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      ' :!              E UNITED STATES NUCLEAR REGULATORY COMMISSION
        ",                                          WASHINGTON, D.C. enana anni OMAHA PUBLIC POWER DISTRICT DOCKET NQ.60-285 FORT CALHOUN STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. DPR-40
: 1. The Nuclear Regulatory Commission (the Commission) has fount ^ at:
A. The application for amendment by the Omaha Public Pr ver District (the licensee) dated January 9,1995, as supp%mented by letters dated October 17,1996, and January 26,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFP Chapter I; B. The facility will operate in conformity with the s,pplication, the provisions of the Act, and the rules and regu!ations of the Commission;.
C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted h compliance with the Commission's regulations; D. The issuance of this Ocense amendment will not be inimical to the common defense and security or to t're hea'th and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commbsion's regulations and all applicable requirements have been satisfied.
4 9802240029 900126 PDR    ADOCK 05000295 P                      pog                                                                                  i
 
            -t
: 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:
B. Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.183, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
: 3. The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. Raynard Wharton, Project Manager Project Directorate IV-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
 
==Attachment:==
Changes to the Tecnnical
* Specifications Date of Issuance:      January ?6, 1998 r
4
 
i ATTACHMENT TO LICENSE AMENDMENT NO.183 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 l
l-    Revise Appendix "A" Technical Specifications as indicated below. The revised pages are j      identified by amendment number and contain vr.rtical lines indicating the area of change.
1 REMOVE PAGES                                        INSERT PAGES li                                                  li 2-100                                              2-100 3-16b                                              3-16b                l 3-16e                                              3-16c s          ,
 
l        ,
TABLE OF CONTENTS (Continued)
P.111 2.12 Control Room Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-59 2.13 Nuclear Detector Coming System . . . . . . . . . . . . . . . . . . . . ...... .. . . ... 2-60 2.14 Engineered Safety Features System Initiation Instrumentation Settings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 61 2.15 Instrumentation and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.16 River Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -71 2.17 Miscellaneous Radioactive Material Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-72 2.18 DELETED 2.19 DELETED 2.20 Steam Generator Coolant Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . ..... 2-96 2.21 Post. Accident Monitoring Instrumentation        ...................., ....                                                  . 2-97 2.22 Toxic Gas M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 2-99 3.0  SURVEILLANCE REQUIREMENTS . . . . . .                ....        ... .. ... ......... . . . ... 3-0a 3.1  Instrumentation and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2  Tiquipment and Sampling Tests . . . . . . . . . . . . . . .          ................                                    .. 3-17 3.3  Nctor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance . . . . . . . . . . . . . . . . . . . .                                    . 3 21 3.4  Reactor Coolant System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . . ... 3-36 3.5  Containment Test    ..................................... ...                                                                . 3-37 3.6  Safety injection ard Containment Cooling Systems Tests ... ....... .. .. . .... 3-54 3.7  Emergency Power System Periodic Tests . . . . . . . . . . . . . . . . . . . . . . . . ...                                      . 3-58 3.8  Main Steam isolation Valves ...................                              ................ 3-61 3.9  Auxiliary Feedwater System      ..................................                                                            . 3-62 3.10  Reactor Core Parameters . . . . . . . . . . . . . . . . . .        ............... ..                                        . 3 63 3.11  DELEfED                                                                                                                                        l 3.12  Radioactive Waste Disposal System . . . . . . . . . . . .            ..................                                        . 3-69 3.13  Radioactive Material Sources Surveillance      ............................376 3.14  DETITED 3.15  DELETED 3.16  Residual Heat Removal System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . 3-84 3.17  Steam Generator Tuber . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-86 4.0 ' DESIGN FEATURES        .....................                      ........................41 4.1  Site.....................................................4-1 4.2  Containment Design Features . . . . . . . . . . . . . . . . . . . . . . . .............41 4.2.1    Containment Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2.2    Penetrations ................................... . . . . . . 4-1 4.2.3    Containment Structure Cooling Systems .........................42 li                                      .
Amendmeat N o. ',. . ". . "_ ,'.~,* , ". . , " ,','. . ',^. . '. , ' ,
n- , n, i...n. ., , . ,. ,_ , ,. ,. z. . . , _, , . e.n . , . e. 18 3
 
TABLE i-11 TOX1C GAS MONITORS OPERATING LIMITS Minimum lastrument                                  Operable Channels            Action
                                                                                                              ?
Ammonia Detectors                            2                            (a)(b)
(a)    With one toxic detector inoperable, restore the inoperable detector to OPERABLE status within 7 days, or within the next 6 hours initiate and maintain operation of the control room ventilation system in the recirculation mode of operation.
(b)    With both toxic detectors inoperable, within 1 hour initiate. and maintain operation of the control room ventilation system in the recirculation mode of operation.
I
)
f 2-100                    Amendment No. BhM7,183 4
 
