NRC 2007-0058, Technical Requirements Manual Change Summary
| ML072280364 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/15/2007 |
| From: | Koehl D Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2007-0058 | |
| Download: ML072280364 (7) | |
Text
Committed to Nuclear Excellence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC August 15,2007 NRC 2007-0058 10 CFR 50.71 (e)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Technical Requirements Manual Chanqe Summary In accordance with 10 CFR 50.71(e), Nuclear Management Company, LLC, is submitting changes made to the Point Beach Nuclear Plant Technical Requirements Manual (TRM). contains the TRM change summary from November 20,2001, through December 31,2006.
This letter contains no new com~itments and no revisions to existing commitments.
Dennis L. Koehl
,/
Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
ENCLOSURE 1 TECHNICAL REQUIREMENTS MANUAL CHANGE
SUMMARY
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 Date of Affected Chanae Section Summary 1 1 /20/2001 TRM 4.1 2 Step 5.5 added that fuel oil stability is analyzed only for trending. The same addition was made to Section 7.0, Acceptance Critieria.
TRM 2.1 U1 1 2/21 12001 TRM 2.1 U2 05/01 12002 TRM 3.4.3 04/24/2002 TRM 2.1 U2 04/24/2002 TRM 2.1 U1 05/31 12002 TRM 2.1 U2 0611 712002 TRM 3.7.6 0812 112002 TRM 3.4.3 A note was added to Figure 6 identifying that the figure represents Relaxed Axial Offset Control (RAOC).
A note was added to Figure 6 identifying that the figure represents RAOC.
Action Condition Completion time was changed from "immediately" to "prior to reactor startup."
Required test pressures were changed from greater than normal operating to normal operating based on the ASME Code. The Bases for each test pressure were also changed.
The hot channel factor (HCF) curve was changed to two curves because there are two fuel assembly types being used. Tavg Departure from Nucleate Boiling (DNB) limit value was changed. The changes were for Cycle 26.
The HCF curve was changed to two curves due to two fuel assembly types being used. Tavg DNB limit value was changed.
HCF curves were revised for core burnup.
Technical Requirements Manual (TRM) was rewritten based on vendor program for turbine overspeed protection.
Reactor Coolant System (RCS) operating pressure was increased to 2250 psia.
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Date of Affected Channe Section 0911 2/2002 TRM 3.7.7 09/20/2002 TRM 2.1 U1 1 011 1/2002 TRM 3.7.7 1 011 1/2002 TRM 3.4.1 01 /02/2003 TRM 3.7.7 1 2/20/2002 TRM 4.7 01 /17/2003 TRM 4.9 01 /08/2003 TRM 4.1 1 02/03/2003 TRM 2.1 U1 02/03/2003 TRM 2.1 U2 Clarified Condition C; on low Service Water (SW) pump bay level, containment accident coolers are inoperable rather than SW pumps being inoperable. Added strainer backwash valves to Table 3.7.7-1.
Revised for Cycle 28.
Changed applicability of TRM from all SW pumps being operable to 5 SW pumps being operable.
Condition A temperature limit was changed from 7g°F to 80°F. New Condition D was added with accompanying Table 3.7.7-2.
RCS activity E-bar sampling was revised to be applicable in Mode 1 only to eliminate low flow non-representative samples.
Specific instrument identification number was removed from Condition D Bases.
Section XI ASME Code was replaced with O&M Code. There were associated program content changes.
Added use of, and reference to, Chemistry procedure CAMP 51 0 for secondary water chemistry sampling.
Replaced the performance of manual, periodic sampling with continuous in-line monitoring.
Safety Limit Curve applicability was revised to 1540 MWt as a result of power uprate.
Safety Limit Curve applicability was revised to 1540 MWt as a result of power uprate.
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Date of Affected Change Section Summarv 02/03/2003 TRM 3.3.2 1211 612002 TRM 3.7.6 0 1 /27/2003 TRM 4.1 04/25/2003 TRM 3.4.3 04/02/2003 TRM 4.3 09/05/2003 TRM 4.12 1 0/03/2003 TRM 3.7.7 10/1 612003 TRM 2.1 U2 0 112 112004 TRM 2.1 U2 01 /22/2004 TRM 3.5.1 04/08/2004 TRM 2.1 U1 04/05/2004 TRM 3.7.7 Revision 0 for Leading Edge Flow Meter was issued.
Crossover steam dump requirements were added (with step renumbering) as a result of power uprate.
Typographical error was corrected. A missing Code of Federal Regulations (CFR) number was added.
The document was canceled.
Changed the Chemistry Analytical Methods and Procedures number for performing chloride analysis.
Diesel fuel oil pour point specification was changed to cloud point temperature from a fixed temperature limit.
In Table 3.7.7-1, several service water valve alignments were eliminated as options to compensate for ring header isolation.
Revised for Cycle 27.
