View source for B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified

{{Adams
| number = ML20237B274
| issue date = 08/12/1998
| title = Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified
| author name = 
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = 
| docket = 05000336
| license number = 
| contact person = 
| document report number = B17385, NUDOCS 9808180154
| package number = ML20237B272
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS &amp; TEST REPORTS
| page count = 13
}}

=Text=
{{#Wiki_filter:__                                    ._     ._.
I                                                                                                                                                                                                   Docket No. 50-336 117385 l
Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Change to Technical Specifications Updating List of Documents Describing the Analytical Methods Specified in Technical Specification 6.9.1.8b Marked Up Pages l
August 1998  l l
1 l
9808180154 980812 PDR     ADOCK 05000336 P                         PDR

ADMINISTRATIVE CONTROLS                                                               NOV p 3 ;; ,_ , 6
     /
      /. Documentation tolerances allowed of    by all thefailures       to lift or reclose design ba(inability' pressurizer PORVs or safety valves.
sis) within and challenges                   to the the t
ANNUAL RADIOACTIVE EFFLUENT REPORT 6.9.1.6   A routine Annual Radioactive Effluent Report covering the operation of the unit during the previous calendar year of operation shall be i
submitted by May 1 of each year.
        . The report shall include that information delineated in the REMODCM.
Any changes to the REMODCM shall           be submitted in the Annual Radioactive Effluent Report.
MONTHLY OPERATING REP 0kr 6.9.1.7   Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident inspector, no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIHTTS REPORT 6.9.1.8   a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.
3/4.1.1.1
{
200*F 3/4.1.1.2 3/4.1.1.4 SHUTDOWN MARGIN SHUTDOWN MARGIN - T       s                        - T*V9 > 200*F ModeratorTemperatuN9 Coefficient 3/4.1.3.6        Regulating CEA Insertion Limits 3/4.2.1          Linear Heat Rate                                                           -
3/4.2.3          Total Integrated Radial Peaking Factor - F[
3/4.2.6          DNB Margin b.
The analytical methods used to determine the ccre operating limits shall be those previously reviewed and approved by the NRC, specifically those described w
in the following documents:
b
: 1)    XN-75-27(A),     atest Revision        and Supplements,/ " Exxon Nuclear Neut onics De         Me   hods                  for Pressuri d Water #..
Reactors,"    xon Nucle @r Coa 0   .
: 2)    XN.NF 3(P), latest ne ision and Supplem nts, " Exxon Nuclear Methodology fo         Pressurized Wa r Reactors:
1 Analys s of Chapter 15 Ev nts,"      Exxon Nucle                             Company.
: 3)    XN-H 21(A),      late t    Revision                      ad                    Supplements,
                        " Application of Exxo9 Nuclear Company P R Thermal Margin                                                 .
He~thodology to Mixed Core Configurations," Exxon Nuclear Company.
4 MILLSTONE - UNIT 2                         6-18     ' Amendment Hos. E, sJ, Jpf, JJJ, Cenh JH,JH,JH,119.
m, m, n),                          l
                                                                                                                                        \
j

ADMINISTRATIVE CONTROLS                                                 2 3 1993                  !
CORE OPERATING LIMITS REPORT (Con't.)
( 4)   XN-84-93(   , latest Revision and Supplements          "Steamline Break Me odology for PWR's,      xxon Nuclear Com any.
: 5) XN 2(A), Supplements     ,   2, 3, and 4      " Computational Proce ure for Evaluation od Bow," Exxon N lear Company.
l
: 6) XN- F-82-49(A),   lates Revision, "Exx n Nuclear Company Ev luation Model EXEM WR Small Break odel," Exxon Nuclear Company.
                                                                                                             /
(
h J w'
                                                                           )
I?cpk won            5nsek R
(
1 l
I V   1
                     'gSTONE-UNIT 2                          6-18a         Amendment.Nos. JE, JJ, JE/, JJJ,          l JJ5, 111, 179, JJ7, Jff,Jf)

