER I. + 3. 6-50 3.4-18 0 3 . 4-58 0 3 .6-10 2-3 3.6-50 6-13 3.4-19 109 3 .4-59 0 3.6-11 2-3 3.6-51 110 3.4-20 109 3.4-60 0 3 .6-12 128 3.6-52 110 3.4-21 109 3.4-61 6-13 3 .6-13 6-10 3 .6-53 0 3.4-21a 109 3.4-62 6-14 3.6-14 110 3.6-54 ý0 3.4-22 0 3.4-63 6-14 3.6-15 3-4 3.6-55 0 3.4-23 0 3.5-1 0 3.6-16 0 3.6-56 0 3.4-24 0 3 .5-2 0 3.6-17 128 3.6-57 0 3.4-25 0 3 .5-3 6-14 3.6-18 3-4 3.6-58 0 3.4-26 0 3.5-4 3-7 3 .6-19 3-4 3.6-59 3-4 3.4-27 0 3 .5-5 0 3.6-20 128 3.6-60 0 3.4-28 0 3.5-6 133 3.6-21 129 3.6-61 0 3.4-29 0 3 .5-7 0 3.6-22 110 3.6-62 0 3.4-30 0 3.5-8 Ox 3.6-23 0 3.6-63 0 3.4-31 0 3 .5-9 0 3 .6-24 6-11 3 .6-64 139 3.4-32 0 3 .5-10 134 3 .6-24a 6-11 3.6-65 0 3.4-33 3-4 3 .5-11 113 3.6-25 129 3.6-66 122 3.4-34 138 3.5-12 109 3.6-26 3-9 3.6-67 122 3.4-35 133 3.5-13 109 3 .6-27 121 3.6-68 122 3.4-36 133 3 .5-13a 109 3.6-28 110 3.6-69 122 3.4-37 0 3.5-14 109 3.6-29 2-1 3.6-70 122 3.4-38 01 3 .5-15 0 3.6-30 0 3. 6-71 122 3.4-39 110 3.5-16 0 3.6-31 0 3 .6-72 0 3.4-40 110 3 .5-17 0 3 .6-32 0 3 .6-73 0 3.4-41 133 3.5-18 0 3 .6-33 0 3.6-74 0 3.4-42 110 3.5-19 0 3 .6-34 0 3.6-75 133 3.4-43 0 3.5-20 6-14 3.6-35 109 3 .6-76 6-12 3.4-44 0 3.5-21 133 3.6-36 0 3 .6-77 3-3 3.4-45 133 3 .5-22 133 3.6-37 109 3.6-78 122 3.4-46 0 3 .5-23 0 3.6-38 109 3.6-79 0 3.4-47 0 3.5-24 0 3.6-39 0 3.6-80 133 3.4-48 0 3.5-25 0 3 .6-40 0 3.6-81 2-8 3.4-49 0 3.6-1 0 3 .6-41 0 3.6-82 2-8 3.4-50 0 3 .6-2 128 3 .6-42 0 3.6-83 121 3.4-51 0 3 .6-3 2-1 3 .6-43 3-9 3.6-84 6-5 3.4-52 0 3 .6-4 128 3.6-44 3-9 3.6-85 115 3.4-53 6-4 3 .6-5 0 3.6-45 3-9 3..6-86 6-5 3.4-54 6-13 3.6-6 110 3.6-46 3-9 3.6-87 110 3.4-55 6-4 3 .6-7 110 3 .6-47 1 3.6-88 6-5 3.4-56 0 3.6-8 2-3 3 .6-48 0 3.6-89 6-5 3.4-57 0 3.6-9 2-3 3 .6-49 0 RIVER BEND TSB-C Revision No. 139