HCF Wz constants were changed at several burnup values as a result of vendor recalculation of values.
TSR 3.5.1.3 was added to verify charging pump capability.
HCF, K(z) and W(z) figures were revised.
Condition I and associated Bases were added for a Zurn strainer bypass flow path not isolated.
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Date of Affected Chanqe Section Summary 04/08/2004 TRM 2.1 U2 04/08/2004 TRM 2.1 U1 04/08/2004 TRM 2.1 U1 04/08/2004 TRM 2.1 U1 0411 412004 TRM 2.3 U1 0411 612004 TRM 2.1 U1 0512 1/2004 TRM 3.4.4 06/01 12004 TRM 2.3 06/29/2004 TRM 3.9.3 09/24/2004 TRM 4.3 1 1 /04/2004 TRM 3.3.1 Shutdown rods fully withdrawn position was revised to 228 steps from 225 steps.
Shutdown rods fully withdrawn position was revised to 228 steps from 225 steps.
Issued for Cycle 29.
Refueling boron concentration was reduced from 2400 to 2200 ppm.
The previous Core Operating Limit Report (COLR) was maintained for an additional operating cycle.
Fuel cycle numbers were added to refueling boron concentration values.
The word "series" was removed in the Required Action when the vent from the common header to the pressure relief tank cannot be vented.
The previous Cycle U1 COLR was canceled.
The new TRM established containment closure controls during movement of recently irradiated fuel.
In Section 7.0, a NUREG 0737 acceptance criteria were added for sampling and analysis of plant effluents. Plant Emergency Plan Implementing Procedure references were also added.
All pages/sections were changed to accommodate the relocation of the hydrogen monitors from the Technical Specifications to the TRM.
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Date of Affected Chanqe Section Summary 0211 612005 TRM 3.3.2 03/29/2005 TRM 4.9 04/29/2005 TRM 2.1 U2 0511 512005 TRM 4.5 0511 012005 TRM 3.9.4 0612312005 TRM 3.9.4 0912312005 TRM 3.9.4 1011 212005 TRM 2.1 U1 A sentence was added in the background section to perform a manual calculation of calorimetric power if the Plant Process Computer System is not available.
Various Chemistry CAMP procedure references were added that are used to operate sample analysis equipment to the references and applicable sections in Section 5.1.
Revised for Cycle 28, which includes 0.422V+ fuel.
CFq factor and FNAH limit were added. Refueling boron concentration was changed to 21 00 ppm.
The HCF operating curve and Figure 5 RAOC W (z) were revised.
Cyclic/transient event counting was changed from an annual to a 2-year frequency.
New guidance was provided for reactor vessel head (RVH) lift requirements. The RVH drop weight was confirmed to be 176,000 pounds.
The TLCO and Applicability were changed to reflect updated administrative requirements, including Table 3.9.4-1. The reference section was also updated.
The TLCO and Applicability were changed to reflect the updated administrative requirements for containment closure, water volume available for recirculation and minimum shutdown time. The reference section was also updated.
Reissued for Cycle 30. Figures for HCF (normalized) and W(z) were changed. Shutdown bank fully withdrawn position was revised for Cycle 30. CFq factor formula was changed. Boron concentration was revised.
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Date of Affected Channe Section Summary 08/08/2005 TRM 3.5.1 01 /05/2006 TRM 3.5.1 1211 212005 TRM 3.7.3 02/08/2006 TRM 4.1 7 02/08/2006 TRM 4.2 02/08/2006 TRM 4.15 02/08/2006 TRM 4.6 05/05/2006 TRM 4.1 2 1 0/27/2006 TRM 3.5.1 10/27/2006 TRM 2.1 U2 1 1 /22/2006 TRM 3.7.6 Boric acid tank volumes for concentrations between 3.0 and 4.5 were changed.
Boric acid storage tank volume was revised to be for a 3.5 to 4.0 concentration.
References to instrument uncertainty and acceptable values were added to Applicability and Surveillance Requirement sections.
Department titles were corrected to reflect the current organization chart.
Department titles were corrected to reflect the current organization chart.
Department titles were corrected to reflect the current organization chart.
Department titles were corrected to reflect the current organization chart. In Section 5.3 the surface exam techniques were updated to include magnetic particle andlor dye penetrant inspections associated with extension of RCP flywheel inspections.
License Renewal Aging management programmatic requirements were added. Specific procedure and form references were added.
Boric acid storage tank minimum volumes for all concentrations were changed.
Issued for Cycle 29. CFq factor and FNAH limit were added. Refueling boron concentration was changed to 2300 ppm. The HCF operating curve was changed. RAOC W(z) was revised.
Shutdown banks fully withdrawn at 225 steps.
In TSR 3.7.6.4, the frequency for the functional test of the turbine stop and governor valves, and the integrity test of the turbine stop valves were changed from 92 days to six months.
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