                                                                                                                                                                                 \
ADMINISTRATIVE CONTROLS                                                                                                     August 28, 1992 CORE OPERATING t1MITS REPORT fCONT.1
                                      .--             x-
                                                                                                                           -. -- s          m-m                        m      M
: 7)    EXEM PWRA.arge Brea LOCA Evaluation Model as defined by:
XN-NF-82-20(A),                                                     atest Revision and Supplements.
Nuclear Compan                                                       Evaluation Model EXEM/PWR ECCS *Mode Updates,* Exxon                                                              [ Nuclear Company. Exxoh
                                                                                                                                               /
                                                                                                           /               /                  !                      /
i XN-NF-82-07(A), latest Rey,ision, " Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exx'on Nuclear Compa y.
SO                                         XN-NF-81-8(A),
t, , se rr M                                                                                                   latest Revision,                      Fuel / Rod Thermal- echanical Response Evaluation                                                          / RODEX2 Model,"  Exxon Nuclear Company."
                                                                                                                                                              /
XN-NFf85-16(A), Volume 1 and Supp1                                                            nts, Volume 2 3atest Revision and Supplements, "PWR 17x17 Fuel Cooling Test Pro / ram," Exxon Nuclear Company.
X/-NF-85-305(A) and Supplements " Scaling of FCTf Based Reflood He.t Traysfer Correlation or Other Bundle D& signs,"
                                           / Exxon Nuclear Company.
I                                          /
: 8)    XN-NF-78-44(A),/ latest Revisin'n, " Generic                                                                                 d      \
Ejection Analysis," Exxon Nuclear Company.
Colrol     Rod
                                                                                                                                                                                 )
: 9)    XN-NF-621(A),/ latest Revisio C                                                                                     *XNB Critical / Heat Flux
                                                                                                                                                 ~n-V' The    acceptable Mi 1 stone analyticf1 methodol)ogies arr[. 2 - specific ,applicatipa-                                                       of # ese describJddn ANFJ- 8426, "MiT1 stone Unit-2 CycleA0
                                                 -                                   Safety 1Gialysis Refort," datfd October,1988.
c.
The    core operating applicable    limits                                                      limits shall be determined so that all (e.g., fuel thermal-mechanical limits, thennal-hydraulic limits, ECCS limits, nuclear limits suchcore                                                            as shutdown     margin, the safety analysis are Let.                                          and  transient  and  accident      analysis  limits) of
: d. The CORE OPERATING                                                       LIMITS REPORT,      including any mid-cycle                    ~
revisions or supplements therete,                                                           shall be provided upon
* issuance, for each reload cycle, to the NRC Document Control Desk                                                                         ,
with copies to the Regional Administrator and Resident Inspector.                                                                         j i
                     }7 '% REPORTS S o, Special reports shall be submitted to the U.S.
Commission, Document Control Desk, Washington, D.C. Nuclear                                                      20555, oneRegulatory copy l
l to the Regional Administrator, Region 1, and one copy to the NRC Resident Inspector within the time period specified for each report.
These reports shall be submitted covering the activities identified below    pursuant to the requirements of the applicable reference specification:
a.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
ggSTONE-UNIT 2                                                                          6-19 AmendmentNo.JfE///

Insert A - Paaes 6-18. 6-18a. and 6-19
: 1)   XN-75-27(A) and Supplements 1 through 5, " Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Report and Supplement 1 dated April 1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P).
: 2)   ANF-84-73 Revision 5 Appendix B (P)(A)," Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.
: 3)   XN-NF-82-21(P)(A) Revision 1, " Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.
: 4)   EMF-84-93(P) Revision 1, "Steamline Break Methodology for PWRs," Siemens Power Corporation, June 1998.
{
: 5)   XN-75-32(P)(A) Supplements 1 through 4          " Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.
: 6)   XN-NF-82-49(P)(A) Revision 1, " EXXON Nuclear Company Evaluation Model EXEM PWR Small Break Model," Advanced Nuclear Fuels Corporation, April 1989.
I
: 7)   XN-NF-82-49(P)(A) Revision 1 Supplement 1, " Exxon Nuclear Company            ]
Evaluation Model Revised EXEM PWR Small Break Model," Siemens Power           l Corporation, December 1994.
: 8)   EXEM PWR Large Break LOCA Evaluation Model as defined by:
             . XN-NF-82-20(P)(A) Revision 1 Supplement 2, " Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, February 1985.
l
             . XN-NF-82-20(P)(A) Revision 1 and Supplements 1,3 and 4, " Exxon Nuclear l                  Company Evaluation Model EXEM/PWR ECCS Model Updates," Advanced Nuclear Fuels Corporation January 1990.
             . XN-NF-82-07(P)(A) Revision 1, " Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, November 1982.
I L___--_

