ML021620149
| ML021620149 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/07/2002 |
| From: | Nazar M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-99-002 | |
| Download: ML021620149 (15) | |
Text
NMC__
Committed to Nuclear Excellence Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch MN 55089 June 7, 2002 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Supplement to License Amendment Request dated December 11, 2000 Conversion to Improved Technical Specifications (ITS)
By letter dated, December 11, 2000, Prairie Island submitted a License Amendment Request (LAR) to convert the current Technical Specifications (CTS) using the guidance of NUREG-1431, Revision 1 as amended by NRC and industry Technical Specification Task Force (TSTF) documents. This letter supplements the subject LAR.
The NRC Staff, in telephone calls, has requested changes in the proposed Technical Specifications and additional documentation to comply with the requests for information in Generic Letter (GL) 99-02. Change designator E52 pages make these changes in response to GL 99-02., Page List by RAI Q, provides a cross-reference of change designators and other sources of page changes to the pages that they changed. to this letter contains Revision 15 change pages. Changes to the Revision 15 pages are sidelined in the right margin beside the line(s) which have been revised. Change Pages from Parts A, B, D, F, G or Cross-References are dated 5/29/02. Change Pages from Parts C and E are marked as Revision 15 with a small textbox below the revision sideline which contains "R-1 5".
The Significant Hazards Determinations and Environmental Assessments, as presented in the original December 11, 2000 submittal and as supplemented
- Tr~Tf'T T A Ti 1 A "*T A (-i'IlurNT C
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.lAI 200VILI2VIN June 7, 2002 Page 2 of 2 March 6, 2001, July 3, 2001, August 13, 2001, November 12, 2001, December 12, 2001, January 25, 2002, January 31, 2002, February 14, 2002, February 15, 2002, February 16, 2002, March 6, 2002, April 11, 2002, May 10, 2002 and May 30, 2002, bound the proposed license amendment.
On February 2, 2001, NMC submitted an LAR to provide miscellaneous clarifications of current Technical Specifications (CTS) Table 3.5-2B. By this letter, NMC requests to withdraw, effective upon the date of issuance of the improved Technical Specifications, the proposed LAR dated February 2, 2001 since the ITS will replace the affected CTS requirements.
NMC is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and attachments to the designated State Official.
To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects these statements are not based on my personal knowledge, but on information furnished by other Prairie Island Nuclear Generating Plant (PINGP) and NMC employees, contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
In this letter NMC has not made any new or revised any Nuclear Regulatory Commission commitments. Please address any comments or questions regarding this matter to myself or Mr. Dale Vincent at 1-651-388-1121.
Mano K. Nazar Site Vice Presi ent Prairie Island uclear Generating Plant C:
Regio al Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC James Bernstein, State of Minnesota Attachments:
- 1.
Page List by RAI Q
- 2.
Revision 15 Change Pages
UNITED STATES NUCLEAR REGULATORY COMMISSION NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 SUPPLEMENT TO LICENSE AMENDMENT REQUEST DATED DECEMBER 11, 2000 CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS (ITS)
By letter dated June 7, 2002, Nuclear Management Company, LLC, a Wisconsin corporation, is submitting additional information in support of the License Amendment Request originally submitted December 11, 2000.
This letter contains no restricted or other defense information.
NUCLEAR MANAGEMENT COMPANY, LLC By.
1ý 771 Mano K. Nazar Site Vice Presidenji/
Prairie Island Nuc tar Generating Plant State of County of.
On this
-7 A day of -
z/*-,0
_-gjýý before me a notary public acting in said County, personally apired M-ano K. Nazar, Site Vice President, Prairie Island Nuclear Generating Plant, and b6eing first duly sworn acknowledged that he is authorized to execute this document on behalf of Nuclear Management Company, LLC, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true.
Prairie Island Nuclear Generating Plant to Supplement dated June 7, 2002 to License Amendment Request dated December 11, 2000 Conversion to Improved Technical Specifications (ITS)
Page List by RAI Q
Page List by RAI Q 6/5/2002 RAI Q#
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Prairie Island Nuclear Generating Plant to Supplement dated June 7, 2002 to License Amendment Request dated December 11, 2000 Conversion to Improved Technical Specifications (ITS)
Revision 15 Change Pages
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Section Part
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8 Page 1 of 1 improved Technical Specifications Supplement dated 5/29/02 Revision 15 Change Page List UPDATING INSTFRUCTIONS Page Revision/
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Section Part B
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Page Revision/
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5/29/02 5/29/02 15 15 15 15 15 5/29/02
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of the Control Room Special Ventilation System, Auxiliary Building Special Ventilation System, Shield Building Ventilation System, and the Spent Fuel Pool Special and Inservice Purge Ventilation System each operating cycle (18 months for shared systems).
Demonstrate for the Auxiliary Building Special Ventilation, Shield Building Ventilation, Control Room Special Ventilation, and Spent Fuel Pool Special and Inservice Purge Ventilation Systems that:
- a.
An inplace DOP test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05% (for DOP, particles having a mean diameter of 0.7 microns);
- b.
