ML20115C997

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Revised McGuire Nuclear Station Selected Licensee Commitiments Manual
ML20115C997
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 06/25/1996
From: Crane K
DUKE POWER CO.
To:
References
PROC-960625, NUDOCS 9607120233
Download: ML20115C997 (12)


Text

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av...a v. sv J., ., FORM 901.1/REV. 89 DesPostTIOf3 OF THE ORIO4 MAL NORMAL DOCUMENT W SE TO TNT PRIORITY TnANsMITTAL SIGNATURE Uts-LEss REC PsENT es OTHERWisE .

IDENTW1ED BELOW.

DUKE POWER COMPANY (1) 1756 J B JONES MG01UC DATE: 06/27/96 (213759 U S NUCLEAR REG UASH, DC DOCUMENTTRANSMITTAL FORM DOCUMENT TRANSMITTAL, 15.478 (3)

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REFERENCE:

gg) OTHER ACMNOWLEDGEMENTREQUIRED hYES (9) MCGUIRE NUCLEAR STATION IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED. PLEASE (10) SELECTED LICENSEE AMEgNRECEPT W RETURNING THIS FORM OR DN till C0MMITMENTS HANUAL McGute Nudear Station gjgg P O. Box 12700 Document Managerrwwt MG02DM (13) Hagers rerry Road g14) HurWersviRe.NeettiCarolina 29078 (15)

(16) Rec d sy Dare (17)

(18) PAGE 4 0F 4 0A "~

DOCUMENT NO. Cn DI 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 TOTAL COND Ue'S SLC PG. 16.5-1 NA NA 06/27/96 MADM-03 71 V1- 80 SLC PG. 16.5-2 NA 4A 06/27/96 SLC PG. 16.5-2A NA 9A 06/27/96 9607120233 960625 PDR ADOCK 05000369 P PDR REMARKS:

/ T C MCMEEKIN T) VICE PRESIDENT MCGUIRE NUCLEAR STATION BY VAY I PD M MG01PP kl P/r_lR

_ _ . - . . ~ _ _ . _ _ . _ ,. _ __ .. _ _. . . . . _ _ . . _ . _ _ _ . _ . .

i June 25, 1996 ,

To: All Holders of'the Selected Licensee Commitments Manual Please find attached a revision to the subject manual. Your' ,

copy of the SLC manual should be revised as follows: '

l Remove these pages: Insert these pages: 1 J

List of Effective Pages List of--Effective Pages Revision 13 Revision 14 i

Page 16.5-1 Page 16.5-1 l Page 16.5-2 Page 16-5-2 Page 16.5-2a l Questions or problems should be directed to Kay Crane, l McGuire Regulatory Compliance at extension 4306.

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Kay L. Crane,

n McGuire Regulatory Compliance

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McGuire Nuclear station <

Selected Licensee Comunitments i

( List of Effective Pages ]

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Page Revision Date LOEP Tab i

List of Effective Pages 14 1 through 9 j Tab 16 J

$ 16.0-1 4/96 .-

16.0-2 4/96 Tab ifJ l

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l Tab 16.5 16.5-1 6/96 16.5-2 6/96 16.5-2a 6/96 16.5-3 3/93 e

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16,5-7 3/93 16.5-8 3/93 16.5-9 3/93 16.5-10 3/93 Tab 16.6 l Tab 16.7 16.7-1 -

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(j 16'.7-2 8/95 16.7-3 8/95 16.7-4 8/95 16.7-5 8/95 16.7-6 8/95 16.7-7 8/95 16.7-8 8/95 16.7-9 8/95 16.7-10 8/95 l 16.7-11 8/95 l 16.7-12 8/95 16.7-13 8/95 16.7-14 8/95 l Tab 16.8 16.8-1 10/90 1

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( ,) Table 16.8-la 1 of 28 10/94 j

