ML20198P910: Difference between revisions

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{{#Wiki_filter:.  .    ..    ..    .        .      .
{{#Wiki_filter:,
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l NIAGARA MOHAWK G EN E R ATIO N                                   ""'''*"'"***'"***" " "*" "" * * * * #
NIAGARA MOHAWK G EN E R ATIO N BUSINESS GROUP E.7l.TNoo.m October 31,1997
BUSINESS GROUP E.7l.TNoo.m                                                   October 31,1997
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[*flO'Jlg ,                                                   NMP2L 1735 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-410 NPP-69 Gentlemen:
NMP2L 1735 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-410 NPP-69 Gentlemen:
Niagara Mohawk Power Corporation (NMPC) hereby transmits an Application for Amendment to Nine Mile Point Unit 2 (NMP2) Operating License NPF-69. Also enclosed are proposed changes to the Technical Specifications set forth in Appendix A to the above mentioned License. These changes are included as Attachment A. Supporting information and analyses demonstrating that the proposed changes involve no significant hazards consideration pursuant to 10CFR50.92 are included as Attachment B.
Niagara Mohawk Power Corporation (NMPC) hereby transmits an Application for Amendment to Nine Mile Point Unit 2 (NMP2) Operating License NPF-69. Also enclosed are proposed changes to the Technical Specifications set forth in Appendix A to the above mentioned License. These changes are included as Attachment A. Supporting information and analyses demonstrating that the proposed changes involve no significant hazards consideration pursuant to 10CFR50.92 are included as Attachment B.
NMPC proposes to revise Technical Specification Section 2.2, Limiting Safety System Settings, Section 3/4.3.1, Reactor Protection System Instrumentation, and associated Bases, and Section 3/4.3.6, Control Rod Block Instrumentation. These revision: are being proposed to sqport the installation of the Nuclear Measurement Analysis and Control (NUMAC)
NMPC proposes to revise Technical Specification Section 2.2, Limiting Safety System Settings, Section 3/4.3.1, Reactor Protection System Instrumentation, and associated Bases, and Section 3/4.3.6, Control Rod Block Instrumentation. These revision: are being proposed to sqport the installation of the Nuclear Measurement Analysis and Control (NUMAC)
Power Range Neutron Monitor (pRNM) System. The NUMAC PRNM is designed to replace the existing Average Power Range Monitor (APRM) System and to support the eventual activation of the Oscillation Power Range Monitor (OPRM) System required for the       l detection of reactor instability conditions. Technical Specification changes associated with the OPRM System will be submitted via a separate Amendment Application. The proposed modificdon is consistent with NMPC's response to Generic Letter 94-02, "Long-Term
Power Range Neutron Monitor (pRNM) System. The NUMAC PRNM is designed to replace the existing Average Power Range Monitor (APRM) System and to support the eventual activation of the Oscillation Power Range Monitor (OPRM) System required for the l
                                                                                                              /
detection of reactor instability conditions. Technical Specification changes associated with the OPRM System will be submitted via a separate Amendment Application. The proposed
Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulle Instabilities in Boiling Water Reactors."                                                   p\ g fj '
/
modificdon is consistent with NMPC's response to Generic Letter 94-02, "Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulle Instabilities in Boiling Water Reactors."
p\\ g fj '
The proposed Technical Specification changes are consistent with General Electric Licensing Topical Report, NEDC-32410P-A, " Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option III Stability Trip Function,"
The proposed Technical Specification changes are consistent with General Electric Licensing Topical Report, NEDC-32410P-A, " Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option III Stability Trip Function,"
with some minor deviations. NEDC-32410P-A provides licensees guidance for the review and evaluation of the NUMAC-PRNM modification, specific actions required to conform to the Topical Report, and " marked up" Technical Specifications to support the modification.
with some minor deviations. NEDC-32410P-A provides licensees guidance for the review and evaluation of the NUMAC-PRNM modification, specific actions required to conform to the Topical Report, and " marked up" Technical Specifications to support the modification.
Attachment C to this Application, Plant-Specific Information Required for NUMAC-PRNM 9711120052 971031 DR ADOCK O             40 lllllllll
Attachment C to this Application, Plant-Specific Information Required for NUMAC-PRNM 9711120052 971031 DR ADOCK O 40 lllllllll