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+ 4 3.6-90 6-5 3.6-130 2-4 3.7-28 0 3-8-36 0 3.6-91 115 3.6-131 2-4 3.7-29 115 3 .8-37 115 3.6-92 6-5 3 .6-132 3-4 3.7-30 0 3.8-38 110 3.6-93 115 3.6-133 3-4 3.7-31 115 3.8-39 102 3.6-94 6-5 3.6-134 2-8 3.8-1 0 3 .8-40 102 3 .6-95 6-5 3.6-135 2-8 3.8-2 5-3 3 .8-41 3-2 3 .6-96 0 3.6-136 6-2 3.8-3. 0 3 .8-42 0 3 .6-97 1 3.6-137 2-8 3.8-4 133 3.8-43 0 3.6-98 0 3.6-138 2-8 3.8-5 105 3 .8-44 0 3.6-99 0 3.6-139 2-8 3.8-6 0 3 .8-45 0 3.6-100 0 3.6-140 2-8 3.8-7 0 3 .8-46 0 3 .6-101 121 3.6-141 2-8 3.8-8 105 3 .8-47 0 3.6-102 121 3.6-142 2-8 3. 8-8a 105 3 .8-48 3-2 3 .6-103 121 3.7-1 110 3.8-9 105 3.8-49 134 3 .6-104 6-5 3.7-2 110 3.8-10 0 3 .8-50 0 3 .6-105 110 3.7-3 110 3.8-11 0 3 .8-51 125 3.6-106 3.7-4 1 3.8-12 0 3. 8-51a 125 3.6-107 6-5 3.7-5 1 3.8-13 0 3.8-52 125 6-5 3.6-108 6-5 3.7-6 0 3.8-14 127 3. 8-52a 125 3 .6-109 6-5 3.7-7 3-1 3.8-15 139 3. 8-52b 125 3.6-110 6-5 3.7-8 1 3.8-16 102 3.8-53 125 3 .6-111 3.7-9 0 3.8-17 102 3.8-54 125 3 .6-112 3.7-10 132 3.8-18 127 3.8-55 0 3 .6-113 6-5 3.7-11 132 3.8-19 117 3 .8-56 120 3.6-114 0 3.7-12 132 3.8-20 117 3 .8-57 120 3.6-115 3 .7-12a 132 3.8-21 102 3.8-58 120 3.6-116 3.7-13 132 3.8-22 113 3.8-59 110 3 .6-117 3.7-14 132 3 .8-23 113 3.8-60 110 3 .6-118 3.7-15 132 3.8-24 113 3 .8-61 115 3.6-119 135 3.7-16 132 3. 825 102 3.8-62 0 3.6-120 119 3.7-17 4-4 3.8-26 102 3.8-63 0 3.6-121 2-4 3.7-18 110 3.8-27 113 3.8-64 0 3.6-122 3.7-19 6-13 3.8-28 113 3.8-65 0 3.6-123 2-4 3.7-20 115 3.8-29 113 3.8-66 1 2-4 3.6-124 2-4 3.7-21 6-13 3.8-30 113 3.8-67 4-5 3.6-125 3.7-22 .0 3.8-31 102 3 .8-68 4-5 2-4 3.6-126 2-4 3.7-23 0 3 .8-32 3-1 3.8-69 1 3.6-127 3.7-24 1 3 .8-33 3-1 3.6-128 110 3.7-25 137 3 .8-34 110 3.6-129 3-4 3.7-26 137 3.8-35 0 3.7-27 0 RIVER BEND TSB-d Revision No. 139

Control Rod Scram Times B 3.1.4 BASES (continued)

SURVEILLANCE The four SRs of this LCO are modified by a Note stating that during a REQUIREMENTS single control rod scram time surveillance, the CRD pumps shall be isolated from the associated scram accumulator. With the CRD pump isolated (i.e., charging valve closed), the influence of the CRD pump head does not affect the single control rod scram times. During a full core scram, the CRD pump head would be seen by all control rods and would have a negligible effect on the scram insertion times.