Table 16.8-la 2 of 28 5/96 Table 16.8-la 3 of 28 10/94 Table 16.8-la 4 of 28 10/94 Table 16.8-la 5 of 28 10/94 Table 16.8-la 6 of 28 10/94 Table 16.8-la 7 of 28 10/94 Table 16.8-la 8 of 28 10/94 I

Table 16.8-la 9 of 28 10/94 Table 16.8-la 10 of 28 10/94 Table 16.8-la 11 of 28 10/94 Table 16.8-la 12 of 28 10/94 Table 16.8-la 13 of 28 10/94 l Table 16.8-la 14 of 28 10/94 Table 16.8-la 15 of 28 10/94

/~N Table 16.8-la 16 of 28 10/94 k Table 16.8-la 17 of 28 10/94 Table 16.8-la 18 of 2E 10/94 Revision 14 Page 2 I

Page Revision Date f( ) Ta'ble 15.8-la 19 of 28 10/94 Table 16.8-la 20 of 28 10/94 Table 16.8-la 21 of 28 10/94 Table 16.8-la 22 of 28 10/94 Table 16.8-la 23 of 28 10/94 Table 16.8-la 24 of 28 10/94 Table 16.8-la 25 of 28 10/94 Table 16.8-la 26 of 28 10/94 Table 16.8-la 27 of 28 5/96 Table 16.8-la 28 of 28 10/94 Table 16.8-lb 1 of 30 10/94 Table 16.8-1b 2 of 30 5/96 Table 16.8-1b 3 of 30 10/94 Table 16.8-1b 4 of 30 10/94 Table 16.8-1b E cf 30 10/94

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Table 16.8-1b 29 of 30 10/94 Table 16.8-1b 30 of 30 10/94 16.8-2 4/96 16.8-3 4/96 16.8-4 4/96 Tab 16.9 16.9-1 2/91 l 16.9-2 16.9-3 16.9-4 (O) 16.9-5 Table 16.9-1 16.9-6 1/96 16.9-7 16.9-8 16.9-9 Table 16.9-2 8/90 '

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l 16.5 REACTOR COOLANT SYSTEM

(} REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less l

than 60" Wide Range NC system level, the following conditions shall be met:

a. If steam generator (S/G) nozzle dams arb in use, at least f

l one hot leg vent path shall remain open whenever the reactor vessel head is in place. The vent path may be satisfied by:

1. No hot leg nozzle dam installed l

AND

2. Removal of either:
i. A hot leg diaphragm and manway, ii. A cold leg diaphragm and manway in the vented loop.

() b. If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater:

l l 1. A hot leg vent path shall be provided. The vent path may be satisfied by the removal of either:

i. hot leg S/G manway and diaphragm (no hot leg

! nozzle dam) l l ii. no hot leg nozzle dam and cold leg menway and diaphragm in the same steam generator iii. by the removal of the reactor vessel head l

OR  ;

2. Containment closure shall be achievable prior to ,

the onset of core boiling. '

i I6.5-1 i

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c. A, detailed review of each outage schedule which involves O operation at reduced inventory shall be conducted, looking in particular at Evolutions which could perturb the NCS.
d. Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor,
e. The reactor has been subcritical for at least 7 days; or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218. '

REMEDIAL ACTIONS:

a. With the vent path of 16.5-la not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.

TESTING REOUIREMENTS:

None

()

REFERENCES:

1) Generic Letter 88-17, Loss of Decay Heat Removal 2 ) NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle
3) Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities
4) McGuire Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5) Management McGuire Station Directive 3.1.3 (MSD403) Shutdown Risk Guidelines.
6) Design Study: CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services.
7) Design Study: MGDS-0228/CNDS-0218, McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator l Mitigation, Safety Analysis, Engineering Support Section, l Design Engineering Department.

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BASIS:

O Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC system reduced i inventory. Numerous events have occurred in the industry that i resulted in a loss of residual heat removal during reduced inventory operation. This is of great concern due to the potential for substantial core damage occurring in a'relatively short time period.

l This selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.

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