1 1        34 l
1 34 l
l                    Page 2 i
Page 2 i
;                    Retrofit, provides a table which lists the required utility actions delineated in the Topical Report and NMPC's response. This Topical Report was approved by the Commission by j                     letter to the NUMAC Projects Manager dated September 5,1995. In their acceptance letter,
Retrofit, provides a table which lists the required utility actions delineated in the Topical Report and NMPC's response. This Topical Report was approved by the Commission by j
)                     Section 5.0, Plant Specific Actions, the Commission requested certain information from i                     licensees referencing NEDC-32410P A for implementation of the NUMAC-PRNM. This i                     information is provided in Attachment D. Supplement 1 to NEDC-32410P A provided
letter to the NUMAC Projects Manager dated September 5,1995. In their acceptance letter,
.                    clarifications to NEDC-32410P A and developed specific proposed TSs to implement the i
)
OPRM. Information in Supplement I relating to response time testing requirements has been
Section 5.0, Plant Specific Actions, the Commission requested certain information from i
;                    included in this submittal. Supplement I was approved by the NRC by letter to the i                     NUMAC Project Manager dated December 26,1996. Attachment E to this Application
licensees referencing NEDC-32410P A for implementation of the NUMAC-PRNM. This i
-l                   provides a " marked up" copy of our current Technical Specifications.
information is provided in Attachment D. Supplement 1 to NEDC-32410P A provided clarifications to NEDC-32410P A and developed specific proposed TSs to implement the i
W j                     The NUMAC PRNM modification is scheduled to be installed during our next refueling outage (RFO6) currently planned for the Spring of 1998. Accordingly, approval of this
OPRM. Information in Supplement I relating to response time testing requirements has been included in this submittal. Supplement I was approved by the NRC by letter to the i
:                    amendment is requested by April 1,1998, to support our outage planning schedule, NMPC i                     also requests the flexibility to implement this amendment upon completion and acceptance of
NUMAC Project Manager dated December 26,1996. Attachment E to this Application
;                    the NUMAC PRNM modification, versus the normal 30 day implementation requirement.
-l provides a " marked up" copy of our current Technical Specifications.
:                    Pursuant to 10CFR50.91(b)(1), NMPC has provided a copy of this license amendment request and the associated analyses regarding no significant hazards consideration to the i                     appropriate state representative.
W j
The NUMAC PRNM modification is scheduled to be installed during our next refueling outage (RFO6) currently planned for the Spring of 1998. Accordingly, approval of this amendment is requested by April 1,1998, to support our outage planning schedule, NMPC i
also requests the flexibility to implement this amendment upon completion and acceptance of the NUMAC PRNM modification, versus the normal 30 day implementation requirement.
Pursuant to 10CFR50.91(b)(1), NMPC has provided a copy of this license amendment request and the associated analyses regarding no significant hazards consideration to the i
appropriate state representative.
Very truly yours, t
Very truly yours, t
0     ,    b B. Ralph Sy la Chief Nuclear Officer BRS/JMT/Imc Attachments xc:     Mr. H. J. Miller, NRC Regional Administrator Mr. A. W. Dromerick, Acting Director, Project Directorate 11, NRR
0 b
                              - Mr. B. S. Norris, Senior Resident _ Inspector Mr. D. S. Hood, Senior Project Manager, NRR Mr. J. P. Spath NYSERDA 2 Empire Plaza, Suite 1901 Albany, NY 12223-1253 Records Management}}
B. Ralph Sy la Chief Nuclear Officer BRS/JMT/Imc Attachments xc:
Mr. H. J. Miller, NRC Regional Administrator Mr. A. W. Dromerick, Acting Director, Project Directorate 11, NRR
- Mr. B. S. Norris, Senior Resident _ Inspector Mr. D. S. Hood, Senior Project Manager, NRR Mr. J. P. Spath NYSERDA 2 Empire Plaza, Suite 1901 Albany, NY 12223-1253 Records Management}}