SR 3.1.4.1 The scram reactivity used in DBA and transient analyses is based on assumed control rod scram time. Measurement of the scram times with reactor steam dome pressure > 950 psig demonstrates acceptable scram times for the transients analyzed in References 3 and 4.

Scram insertion times increase with increasing reactor pressure because of the competing effects of reactor steam dome pressure and stored -

accumulator energy. Therefore, demonstration of adequate scram times at reactor steam dome pressure greater than 950 psig ensures that the scram times will be within the specified limits at higher pressures. Limits are specified as a function of reactor pressure to account for the sensitivity of the scram insertion times with pressure and to allow a range of pressures over which scram time testing can be performed. To ensure scram time testing is performed within a reasonable time following a shutdown > 120 days, all control rods are required to be tested before exceeding 40% RTP. This Frequency is acceptable, considering the additional surveillances performed for control rod OPERABILITY, the frequent verification of adequate accumulator pressure, and the required testing of control rods affected by fuel movement within the associated core cell and by work on control rods or the CRD System.

SR 3.1.4.2 Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains "representative" if no more than 71/2% of the control rods in (continued)

RIVER BEND .B 3.1-24 Revision No. 139

Control Rod Scram Times B 3.1.4

BASES, SURVEILLANCE SR 3.1.4.3 (continued)

REQUIREMENTS The Frequency of once prior to declaring the affected control rod OPERABLE is acceptable because of the capability of testing the control rod over a range of operating conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.

SR 3.1.4.4 When work that could affect the scram insertion time is performed on a control rod or CRD System or when fuel movement within the reactor..

pressure vessel occurs, testing must be done to demonstrate each affected control rod is still within the limits of Table 3.1.4-1 with the reactor steam dome pressure 5 950 psig. Where work has been performed at high reactor pressure, the requirements of SR 3.1.4.3 and SR 3.1.4.4 will be satisfied with one test. For a control rod affected by work performed while shut down, however, a zero pressure and a high pressure test may be required. This testing ensures that the control rod scram performance is acceptable for operating reactor pressure conditions prior to withdrawing the control rod for continued operation.

Alternatively, a test during hydrostatic pressure testing could also satisfy both criteria. When fuel movement within the reactor pressure vessel occurs, only those control rods associated with the core cells affected by the fuel movement are required to be scram time tested. During a routine refueling outage, it is expected that all control rods will be affected.

The Frequency of once prior to exceeding 40% RTP is acceptable because of the capability of testing the control rod at the different conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.

REFERENCES 1,. 10 CFR 50, Appendix A, GDC 10.

2. USAR, Section 4.3.2.5.5.
3. USAR, Section 4.6.1.1.2.5.3.
4. USAR, Section 5.2.2.2.3.
5. USAR, Section 15.4.1.
6. USAR, Section 15.4.9.

RIVER BEND B 3.1-26 Revision No. 139

Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1 BASES APPLICABLE 5.e. Drywell Pressure-High (continued)

SAFETY ANALYSES, LCO, and The Allowable Value was selected to be the same as the ECCS Drywell APPLICABILITY Pressure-High Allowable Value (LCO 3.3.5.1), since this may be indicative of a LOCA inside primary containment.

This Function isolates the Group 10 and 14 valves.

5.f. Manual Initiation The Manual Initiation push button channels introduce signals into the RHR Shutdown Cooling System isolation logic that are redundant to the automatic protective instrumentation and provide manual isolation capability. There is no specific USAR safety analysis that takes credit for this Function. It is retained for the isolation function as required by the NRC in the plant licensing basis.

There are four push buttons for the logic, two manual initiation push buttons per trip system. There is no Allowable Value for this Function since the channels are mechanically actuated based solely on the position of the push buttons.

Four channels of the Manual Initiation Function are available and are required to be OPERABLE.

ACTIONS The ACTIONS are modified by two Notes. Note 1 allows penetration flow path(s), with the exception of the drywell 24 inch purge valve flow path, to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment and/or drywell isolation is indicated.