A halogenated hydrocarbon test of the inplace charcoal adsorber shows a penetration and system bypass < 0.05% (for DOP, particles having a mean diameter of 0.7 microns);
- c.
A laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than; 1) 15% penetration for Auxiliary Special Ventilation System, 2) 15% penetration for Shield Building Ventilation System, 3) 7.5% penetration for the Spent Fuel Pool Special and Inservice Purge System, and 4) 2.5% penetration for the Control Room Special Ventilation System when tested in accordance with ASTM D3803-1989 at a temperature of 30'C and 95% relative humidity (RH); and
- d.
The pressure drop across the combined HEPA filters and the charcoal adsorbers is less than 6 inches of water at the system flowrate +/- 10%.
Prairie Island Units 1 and 2 5.0-23 5/29/02
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Ventilation Filter Testing Program (VFTP)
(continued)
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
5.5.10 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas holdup system, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.
The program shall include:
- a.
The limits for concentrations of oxygen in the waste gas holdup system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria;
- b.
A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than or equal to 78,800 curies of noble gas (considered as dose equivalent Xe-133); and
- c. A surveillance program to ensure that the quantity of radioactivity contained in each of the following tanks shall be limited to 10 curies, excluding tritium and dissolved or entrained noble gases:
Condensate storage tanks Outside temporary tanks The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies Prairie Island Units 1 and 2 5.0-24 5/29/02
TSS.09 Ovorf Ic;; 2 penetration and sy,,stem-r bypass < 0.05%ý (for DOP, particles hiavingj a.ean diameter o. 0.7 microns);
LR5.0-22
- b.
Ahalogenated hyd rocarbjon test of the inpiace charcoal adsorber shows a penetration and sy,,stem lbypass < 0.05%ý (for DOP, particles having a m,,ean diameter of 0.7 m~icrons)
- c.
A laboratýory testý of a sample -of the charcoal adsorber, whE-n obtained as described in Regulatory Guide 1.52, Rev,.ision 2, shows the methyl iodide penetration less than; 1) 15%5 penetration for the Auxiliary Special-Ventilation syste-m, 2) 15%ý penetrat ion for the Shield Building Ventilation System.i
- 3) 7.5%
penetration for the Spent Fuel Pool. Special and Inservice Purge System, and 4) 2.5%6 penetration for the Control R~oom Special Ventilation System) when tested in accordance with ASTM D3803 70% RH with humidit-controls if the humidity controls are R-15 capable of maintaining the humidity of the air entering te charcoal less than or equal to 70t R4 under worst-case design basis conditions); and d,
The pressure drop across the combined HEPqa filters and the charcoal adsorbersa is less than 6 inches of woater a vte saystem flonun rate +/-10%t, The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
5.5n10 Explosive Gas and Storage Tank Radioactivity monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas holdup system, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.
The program shall include:
,a. The limits for concentration of oxygen in the waste gas holdup system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria;
- b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than or equal to 78,800 curies of noble gases (considered as dose equivalent Xe-133); and
- c. A surveillance program to ensure that the quantity of radioactivity contained in each of the following tanks shall be limited to 10 curies, excluding tritium and dissolved or entrained noble gases:
Condensate storage tanks A5.0-06 Outside temporary tanks The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program test survcillancc frequencies.
Markup for PI ITS Part C PI Current TS Page 25 of 41
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) chemistry to inhibit SG tube degradation and low pressure turbine dise stress corroion cracking. The program shall irel ude
- a.
identifi'ation of a sampling schedule for the critical variables and control points for these variables;
- b.
Identification of the preeed"res used to measure the values of the critical variab4-e;
. identifiation of process sampling points, which shall inelude monitoring the discharge of the c ondensate pumps for evidence of condenser in leakage;
- d.
Procedures for the recording and mfanagement of data;
- e.
Procedures defining corrective actions for all off contro point chemistry conditions; and
- f. A oreeedure identifying the authority responsible forth interpretation of the data and the sequence and timing of administrative events, which is required to initiat eorreetive action.
I CL5.0-88 ]
5.5.94-4 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature ([SF) filter ventilation systems the Control Room Special Ventilation System, Auxiliary Building Special Ventilation System, Shield Building Ventilation System, and the Spent Fuel Pool Special and Inservice Purge Ventilation System each operating cycle (18 months for shared systems)at thc frequenciesý specified in
[Regutlator-y Guide 1.and in accordance wit
[Regulatory r
CL5.0-66 I
I 1 R-15 I
I L----------I (conti nued)
Markup for PI ITS Part E WOG STS Rev 1, 04/07/95 5.0-27
Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
Guide 1.52, Revision 2989, an AG
]..
Demonstrate for the Auxiliary Building Special Ventilation, Shield Building Ventilation, Control Room Special Ventilation, and Spent Fuel Pool Special and Inservice Purge Ventilation Systems that:
a. Demonstrate-for each of the [SF s.yst.ms --
a-an inplace DOP test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < f0.051% (for DOP, particles having a mean diameter of 0.7 microns); when tested in a,,,rdance ita [Retu0la tj *G*i*U i
Revision 2, and ASME N,]
thesystem fl.wrate speeified below [+/- 10%]lj.
