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{{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 P..... | ||
YIODES 1, 2, 3 and 4.ACTION: Mith eith r (a)th m asured ov rail int rated con,ainm nt 1 akage rate exceeding 0.75 La or (b)with the measured combined leakage rate for all p netrations and valv s subject to Types B and C tests exc eding 0.60 L r store th leakag rate(s)to within the limit(s)prior to increasing the R ac or Coolant Syst m t mp rature above 200'F.SURYEILLAHC" REQUIRE,"!="H S 4.6.1.2 Th~con.ainm nt leakag rat s shall b d monstrat d at th following t~st schedule and shall be determined in conforrance with the crit ria sp cifi d in Appendix J of 10 CFR 50 using the m thods and provisions of ANSI N45.4-1972: | PDR ADOCK 05000315 PDR | ||
a.shu4de 6 Ql Q (Qy~~TM~p~~CL,MA LCh'\0~4 I~ | |||
uheequent | COHTAINHENT SYST:-~S CONTAINS=.HT LDKAC= | ||
~ay-be-resumed a'ach containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3-%45 pR-i~Yon4i>~~g,h~(+ | LIl'IITING CONDITION rOR 0. "=RATIOH 3.6.1.2 Containm nt leakag rates shall be limited to: | ||
b)AQIc COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.~- | : a. An overall integrat d leakage rat of <L, 0.25 p rc nt by weight of the containment air per 24 hours at P, 12.0 psig, and | ||
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of<L, 0.25 percent by weight of the containment air per 24 hours at P, 12 psig.b.A combined leakage rate of<0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P. | : b. A combin d leakaoe rate of <0.60 La for all penetra ions and valves subj ct to Type B and C tests wh n pr ssuriz d to P APPLICABILiTY: YIODES 1, 2, 3 and 4. | ||
MODES 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the overall integrated leakage rate to<0.75 L and the coimttbined leakage rate for all penetrations and valves subjec$to Type B and C tests to<0.60 L prior to increasing the Peactor Coolant System temperature above$00'F.SURVEI LLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: | ACTION: | ||
Mith eith r (a) th m asured ov rail int rated con,ainm nt 1 akage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all p netrations and valv s subject to Types B and C tests exc eding 0.60 L r store th leakag rate(s) to within the limit(s) prior to increasing the R ac or Coolant Syst m t mp rature above 200'F. | |||
-be-cenducted-at t | SURYEILLAHC" REQUIRE,"!="H S 4.6.1.2 Th~ con.ainm nt leakag rat s shall b d monstrat d at th following t~st schedule and shall be determined in conforrance with the crit ria sp cifi d in Appendix J of 10 CFR 50 using the m thods and provisions of ANSI N45.4-1972: | ||
a. | |||
ghee-ll shu4de lgg 5 g 6) 4k 04 Ql Q (Qy~~ TM~p~~ CL,MA LCh'\ 0~4 I~ | |||
<k~ba-.~~d~~(r~m d.A-wee | wW. +W ~~i~e.n ~+5 s~i~i~ ~~ | ||
O.ir | ~~g,pi~ + aqpnoued w<~p4>< | ||
p t < + < ~Q ~<p )~< I< ~ VEC LgKEA I | |||
f One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which.allows the provisions of Technical Specification 4.0.8 to be applicable. | g~PtI++~ ~\ >6 Sp~t<'+ | ||
COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 ARE%)MENT NO.444. | ~~ ~)p).~4~~ | ||
ATTACHMENT 3 TO AEP:NRC:1215 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of sL~, 0.25 percent by weight of the containment air per 24 hours at | $ ~ I 41 (.~4 >~ g o z ~a+ | ||
Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L~restore the leakage rate(s)to within the limit(s)prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6'.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be | D. C. COOK-UNIT 1 3/4 6-2 Amendment Ho. +8- | ||
a~Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions. | ) | ||
b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.The provisions of Specification 4.0.2 are not applicable. | |||
COOK NUCLEAR PLANT-UNIT 1 3/4 6-2 AMENDMENT NO. | uheequent Typ~~ est s s~k-b o-sense sos-me | ||
This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.440, CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of | . ~ae-the-aha ~ay-be-resumed a'ach containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3- | ||
Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L~, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 | %45 pR- i~Yon4i>~~g,h~(+ b)AQIc COOK NUCLEAR PLANT - UNIT 1 3/4 6-3 AMENDMENT NO. ~- | ||
a.Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.t b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.c~The provisions of Specification 4.0.2 are not applicable. | |||
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: | |||
: a. An overall integrated leakage rate of < L, 0.25 percent by weight of the containment air per 24 hours at P, 12 psig. | |||
: b. A combined leakage rate of < 0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P . | |||
MODES 1, 2, 3 and 4. a'PPLICABILITY: | |||
ACTION: | |||