Note 2 has been provided to modify the ACTIONS related to primary containment and drywell isolation instrumentation channels. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or, not within limits will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition.

However, the Required Actions for inoperable primary containment and drywell isolation instrumentation channels provide appropriate compensatory measures for separate inoperable channels. As such, a Note has been provided that allows separate Condition entry for each inoperable primary containment and drywell isolation instrumentation channel.

(continued)

RIVER BEND B 3.3-159 Revision No. 139

RHR Suppression Pool Cooling B 3.6.2.3 BASES ACTIONS B. 1 (continued)

With two RHR suppression pool cooling subsystems inoperable, one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. In this condition, there is a substantial loss of the primary containment pressure and temperature mitigation function. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and the potential avoidance of a plant shutdown transient that could result in the need of the RHR suppression pool cooling subsystems to operate.

C.1 and C.2 If the Required Action and required Completion Time of Condition A cannot be met or if two RHR suppression pool cooling subsystems are inoperable, 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 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 3.6.2.3.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, and automatic valves, in the RHR suppression pool cooling mode flow path provides assurance that the proper flow path exists for system operation.

This SR does not apply to valves that are locked, sealed, or otherwise, secured in position since these valves were verified to be in the correct position prior to being locked, sealed,.or secured. A valve is also allowed to be in the nonaccident position, provided it can be aligned to the accident position within the time assumed in the accident analysis. This is acceptable, since the RHR suppression pool cooling mode is manually initiated. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositiorned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.

The Frequency of 31 days is justified because the valves are operated under procedural control, improper valve position would affect only a single subsystem, the probability of an event requiring initiation of the system is low, and the subsystem is a manually initiated system. This Frequency has been shown to be acceptable, based on operating experience.

(continued)

RIVER BEND B 3.6-64 Revision No. 139

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued)

REQUIREMENTS SR 3.8.1.7 requires that, at a 184-day Frequency, the DG starts from standby conditions and achieves the required voltage and frequency within 10 seconds for DG 1A and DG 1B and 13 seconds for DG .1C. The start requirements for each DG support the assumptions in the design basis LOCA analysis (Ref. 5). The start requirements may not be applicable to 3.8.1.2 (see Note 3 of SR 3.8.1.2), when a modified start as described above is used. If a modified start is not used, the start requirements of SR 3.8.1.7 apply. Since SR 3.8.1.7 does require a 10 second start for DG 1A and DG 1B and 13 seconds for DG 1C, it is more restrictive than SR 3.8.1.2, and it may be performed in lieu of SR 3.8.1.2.

This is the intent of Note 1 of SR 3.8.1.2. Similarly, the performance of SR 3.8.1.12 or SR 3.8.1.19 also satisfies the requirements of SR 3.8.1.2 and SR 3.8.1.7.

In addition to the SR requirements, the time for the DG to reach steady state operation, unless the modified DG start method is employed, is periodically monitored and the trend evaluated to identify degradation of governor and voltage regulator performance.

The normal 31 day Frequency for SR 3.8.1.2 is consistent with the industry guidelines for assessment of diesel generator performance (Refs. 14 and 15). The 184 day Frequency for SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7). These Frequencies provide adequate assurance of DG OPERABILITY, while, minimizing degradation resulting. from testing.

..2 SR 3.8.1.3 This Surveillance demonstrates that the DGs are capable of synchronizing and accepting the surveillance test load of,3,00 - 3,100 kW. These Technical Specification load values were selected in view of human engineering considerations that the smallest graduation on the watt meter is 100 kW. The minimum run time of 60 minutes is required to stabilize engine temperatures, while minimizing the time that the DG is connected to the offsite source.

Although no power factor requirements are established by this SR, the DG is normally operated at a power factor between 0.8 lagging and 1.0.

The 0.8 value is the design rating of the machine, while 1.0 is an operational limitation to ensure circulating (continued)

RIVER BEND B 3.8715 Revision No. 139

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