TABLE 3-3 (Continued)
MINIMUM F.NOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONI'ROLS Surveillance Channel Description                  Function              Frequency    Surveillance Method
: 25. Containment Purge Isolation          a. Check              M            a.      Verify valve position using control Valves (PCV-742A, B, C, & D)                                                      room indication.
: 26. Containment flydrogen                a. Check              M            a.      CHANNEL CHECK Ionitors (VA.81 A&B)
: b. Test                Q          b.        Calibrate span /zero using sample gas and check flow rates.
: c. Calibrate          R          c.        CHANNEL CALIBRATION
: 27. Containment Water I.evel            a. Check              M          a.      CHANNEL CHECK Narro v Range (LT-599 A. LT-600)
: b. Calibrate          R          b.      CHANNEL CALIBRATION Wide Range (LT-387 &                a. Check              M          a.      CHANNEL CHECK LT-388)
: b. Calibrate          R            b.      CHANNEL CALIBRATION
: 28. Containment Wide Range              a. Check              M            a.      CHANNEL CIIECK Pressure Indication
: b. Calibrate          R            17.      CHANNEL CALIBRATION
: 29. Toxic Gas Detectors:
YIS.6287A&B (NII)                    a. Check              S            a.      Comparison of readings from redundar,t channels.
b Calibrate          Q            b.      Gas calibration.
316b                        Amendment No. M 'a a2 a'',m'' 'a2.183 j
c-
 
                                                                                              ~              '
I4 j
I 1
TABLE 3-3 (Continued)
:                                            MINIMUM FREOUENCIES FOR CIIECKS. CAL 10 RATIONS AND TFSI'ING OF MISCELLANEOUS INSTRUMENTATION AM CONTROLS Surveillance Channel Description                      Function                Frequency.            %rveillance Method 3
: 30. Core Exit Thermo-                        a. Check                M            a.      CIIANNEL CIIECK couple
: b. Calibrate            R            b.      CilAN!iEL CALIBRATION
: 31. IIcated Junction Thermocoup!e (YE-116A and YE-I16B)                    a. Check                M            a.      CIIANNEL CilECK
                                                                                                                                                                                      ]
: b. Calibrate            R            b.      CilANNEL CALIBRATION PM - Prior to scheduled cold leg moldown below 300"F; monthly whenever temperature remains below 200"F and reactor vessel head is installed.
i e
3-16c                                Amendment No. S'','m,! 3n,!?2,!R2.183
, . _ _ . .}}

Latest revision as of 06:15, 1 January 2021

Amend 183 to License DPR-40,revises TS to Delete Requirements for Toxic Gas Monitoring Sys Contained in TS 2.22 & TS 3.1,table 3-3,item 29,for Toxic Chemicals Except Ammonia
ML20203A413
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/26/1998
From: Wharton L
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20203A377 List:
References
NUDOCS 9802240029
Download: ML20203A413 (7)
v • d • e


Text

I

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[.

' :! E UNITED STATES NUCLEAR REGULATORY COMMISSION

", WASHINGTON, D.C. enana anni OMAHA PUBLIC POWER DISTRICT DOCKET NQ.60-285 FORT CALHOUN STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. DPR-40

1. The Nuclear Regulatory Commission (the Commission) has fount ^ at:

A. The application for amendment by the Omaha Public Pr ver District (the licensee) dated January 9,1995, as supp%mented by letters dated October 17,1996, and January 26,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFP Chapter I; B. The facility will operate in conformity with the s,pplication, the provisions of the Act, and the rules and regu!ations of the Commission;.

C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted h compliance with the Commission's regulations; D. The issuance of this Ocense amendment will not be inimical to the common defense and security or to t're hea'th and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commbsion's regulations and all applicable requirements have been satisfied.

4 9802240029 900126 PDR ADOCK 05000295 P pog i

-t

2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:

B. Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.183, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L. Raynard Wharton, Project Manager Project Directorate IV-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Tecnnical

  • Specifications Date of Issuance: January ?6, 1998 r

4

i ATTACHMENT TO LICENSE AMENDMENT NO.183 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 l

l- Revise Appendix "A" Technical Specifications as indicated below. The revised pages are j identified by amendment number and contain vr.rtical lines indicating the area of change.