[SF Ventilation System Frlowrate I
II I
SI I
I 5.5.9 Ventilation Filter Testing Program (VFTP)
(continued)
- b.
Demonstrate for ^aeh of the
[5F syst.ms t-*
atA-n C
,nplae-halogenated hydrocarbon test of the inplace charcoal adsorber shows a penetration and system bypass < {0.051% (for DOP, particles having a mean diameter of 0.7 microns); wfhen testod in accordance
ý rl*,
mo~
1; 1,,.-
o uG e
I.,5 01 with
[Regulatr Gie 12, Revision 2,and ASM[ NS10 1989] at the system floiriate speeifiod below rf.
I *o-I
[Sf Ventilation System T
I LR-15
.5.0-66 ý I]I I R-15,'
L ------- j Fa wr'
- a. e (continued)
Markup for PI ITS Part E WOG STS Rev 1, 04/07/95 5.0-28 I
I"
-4I
Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
'CL5.0-66 C.
Demnstratcfor eaeh of the [SF systms that aA laboratory test of a sample of the charcoal adsorber, when obtained as-described in fRegulatory Guide 1.52, Revision 2+/-, shows the methyl iodide penetration less than; 1) 15% penetration for Auxiliary Special Ventilation System, 2) 15% penetration for Shield Building Ventilation System, 3) 7.5% penetration for the Spent Fudel Pool Special and Inservice Purge System, and 4) 2.5%
penetration for the Control Room Special Ventilation Systelmtkhe-----------
value specified belo-WE when tested in accordance with R15 fASTM D3803-19891 at a temperature of
_--E30°C land 95,-g-re+er15 than or equal to the relative humidity (RH); and*s-pe-i-f-ied below.
ESF eniain ytmrentrati on R11 Re;view'er'- s Note:
Al owabl e p.netrati an
.- r] l met iodide effiiency:11,'1 fýor ehareoal eredited in-s-taff sact evaluation*!/
(safety-**
f*r.
Safety fator r
[5] for systems wit eaters.
[7]
for s
"without heater"s.""
- d.
Demolnstrate fo eah o h
[F sses thahe pressure drop across the combined HEPA filtersT the.
lt' r-and the charcoal adsorbers is less than 6 inches of
[CL5.0-66 water at the val ecifled beo when t in ae.--.--n,,
with
[R.gulatory Guide 1.52, 5.5.11 Ventilat.^n Filter T.-e tr*
I-IFision 2j and ASM[ F11 1980]
at the system flowrate sp..'if'^d belo....[- 109J.
ESF Venti-laIon System Delta P Fowrat-e (conti nued)
Markup for PI ITS Part E WOG STS Rev 1, 04/07/95 5.0-29
Programs and Manuals 5.5 5.5 Programs and Manuals (continued)
SI I
I I
II I
I I
--- r --
e -. 4Demonstrate that the heaters for eaeh of the [SF systcmsl
.1 I,
LI IL 4
,t.
1..
1: 1-,
O
¥11
,11,**
%isiat the valuc p
fe d 5o
[V 10:%]
he n t e st ed in a.c.rdan4ce it.
[ASME N510 1989].
[SF Ventilation System ftag
+
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
5.5.10-Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas holdup system-IWeste---a CL5.0-56 Holdup, Sys em]-, fthe quantity of radioactivity contained in gas storage tanks or fed into the e,,gas treatment syst,, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanksl. The gaseous radioactivity quantities shall Waste Gas System Leak or Failureq].
The liquid radwastc quantities shall be detcrmincd-in accordance with [Standard Review Planl Section 15.7.3, "Postulated Radioactive Release due to Tan-k Fail'u' e" ].
+
+
(conti nued)
WOG STS Rev 1, 04/07/95 Markup for PI ITS Part E I--
-r--
+
+
5.0-30
Part F Pca Difference Difference Category Number 5.0-CL Justification for Differences 88 ISTS 5.5.11 (ITS 5.5.9) was revised to include the Control Room Special Ventilation System, Auxiliary Building Special Ventilation System, Shield Building Ventilation System, and the Spent Fuel Pool Special and Inservice Purge Ventilation Systems in the Ventilation Filter Testing Program (VFTP). These Systems are credited in the PI USAR accident analysis and will be tested in accordance with the guidance of Regulatory Guide 1.52, Rev. 2 and ASTM D3803 - 1989. The testing conditions for these ventilation systems is 95% Relative Humidity (RH) at 30 °C. Based on the System efficiencies described in the USAR, the following penetration efficiencies have been calculated and listed in the ITS: Control Room Ventilation System < 2.5%, Auxiliary Building Special Ventilation System < 15%, Spent Fuel Pool Special and Inservice Purge System < 7.5% and Shield Building Ventilation System < 15%.
Prairie Island Units I and 2 5/29/02 Package 5.0 Part F 8