                                                                -------------------------------m
                            . XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
                            . ANF-81-58(P)(A) Revision 2 Supplements 3 and 4, "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," Advanced Nuclear Fuels Corporation, June 1990.
XN-NF-85-16(P)(A) Volume 1 and Supplements 1, 2 and 3; Volume 2, Revision 1 and Supplement 1, "PWR 17x17 Fuel Cooling Test Program,"
Advanced Nuclear Fuels Corporation, February 1990.
                            . XN-NF-85-105(P)(A) and Supplement 1, " Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Advanced Nuclear Fuels Corporation, January 1990.
: 9)  XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized water reactors," Exxon Nuclear Company, October 1983.
: 10) XN-NF-621(P)(A) Revision 1, " Exxon Nuclear DNB Correlation for })WR Fuel Designs," Exxon Nuclear Company, September 1983.
: 11) XN-NF-82-06(P)(A) Revision 1 and Supplements 2, 4 and 5, ". Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.
: 12) ANF-88-133(P)(A) and Supplement 1, " Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.
: 13) XN-NF-85-92(P)(A), " Exxon Nuclear Uranium Dioxide /Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1988.                                                                  ,
: 14) ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.
l l
: 15) XN-NF-507(P)(A) Supplements 1 and 2, " ENC Setpoint Methodology for C.E.
Reactors: Statistical Setpoint Methodology," Exxon Nuclear Company, September 1986.                                                       .

Docket No. 50-336 B17385 Attachment 4 Millstone Nuclear Power Station, Unit No. 2 Change to Technical Specifications Updating List of Documents Describing the Analytical Methods Specified in Technical Specification 6.9.1.8b Retyped Pages t
l.
August 1998

ADMINISTRATIVE CON 1ROLS
: d. Documentation of all failures (inability to lift or reclose within the tolerances allowed by the design basis) and challenges to the pressurizer PORVs or safety valves.
ANNUAL RADI0 ACTIVE EFFLUENT REPORT 6.9.1.6   A routine Annual Radioactive Effluent Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year.
The report shall include that information delineated in the REM 0DCM.
Any changes to the REM 0DCM shall                                            be submitted                                    in the Annual Radioactive Effluent Report.
MONTHLY OPERATING REPORT 6.9.1.7   Routine reports of operating statistics and shutdown experience shall be     submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following the calendir month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.8   a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.
3/4.1.1.1                   SHUTDOWN MARGIN - T                          > 200*F 3/4.1.1.2                   SHUTDOWN MARGIN - T
* s 200*F 3/4.1.1.4                   ModeratorTemperatuPJCoefficient 3/4.1.3.6                   Regulating CEA Insertion Limits 3/4.2.1                     Linear Heat Rate 3/4.2.3                     Total Integrated Radial Peaking Factor - F[
3/4.2.6                     DNB Margin
: b. The                analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
: 1)                XN-75-27(A) and Supplements 1 through 5, " Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors,"                                                            !
l Exxon Nuclear Company, Report and Supplement 1 dated April 1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987 (P).
l                                2)                ANF-84-73 Revision 5 Appendix B (P)(A), " Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.                                                           .
MILLSTONE - UNIT 2                                          6-18                      Amendment Nos. 77, 77 J/J, JJ/,
0407                                                                                                                                JJ#, //7. 177,      I 117, 199, 191 199,   l l
l l
l
______________                                                                                                                                                         i