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the overall integrated leakage rate to < 0.75 L and the coimttbined leakage rate for all penetrations and valves subjec$ | |||
to Type B and C tests to < 0.60 L prior to increasing the Peactor Coolant System temperature above $ 00'F. | |||
SURVEI LLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the Yl ~~ ~'-4 criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: | |||
4a4e-)-chal-1 skukde A-4 be-cenducted-at 40-t et N-month iMa.val~uHng. | |||
aha-l-l-be-cenduct-ed-du.r4og 4s er+od;. | |||
the shv4dew Tb~S A, 8, C,<g 6 Eo~agg. X~QrP~Qed amel P~~l+es4,~ <k~ ba- .~~d ~~ LCC.+ | |||
(r ~m d.A-wee reIbAA-Irem~%s s~i4'I'~ 1~ +~<diz~ 4o to ct a.~o,'cA> wodI4I~+ | |||
hr~bI~ Lee-4~ | |||
m <+4 | |||
: 4. E~ ~ >+~~~ | |||
+1 ~N ~mw~p flows. | |||
a.O~Wni~~+ O.ir cJC -5kCJUL ~ g~Ig,~ +~ Q. iA a~P Ii~~~ | |||
1I f 8 C* I | |||
~La ~0%'i+ ic9M 5 ~4 + ~<41 ch+Io & QO, Q ~r~ ~g+ Qpti~p | |||
+ I'c~ ~aqe. o~ ps+ Stan I -S) | |||
D. C. COOK - UNIT 2 3/4 6-2 | |||
CON TAIHHEHT SYSTEMS SURVEILLANCE RE UERMEhTS Continued g ~ | |||
g ~ | |||
~4-4o-be-e~~eat t measured l-eatage-r ndu~Mw Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3. | |||
er~nmb | |||
&~+em, The provisions of Specification 4.0.2 are not applicable. | |||
f One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which. allows the provisions of Technical Specification 4.0.8 to be applicable. | |||
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 ARE%)MENT NO. 444. | |||
ATTACHMENT 3 TO AEP:NRC:1215 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES | |||
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: | |||
: a. An overall integrated leakage rate of sL~, 0.25 percent by weight of the containment air per 24 hours at P 12.0 psig, and | |||
: b. A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,. | |||
APPLICABILITY: Modes 1, 2, 3 and 4. | |||
ACTION: | |||
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L~ restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200'F. | |||
SURVEILLANCE RE UIREMENTS 4.6 '.2 The containment leakage rates shall be demonstrated at the following determined in conformance with the test schedule and shall be criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: | |||
a ~ Types A, B, and C (Overall Integrated and Local Combined Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions. | |||
: b. Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3. | |||
The provisions of Specification 4.0.2 are not applicable. | |||
COOK NUCLEAR PLANT - UNIT 1 3/4 6-2 AMENDMENT NO. | |||
This page intentionally left blank. | |||
COOK NUCLEAR PLANT - UNIT 1 3/4 6-3 AMENDMENT NO. 440, | |||
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: | |||
: a. An overall integrated leakage rate of sL 0.25 percent by weight of the containment air per 24 hours at P 12.0 psig, and | |||
: b. A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,. | |||
APPLICABILITY: Modes 1, 2, 3 and 4. | |||
ACTION: | |||
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L~, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L restore the overall integrated leakage rate to s0.75 L, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to z0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F. | |||
SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: | |||
: a. Types A, B, and C (Overall Integrated and Local Combined Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.t | |||
: b. Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3. | |||
c ~ The provisions of Specification 4.0.2 are not applicable. | |||
One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable. | One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable. | ||
COOK NUCLEAR PLANT-UNIT 2 3/4 6-2 AMENDMENT NO.46&, | COOK NUCLEAR PLANT - UNIT 2 3/4 6-2 AMENDMENT NO. 46&, | ||
) | ) | ||
This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 AMENDMENT NO~}} | This page intentionally left blank. | ||
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO ~}} |
Latest revision as of 13:45, 22 October 2019
ML17332A221 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
Issue date: | 07/19/1994 |
From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | |
Shared Package | |
ML17332A220 | List: |
References | |
NUDOCS 9407250177 | |
Download: ML17332A221 (11) | |
Text
ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 P.....
COHTAINHENT SYST:-~S CONTAINS=.HT LDKAC=
LIl'IITING CONDITION rOR 0. "=RATIOH 3.6.1.2 Containm nt leakag rates shall be limited to:
- a. An overall integrat d leakage rat of <L, 0.25 p rc nt by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 12.0 psig, and
- b. A combin d leakaoe rate of <0.60 La for all penetra ions and valves subj ct to Type B and C tests wh n pr ssuriz d to P APPLICABILiTY: YIODES 1, 2, 3 and 4.