Latest revision as of 10:30, 10 December 2024

Transmits Application for Amend to OL NPF-69 & Proposed Changes to TS Sections 2.2,3/4.3.1 & 3/4.3.6.Supporting Info Including Markup of TS & NSHC Encl
ML20198P910
Person / Time
Site: Nine Mile Point 
Issue date: 10/31/1997
From: Sylvia B
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059B766 List:
References
NMP2L-1735, NUDOCS 9711120052
Download: ML20198P910 (2)


Text

,

O Oo l

NIAGARA MOHAWK G EN E R ATIO N BUSINESS GROUP E.7l.TNoo.m October 31,1997

[*flO'Jlg,

NMP2L 1735 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-410 NPP-69 Gentlemen:

Niagara Mohawk Power Corporation (NMPC) hereby transmits an Application for Amendment to Nine Mile Point Unit 2 (NMP2) Operating License NPF-69. Also enclosed are proposed changes to the Technical Specifications set forth in Appendix A to the above mentioned License. These changes are included as Attachment A. Supporting information and analyses demonstrating that the proposed changes involve no significant hazards consideration pursuant to 10CFR50.92 are included as Attachment B.

NMPC proposes to revise Technical Specification Section 2.2, Limiting Safety System Settings, Section 3/4.3.1, Reactor Protection System Instrumentation, and associated Bases, and Section 3/4.3.6, Control Rod Block Instrumentation. These revision: are being proposed to sqport the installation of the Nuclear Measurement Analysis and Control (NUMAC)

Power Range Neutron Monitor (pRNM) System. The NUMAC PRNM is designed to replace the existing Average Power Range Monitor (APRM) System and to support the eventual activation of the Oscillation Power Range Monitor (OPRM) System required for the l

detection of reactor instability conditions. Technical Specification changes associated with the OPRM System will be submitted via a separate Amendment Application. The proposed

/

modificdon is consistent with NMPC's response to Generic Letter 94-02, "Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulle Instabilities in Boiling Water Reactors."

p\\ g fj '

The proposed Technical Specification changes are consistent with General Electric Licensing Topical Report, NEDC-32410P-A, " Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option III Stability Trip Function,"

with some minor deviations. NEDC-32410P-A provides licensees guidance for the review and evaluation of the NUMAC-PRNM modification, specific actions required to conform to the Topical Report, and " marked up" Technical Specifications to support the modification.

Attachment C to this Application, Plant-Specific Information Required for NUMAC-PRNM 9711120052 971031 DR ADOCK O 40 lllllllll

1 34 l

Page 2 i

Retrofit, provides a table which lists the required utility actions delineated in the Topical Report and NMPC's response. This Topical Report was approved by the Commission by j

letter to the NUMAC Projects Manager dated September 5,1995. In their acceptance letter,

)

Section 5.0, Plant Specific Actions, the Commission requested certain information from i

licensees referencing NEDC-32410P A for implementation of the NUMAC-PRNM. This i

information is provided in Attachment D. Supplement 1 to NEDC-32410P A provided clarifications to NEDC-32410P A and developed specific proposed TSs to implement the i

OPRM. Information in Supplement I relating to response time testing requirements has been included in this submittal. Supplement I was approved by the NRC by letter to the i

NUMAC Project Manager dated December 26,1996. Attachment E to this Application

-l provides a " marked up" copy of our current Technical Specifications.

W j

The NUMAC PRNM modification is scheduled to be installed during our next refueling outage (RFO6) currently planned for the Spring of 1998. Accordingly, approval of this amendment is requested by April 1,1998, to support our outage planning schedule, NMPC i

also requests the flexibility to implement this amendment upon completion and acceptance of the NUMAC PRNM modification, versus the normal 30 day implementation requirement.

Pursuant to 10CFR50.91(b)(1), NMPC has provided a copy of this license amendment request and the associated analyses regarding no significant hazards consideration to the i

appropriate state representative.

Very truly yours, t

0 b

B. Ralph Sy la Chief Nuclear Officer BRS/JMT/Imc Attachments xc:

Mr. H. J. Miller, NRC Regional Administrator Mr. A. W. Dromerick, Acting Director, Project Directorate 11, NRR

- Mr. B. S. Norris, Senior Resident _ Inspector Mr. D. S. Hood, Senior Project Manager, NRR Mr. J. P. Spath NYSERDA 2 Empire Plaza, Suite 1901 Albany, NY 12223-1253 Records Management