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (CONT.)
: 3)  XN-NF-82-21(P)(A) Revision 1, " Application of Exxon Nuclear Company    PWR Thermal    Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.
: 4)  EMF-84-93(P) Revision 1, "Steamline Break Methodology for PT ," Siemens Power Corporation, June 1998.
: 5)  XN-75-32(P)(A)    Supplements   1    through              4,                    " Computational Prcredure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.
: 6)  XN-NF-82-49(P)(A)     Revision    1,    " EXXON                       Nuclear                                               Company Evaluation Model EXEM PWR Small Break Medel," Advanced Nuclear Fuels Corporation, April 1989.
: 7)  XN-NF-82-49(P)(A) Revision 1 Supplement 1, " Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model,"                                                                         l Siemens Power Corporation, December 1994.                                                                                             {
I
: 8)  EXEM PWR Large Break LOCA Evaluation Model as defined by:
XN-NF-82-20(P)(A) Revision 1 Supplement 2, " Exxon                                                                              ,
Nuclear Company Evaluation Model EXEM/PWR ECCS Model                                                                            !
Updates," Exxon Nuclear Company, February 1985.
                    . XN-NF-87-20(P)(A) Revision 1 and Supplement 1, 3, and 4,
                          " Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model   Updates," Advanced Nuclear Fuels Corporation January 1990.
XN-NF-82-07(P)(A) Revision 1, " Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, November 1982.
                     . XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
                     . ANF-81-58(P)(A) Revision 2 Supplements 3 and 4, "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model,"
Advanced Nuclear Fuels Corporation, June 1990.
                     . XN-NF-85-16(P)(A) Volume 1 and Supplements 1, 2, and 3; Volume 2, Revision 1 and Supplement 1, "PWR 17 x 17 fuel Cooling    Test    Program,"     Advanced                           Nuclear                                             Fuels   ,
Corporation, February 1990.                                                                                                     i
                     . XN-NF-85-105(P)(A) and Supplement 1, " Scaling of FCTF                                                                          !
Based Reflood Heat Transfer Correlation for Other Bundle Designs," Advanced Nuclear Fuels Corporation, January 1990.
MILLSTONE - UNIT 2                      6-18a      Amendment No. 79, 17 J/9, 1/J.
osos                                                                     lip,119,179, I??, 199, 191 199,

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (CONT.)
: 9)                   XN-NF-78-44(NP)(A), "A Generic ' Analysis of the Control Rod Ejection Transient for Pressurized water reactors," Exxon Nuclear Company, October 1983.
: 10) XN-NF-621(P)(A) Revision 1, " Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.
: 11) XN-NF-82-06(P)(A) Revision 1 and Supplements 2, 4, and 5,
                                        " Qualification of Exxon Nuclear Fuel for Extended Burnup,"
Exxon Nuclear Company, October 1986.
: 12) ANF-88-133(P)(A) and Supplement 1, " Qualification of Advanced Nuclear fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.
: 13) XN-NF-85-92(P)(A), " Exxon Nuclear Uranium Dioxide /Gadolinia Irradiation Examination and Thermal Conductivity Results,"
Exxon Nuclear Company, November 1988.
: 14) ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:                                      Analysis of Non-LOCA Chapter 15 Events,"
Advanced Nuclear Fuels Corporation, May 1992.
: 15) XN-NF-507(P)(A)                                                     Supplements  1   and   2,   " ENC Setpoint Methodology for C.E. Reactors:                                            Statistical Setpoint Methodology," Exxon Nuclear Company, September 1986.
: c. The core operating limits shall be determined so that all applicable                                                    limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
: d. The                        CORE OPERATING LIMITS REPORT,                                   including any mid-cycle revisions or supplements thereto,                                                       shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2           Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Regior. I, and one copy to the NRC Resident Inspector within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
: a.                Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
MIbiONE - UNIT 2                                                                         6-19                Amendment No. Jf7, JJJ, 0407

Docket No. 50-336 B17385 Attachment 5 Millstone Nuclear Power Station, Unit No. 2 Change to Technical Specifications Updating List of Documents Describing the Analytical Methods Specified in Technical Specification 6.9.1.8b
;                                                    List of Regulatory Commitments 1
i i
i
                                                                                                                                                               )
August 1998

U. S. Nuclecr R gulatory Commission B17385/Attachm:nt 5/Paga 1 l
Change to Technical Specifications Updating List of Documents Describing the Analytical Methods Specified in Technical Specification 6.9.1.8b List of Regulatory Commitments l
The following table identifies those actions committed to by NNECO in this document.
Please notify the Manager - Regulatory Compliance at Millstone Unit No. 2 of any I
questions regarding this document, or any associated regulatory commitments.
Commitment                                               Committed Date or Outage NONE                                                         N/A l
1

l Docket No. 50-336 B17385 Attachment 6 Millstone Nuclear Power Station, Unit No. 2 Change to Technical Specifications Updating List of Documents Describing the Analytical Methods Specified in Technical Specification 6.9.1.8b Post-Scram Main Steam Line Break Analysis for Millstone Unit 2 1
                                                                                                                                                                   )
1 August 1998
   - - _ - _  -- _ _ ---     - - - - - _ - - - -           --     - -- -        --   - - - - - - - - - - -                                     _        _        L}}