1 REMOVE PAGES INSERT PAGES li li 2-100 2-100 3-16b 3-16b l 3-16e 3-16c s ,

l ,

TABLE OF CONTENTS (Continued)

P.111 2.12 Control Room Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-59 2.13 Nuclear Detector Coming System . . . . . . . . . . . . . . . . . . . . ...... .. . . ... 2-60 2.14 Engineered Safety Features System Initiation Instrumentation Settings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 61 2.15 Instrumentation and Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.16 River Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -71 2.17 Miscellaneous Radioactive Material Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-72 2.18 DELETED 2.19 DELETED 2.20 Steam Generator Coolant Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . ..... 2-96 2.21 Post. Accident Monitoring Instrumentation ...................., .... . 2-97 2.22 Toxic Gas M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 2-99 3.0 SURVEILLANCE REQUIREMENTS . . . . . . .... ... .. ... ......... . . . ... 3-0a 3.1 Instrumentation and Control . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Tiquipment and Sampling Tests . . . . . . . . . . . . . . . ................ .. 3-17 3.3 Nctor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance . . . . . . . . . . . . . . . . . . . . . 3 21 3.4 Reactor Coolant System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . . ... 3-36 3.5 Containment Test ..................................... ... . 3-37 3.6 Safety injection ard Containment Cooling Systems Tests ... ....... .. .. . .... 3-54 3.7 Emergency Power System Periodic Tests . . . . . . . . . . . . . . . . . . . . . . . . ... . 3-58 3.8 Main Steam isolation Valves ................... ................ 3-61 3.9 Auxiliary Feedwater System .................................. . 3-62 3.10 Reactor Core Parameters . . . . . . . . . . . . . . . . . . ............... .. . 3 63 3.11 DELEfED l 3.12 Radioactive Waste Disposal System . . . . . . . . . . . . .................. . 3-69 3.13 Radioactive Material Sources Surveillance ............................376 3.14 DETITED 3.15 DELETED 3.16 Residual Heat Removal System Integrity Testing . . . . . . . . . . . . . . . . . . . . . . . . 3-84 3.17 Steam Generator Tuber . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-86 4.0 ' DESIGN FEATURES ..................... ........................41 4.1 Site.....................................................4-1 4.2 Containment Design Features . . . . . . . . . . . . . . . . . . . . . . . .............41 4.2.1 Containment Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2.2 Penetrations ................................... . . . . . . 4-1 4.2.3 Containment Structure Cooling Systems .........................42 li .

Amendmeat N o. ',. . ". . "_ ,'.~,* , ". . , " ,','. . ',^. . '. , ' ,

n- , n, i...n. ., , . ,. ,_ , ,. ,. z. . . , _, , . e.n . , . e. 18 3

TABLE i-11 TOX1C GAS MONITORS OPERATING LIMITS Minimum lastrument Operable Channels Action

?

Ammonia Detectors 2 (a)(b)

(a) With one toxic detector inoperable, restore the inoperable detector to OPERABLE status within 7 days, or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room ventilation system in the recirculation mode of operation.

(b) With both toxic detectors inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate. and maintain operation of the control room ventilation system in the recirculation mode of operation.

I

)

f 2-100 Amendment No. BhM7,183 4

TABLE 3-3 (Continued)

MINIMUM F.NOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONI'ROLS Surveillance Channel Description Function Frequency Surveillance Method

25. Containment Purge Isolation a. Check M a. Verify valve position using control Valves (PCV-742A, B, C, & D) room indication.
26. Containment flydrogen a. Check M a. CHANNEL CHECK Ionitors (VA.81 A&B)
b. Test Q b. Calibrate span /zero using sample gas and check flow rates.
c. Calibrate R c. CHANNEL CALIBRATION
27. Containment Water I.evel a. Check M a. CHANNEL CHECK Narro v Range (LT-599 A. LT-600)
b. Calibrate R b. CHANNEL CALIBRATION Wide Range (LT-387 & a. Check M a. CHANNEL CHECK LT-388)
b. Calibrate R b. CHANNEL CALIBRATION
28. Containment Wide Range a. Check M a. CHANNEL CIIECK Pressure Indication
b. Calibrate R 17. CHANNEL CALIBRATION
29. Toxic Gas Detectors:

YIS.6287A&B (NII) a. Check S a. Comparison of readings from redundar,t channels.

b Calibrate Q b. Gas calibration.

316b Amendment No. M 'a a2 a,m 'a2.183 j

c-

~ '

I4 j

I 1

TABLE 3-3 (Continued)

MINIMUM FREOUENCIES FOR CIIECKS. CAL 10 RATIONS AND TFSI'ING OF MISCELLANEOUS INSTRUMENTATION AM CONTROLS Surveillance Channel Description Function Frequency. %rveillance Method 3
30. Core Exit Thermo- a. Check M a. CIIANNEL CIIECK couple
b. Calibrate R b. CilAN!iEL CALIBRATION
31. IIcated Junction Thermocoup!e (YE-116A and YE-I16B) a. Check M a. CIIANNEL CilECK

]

b. Calibrate R b. CilANNEL CALIBRATION PM - Prior to scheduled cold leg moldown below 300"F; monthly whenever temperature remains below 200"F and reactor vessel head is installed.

i e

3-16c Amendment No. S,'m,! 3n,!?2,!R2.183

, . _ _ . .

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