ACTION:
Mith eith r (a) th m asured ov rail int rated con,ainm nt 1 akage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all p netrations and valv s subject to Types B and C tests exc eding 0.60 L r store th leakag rate(s) to within the limit(s) prior to increasing the R ac or Coolant Syst m t mp rature above 200'F.
SURYEILLAHC" REQUIRE,"!="H S 4.6.1.2 Th~ con.ainm nt leakag rat s shall b d monstrat d at th following t~st schedule and shall be determined in conforrance with the crit ria sp cifi d in Appendix J of 10 CFR 50 using the m thods and provisions of ANSI N45.4-1972:
a.
ghee-ll shu4de lgg 5 g 6) 4k 04 Ql Q (Qy~~ TM~p~~ CL,MA LCh'\ 0~4 I~
wW. +W ~~i~e.n ~+5 s~i~i~ ~~
~~g,pi~ + aqpnoued w<~p4><
p t < + < ~Q ~<p )~< I< ~ VEC LgKEA I
g~PtI++~ ~\ >6 Sp~t<'+
~~ ~)p).~4~~
$ ~ I 41 (.~4 >~ g o z ~a+
D. C. COOK-UNIT 1 3/4 6-2 Amendment Ho. +8-
)
uheequent Typ~~ est s s~k-b o-sense sos-me
. ~ae-the-aha ~ay-be-resumed a'ach containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3-
%45 pR- i~Yon4i>~~g,h~(+ b)AQIc COOK NUCLEAR PLANT - UNIT 1 3/4 6-3 AMENDMENT NO. ~-
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of < L, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 12 psig.
- b. A combined leakage rate of < 0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P .
MODES 1, 2, 3 and 4. a'PPLICABILITY:
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the overall integrated leakage rate to < 0.75 L and the coimttbined leakage rate for all penetrations and valves subjec$
to Type B and C tests to < 0.60 L prior to increasing the Peactor Coolant System temperature above $ 00'F.
SURVEI LLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the Yl ~~ ~'-4 criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
4a4e-)-chal-1 skukde A-4 be-cenducted-at 40-t et N-month iMa.val~uHng.
aha-l-l-be-cenduct-ed-du.r4og 4s er+od;.
the shv4dew Tb~S A, 8, C,<g 6 Eo~agg. X~QrP~Qed amel P~~l+es4,~ <k~ ba- .~~d ~~ LCC.+
(r ~m d.A-wee reIbAA-Irem~%s s~i4'I'~ 1~ +~<diz~ 4o to ct a.~o,'cA> wodI4I~+
hr~bI~ Lee-4~
m <+4
- 4. E~ ~ >+~~~
+1 ~N ~mw~p flows.
a.O~Wni~~+ O.ir cJC -5kCJUL ~ g~Ig,~ +~ Q. iA a~P Ii~~~
1I f 8 C* I
~La ~0%'i+ ic9M 5 ~4 + ~<41 ch+Io & QO, Q ~r~ ~g+ Qpti~p
+ I'c~ ~aqe. o~ ps+ Stan I -S)
D. C. COOK - UNIT 2 3/4 6-2
CON TAIHHEHT SYSTEMS SURVEILLANCE RE UERMEhTS Continued g ~
g ~
~4-4o-be-e~~eat t measured l-eatage-r ndu~Mw Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
er~nmb
&~+em, The provisions of Specification 4.0.2 are not applicable.
f One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which. allows the provisions of Technical Specification 4.0.8 to be applicable.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 ARE%)MENT NO. 444.
ATTACHMENT 3 TO AEP:NRC:1215 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of sL~, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P 12.0 psig, and
- b. A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.
APPLICABILITY: Modes 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L~ restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE UIREMENTS 4.6 '.2 The containment leakage rates shall be demonstrated at the following determined in conformance with the test schedule and shall be criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a ~ Types A, B, and C (Overall Integrated and Local Combined Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.
- b. Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
The provisions of Specification 4.0.2 are not applicable.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-2 AMENDMENT NO.
This page intentionally left blank.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-3 AMENDMENT NO. 440,
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of sL 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P 12.0 psig, and
- b. A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.
APPLICABILITY: Modes 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L~, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L restore the overall integrated leakage rate to s0.75 L, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to z0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
- a. Types A, B, and C (Overall Integrated and Local Combined Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.t
- b. Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
c ~ The provisions of Specification 4.0.2 are not applicable.
One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-2 AMENDMENT NO. 46&,
)
This page intentionally left blank.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO ~