BSEP 04-0160, Submittal of Technical Specification Bases Change
| ML043520232 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/10/2004 |
| From: | O'Neil E Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 04-0160 | |
| Download: ML043520232 (34) | |
Text
Progress Energy DEC 10 2004 SERIAL: BSEP 04-0160 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Submittal of Technical Specification Bases Change Ladies and Gentlemen:
In accordance with Technical Specification (TS) 5.5.10 for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., is submitting Revision 38 to the BSEP, Unit 1 TS Bases and Revision 35 to the BSEP, Unit 2 TS Bases.
Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -
Licensing/Regulatory Programs, at (910) 457-2073.
Sincerely, Edward T. O'Neil Manager - Support Services Brunswick Steam Electric Plant WRM/wrm
Enclosures:
- 1. Summary of Revisions to Technical Specification Bases
- 2. Page Replacement Instructions
- 3. Unit 1 Technical Specification Bases Replacement Pages
- 4. Unit 2 Technical Specification Bases Replacement Pages Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southpon., NC 28461
Document Control Desk BSEP 04-0160 / Page 2 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region H ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 10 Ms. Beverly 0. Hall, Section Chief Radiation Protection Section, Division of Environmental Health North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221
-_ _ Summary of Revisions to Technical Specification Bases Revision l Afected l DateImplemeted Title/Description
_ 1 U nit
__e m
38 1
December 1, 2004
Title:
Implementation of the Boiling Water 35 2
Reactor Vessel and Internals Project (BWRVIP) Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50 (TSC-2003-01)
==
Description:==
Revision 38 and 35 revise Technical Specification (TS) Bases 3.4.9 to reflect implementation of the reactor pressure vessel integrated surveillance program (ISP) developed by the BWRVIP. NRC approval for the Brunswick Plant to adopt the ISP was issued on January 14, 2004, as Amendments 229 and 257 to the facility operating licenses for Unit 1 and Unit 2, respectively.
Title:
Clarification of Surveillance Requirement 3.8.1.10 Purpose (TSB-2004-07)
==
Description:==
Revisions 38 and 35 incorporate a clarification to the description of the purpose for Surveillance Requirement 3.8.1.10.
Title:
Administrative Correction to the List of Effective Pages (LOEP)
==
Description:==
Revision 35 for Unit 2 also includes a correction to the LOEP to remove pages B 3.3.1.3-1 through B 3.3.1.3-9. The actual Bases pages were removed as part of Bases Revision 27, which was submitted by letter dated March 28, 2003 (i.e., Serial:
BSEP 03-0054); however, the LOEP was not accurately updated at that time.
BSEP 04-0160 Page 1 of 2 Page Replacement Instructions Remove Insert Unit 1 -Bases Book 1 Cover Page, Revision 37 Cover Page, Revision 38 LOEP-1, Revision 37 LOEP-1, Revision 38 Unit 1 - Bases Book 2 LOEP-1, Revision 36 LOEP-1, Revision 38 LOEP-3, Revision 36 LOEP-3, Revision 38 B 3.4.9-2, Revision 31 B 3.4.9-2, Revision 38 B 3.4.9-3, Revision 31 B 3.4.9-3, Revision 38 B 3.4.9-5, Revision 31 B 3.4.9-5, Revision 38 B 3.4.9-6, Revision 31 B 3.4.9-6, Revision 38 B 3.4.9-9, Revision 36 B 3.4.9-9, Revision 38 B 3.8.1-28, Revision 31 B 3.8.1-28, Revision 38
BSEP 04-0160 Page 2 of 2 Page Replacement Instructions Remove Insert Unit 2 - Bases Book 1 Cover Page, Revision 34 Cover Page, Revision 35 LOEP-1, Revision 34 LOEP-1, Revision 35 LOEP-2 Revision 33 LOEP-2 Revision 35 LOEP-3 Revision 33 LOEP-3 Revision 35 LOEP-4 Revision 33 LOEP-4 Revision 35 Unit 2 - Bases Book 2 LOEP-1, Revision 33 LOEP-1, Revision 35 LOEP-3, Revision 33 LOEP-3, Revision 35 B 3.4.9-2, Revision 30 B 3.4.9-2, Revision 35 B 3.4.9-3, Revision 30 B 3.4.9-3, Revision 35 B 3.4.9-5, Revision 30 B 3.4.9-5, Revision 35 B 3.4.9-6, Revision 30 B 3.4.9-6, Revision 35 B 3.4.9-9, Revision 33 B 3.4.9-9, Revision 35 B 3.8.1-28, Revision 30 B 3.8.1-28, Revision 35
BSEP 04-0160 Unit 1 Technical Specification Bases Replacement Pages
Unit 1 - Bases Book 1 Replacement Pages
BASES TO THE FACILITY OPERATING LICENSE DPR-71 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 CAROLINA POWER & LIGHT COMPANY REVISION 38
LIST OF EFFECTIVE PAGES - BASES Page No.
Title Page Revision No.
38 List of Effective Pages - Book 1 LOEP-1 LOEP-2 LOEP-3 LOEP-4 38 36 36 36 ii 31 31 B 2.1.1-1 B 2.1.1-2 B 2.1.1-3 B 2.1.1-4 B 2.1.1-5 B 2.1.2-1 B 2.1.2-2 B 2.1.2-3 B 3.0-1 B 3.0-2 B 3.0-3 B 3.0-4 B 3.0-5 B 3.0-6 B 3.0-7 B 3.0-8 B 3.0-9 B 3.0-1 0 B 3.0-11 B 3.0-12 B 3.0-13 B 3.0-14 B 3.0-15 B 3.0-16 B 3.1.1-1 B 3.1.1-2 B 3.1.1-3 B 3.1.1-4 B 3.1.1-5 B 3.1.1-6 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 Page No.
B 3.1.2-1 B 3.1.2-2 B 3.1.2-3 B 3.1.2-4 B 3.1.2-5 B 3.1.3-1 B 3.1.3-2 B 3.1.3-3 B 3.1.3-4 B 3.1.3-5 B 3.1.3-6 B 3.1.3-7 B 3.1.3-8 B 3.1.3-9 B 3.1.4-1 B 3.1.4-2 B 3.1.4-3 B 3.1.4-4 B 3.1.4-5 B 3.1.4-6 B 3.1.4-7 B 3.1.5-1 B 3.1.5-2 B 3.1.5-3 B 3.1.5-4 B 3.1.5-5 B 3.1.6-1 B 3.1.6-2 B 3.1.6-3 B 3.1.6-4 B 3.1.6-5 B 3.1.7-1 B 3.1.7-2 B 3.1.7-3 B 3.1.7-4 B 3.1.7-5 B 3.1.7-6 B 3.1.8-1 B 3.1.8-2 B 3.1.8-3 B 3.1.8-4 B 3.1.8-5 Revision No.
31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 34 31 31 31 31 34 31 37 37 31 31 I
I (continued)
Brunswick Unit 1 LOEP-1 Revision 38 l
Unit 1 - Bases Book 2 Replacement Pages
LIST OF EFFECTIVE PAGES - BASES Page No.
Revision No.
List of Effective Pages - Book 2 LOEP-1 LOEP-2 LOEP-3 LOEP-4 LOEP-5 38 36 38 31 31 Page No.
B 3.4.7-5 B 3.4.8-1 B 3.4.8-2 B 3.4.8-3 B 3.4.8-4 B 3.4.8-5 B 3.4.9-1 B 3.4.9-2 B 3.4.9-3 B 3.4.9-4 B 3.4.9-5 B 3.4.9-6 B 3.4.9-7 B 3.4.9-8 B 3.4.9-9 B 3.4.1 0-1 B 3.4.10-2 i.Hl Revision No.
31 31 31 31 31 31 31 31 31 38 38 31 38 38 31 31 38 31 31 I
I I
I B 3.4.1-1 B 3.4.1-2 B 3.4.1-3 B 3.4.1-4 B 3.4.1-5 B 3.4.1-6 B 3.4.2-1 B 3.4.2-2 B 3.4.2-3 B 3.4.2-4 B 3.4.3-1 B 3.4.3-2 B 3.4.3-3 B 3.4.3-4 B 3.4.4-1 B 3.4.4-2 B 3.4.4-3 B 3.4.4-4 B 3.4.4-5 B 3.4.5-1 B 3.4.5-2 B 3.4.5-3 B 3.4.5-4 B 3.4.5-5 B 3.4.6-1 B 3.4.6-2 B 3.4.6-3 B 3.4.6-4 B 3.4.7-1 B 3.4.7-2 B 3.4.7-3 B 3.4.7-4 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 I
B 3.5.1-1 B 3.5.1-2 B 3.5.1-3 B 3.5.1-4 B 3.5.1-5 B 3.5.1-6 B 3.5.1-7 B 3.5.1-8 B 3.5.1-9 B 3.5.1 -1 0 B 3.5.1 -11 B 3.5.1-12 B 3.5.1-13 B 3.5.1-14 B 3.5.1-15 B 3.5.1 -16 B 3.5.1-17 B 3.5.2-1 B 3.5.2-2 B 3.5.2-3 B 3.5.2-4 B 3.5.2-5 B 3.5.2-6 B 3.5.3-1 B 3.5.3-2 31 31 31 36 36 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 (continued)
Brunswick Unit 1 LOEP-1 Revision 38 l
LIST OF EFFECTIVE PAGES - BASES (continued)
Page No.
B 3.6.4.3-4 B 3.6.4.3-5 B 3.6.4.3-6 Revision No.
Page No.
31 31 31 B 3.7.7-1 B 3.7.7-2 B 3.7.7-3 Revision No.
31 31 31 B 3.7.1-1 B 3.7.1-2 B 3.7.1-3 B 3.7.1-4 B 3.7.1-5 B 3.7.1-6 B 3.7.2-1 B 3.7.2-2 B 3.7.2-3 B 3.7.2-4 B 3.7.2-5 B 3.7.2-6 B 3.7.2-7 B 3.7.2-8 B 3.7.2-9 B 3.7.2-10 B 3.7.2-11 B 3.7.2-12 B 3.7.2-13 B 3.7.2-14 B 3.7.3-1 B 3.7.3-2 B 3.7.3-3 B 3.7.3-4 B 3.7.3-5 B 3.7.3-6 B 3.7.3-7 B 3.7.4-1 B 3.7.4-2 B 3.7.4-3 B 3.7.4-4 B 3.7.4-5 B 3.7.5-1 B 3.7.5-2 B 3.7.5-3 B 3.7.6-1 B 3.7.6-2 B 3.7.6-3 B 3.7.6-4 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 36 31 31 31 31 36 31 31 31 31 31 31 31 31 31 31 31 31 B 3.8.1-1 B 3.8.1-2 B 3.8.1-3 B 3.8.1-4 B 3.8.1-5 B 3.8.1-6 B 3.8.1-7 B 3.8.1-8 B 3.8.1-9 B 3.8.1 -10 B 3.8.1 -11 B 3.8.1-12 B 3.8.1-13 B 3.8.1-14 B 3.8.1-15 B 3.8.1-16 B 3.8.1-17 B 3.8.1 -18 B 3.8.1 -19 B 3.8.1-20 B 3.8.1-21 B 3.8.1-22 B 3.8.1-23 B 3.8.1-24 B 3.8.1-25 B 3.8.1-26 B 3.8.1-27 B 3.8.1-28 B 3.8.1-29 B 3.8.1-30 B 3.8.1-31 B 3.8.1-32 B 3.8.1-33 B 3.8.1-34 B 3.8.2-1 B 3.8.2-2 B 3.8.2-3 B 3.8.2-4 B 3.8.2-5 31 31 36 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 38 31 31 31 31 36 31 31 31 31 31 31 i
i I
I j
i i
(continued)
Brunswick Unit 1 LOEP-3 Revision 38 l
RCS P/T Limits B 3.4.9 BASES BACKGROUND Kic for development of P/T limit curves has been approved by the ASME (continued) through Code Case N-640 (Ref. 4).
The actual shift in the RTNDT of the vessel plate and weld materials will be established periodically by removing and evaluating representative irradiated reactor specimens from selected reactors in accordance with BWRVIP-86A (Reference 5) and Appendix H of 10 CFR 50 (Reference 6).
For BNP, the limiting reactor vessel material with respect to P/T curves is the N16 nozzle material. The shift in the RTNDTOf this material has been established in accordance with Regulatory Guide 1.99, Revision 2 (RG 1.99) (Reference 7).
In development of the P/T curves (Reference 8), it is assumed that the 1/4t (ID) flaw with a cooldown is controlling based on the following:
- 1.
Due to attenuation effects, the fluence is significantly higher at the 1/4t location compared to the 3/4t location. Therefore, the ARTNDT is significantly higher at the 1/4t location.
- 2.
The thermal tensile stress due to a 1 000F/hr heatup (for a 3/4t flaw) is about the same as the thermal tensile stress due to a 1 000F/hr cooldown (for a 1/4t flaw).
- 3.
The allowable material property (i.e., KIA or Kic) is lower at the end of a cooldown transient where thermal stresses are a maximum compared to the end of the heatup transient.
- 4.
For the reactor pressure vessel (RPV) (i.e., a thin cylinder), the pressure stress is essentially constant through the wall, so the 1/4t and 3/4t pressure stresses are not significantly different.
The criticality limits include the Reference 2 requirement that they be at least 400F above the noncritical heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.
The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.
ASME Code,Section XI, Appendix E (Ref. 9), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.
(continued)
Brunswick Unit I B 3.4.9-2 Revision No. 38 l
RCS P/T Limits B 3.4.9 BASES (continued)
APPLICABLE SAFETY ANALYSES The P/T limits are not derived from Design Basis Accident (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed.
Reference 8 provides the curves and limits in this Specification. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the PIT limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.
RCS P/T limits satisfy Criterion 2 of 10 CFR 50.36(c)(2)(ii) (Ref. 10).
LCO The elements of this LCO are:
- a.
RCS pressure and temperature are within the applicable limits specified in Figures 3.4.9-1 and 3.4.9-2, and heatup or cooldown rates are S 1000F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS heatup and cooldown;
- b.
RCS pressure and temperature are within the applicable limits in Figures 3.4.9-3, 3.4.9-4, or 3.4.9-5 and heatup or cooldown rates are
- 300F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS inservice leak and hydrostatic testing;
- c.
The temperature difference between the reactor vessel bottom head coolant and the RPV coolant is
- 1450F during recirculation pump startup;
- d.
The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is
- 500F during recirculation pump startup;
- e.
RCS pressure and temperature are within the criticality limits specified in Figure 3.4.9-2, prior to achieving criticality; and
- f.
The reactor vessel flange and the head flange temperatures are 2 700F when tensioning the reactor vessel head bolting studs.
(continued)
I Brunswick Unit 1 B 3.4.9-3 Revision No. 38 l
RCS PIT Limits B 3.4.9 BASES ACTIONS A.1 and A.2 (continued)
Besides restoring operation within acceptable limits, an engineering evaluation is required to determine if RCS operation can continue. This engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. The evaluation must verify the RCPB integrity remains acceptable and must be completed if continued operation is desired. Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.
ASME Code, Section Xl, Appendix E (Ref. 9), may be used to support the l evaluation. However, its use is restricted to evaluation of the vessel beltline.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to accomplish the evaluation of a mild violation. More severe violations may require special, event specific stress analyses or inspections. A favorable evaluation must be completed if continued operation is desired.
Condition A is modified by a Note requiring Required Action A.2 be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action A.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
B.1 and B.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the RCS remained in an unacceptable P/T region for an extended period of increased stress, or a sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the RCS at reduced pressure and temperature. With the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.
(continued)
Brunswick Unit 1 B 3.4.9-5 Revision No. 38 l
RCS P/T Limits B 3.4.9 BASES ACTIONS B.1 and B.2 (continued)
Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified as safe by stress analyses.
The Required Action must be initiated without delay and continued until the limits are restored. With the applicable limits of Figure 3.4.9-3, 3.4.9-4, or 3.4.9-5 exceeded during inservice hydrostatic and leak testing operations, the maximum temperature change shall be limited to 1 0F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during restoration of the P/T limit parameters to within limits.
Besides restoring the P/T limit parameters to within limits, an engineering evaluation is required to determine if RCS operation is allowed. This engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to > 212 0F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code, Section Xl, Appendix E (Ref. 9), may be used to support the evaluation; however, its use is l
restricted to evaluation of the beltline.
Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
(continued)
Brunswick Unit 1 B 3.4.9-6 Revision No. 38 l
RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.6. SR 3.4.9.7. and SR 3.4.9.8 (continued)
REQUIREMENTS The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.
SR 3.4.9.6 is modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs.
SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated 30 minutes after RCS temperature is
- 800F in MODE 4.
SR 3.4.9.8 is modified by a Note that requires the Surveillance to be initiated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature is
- 1000F in MODE 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the specified limits.
REFERENCES
- 1.
Calculation 0B21-1029, "Instrument Uncertainty for RCS Pressure/Temperature Limits Curve,' Revision 0.
- 2.
- 3.
1989 Edition of the ASME Code, Section Xl, Appendix G.
- 4.
ASME Code Case N-640. "Altemate References Fracture Toughness for Development of P-T Limit Curves Section Xl.
Division 1."
- 5.
EPRI Report TR-1003346, BWRVIP-86-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, October 2002.
- 6.
- 7.
Regulatory Guide 1.99, Revision 2, May 1988.
- 8.
Calculation OB1 1-0005, "Development of RPV Pressure-Temperature Curves For BNP Units 1 and 2 For Up To 32 EFPY of Plant Operation," Revision 1.
- 9.
ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.
- 10.
Brunswick Unit 1 B 3.4.9-9 Revision No. 38 l
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.10 Consistent with Regulatory Guide 1.9 (Ref. 11), paragraph C.2.2.12, this Surveillance demonstrates that DG non-critical protective functions (e.g.,
high jacket water temperature) are bypassed on an ECCS initiation test signal. The non-critical trips are bypassed during DBAs and provide an alarm on an abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. The DG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not immediately detrimental to emergency operation of the DG.
I The 24 month Frequency is based on engineering judgment, takes into consideration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. Operating experience has demonstrated that these components will pass the SR when performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
The SR is modified by a Note. To minimize testing of the DGs, the Note allows a single test (instead of two tests, one for each unit) to satisfy the requirements for both units. This is allowed since the main purpose of the Surveillance can be met by performing the test on either unit. If the DG fails one of these Surveillances, the DG should be considered inoperable on both units, unless the cause of the failure can be directly related to only one unit.
SR 3.8.1.11 Brunswick Nuclear Plant performs a 60 minute run greater than or equal to the continuous rating (3500 kW) which bounds the maximum expected post-accident DG loading. The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for (continued)
Brunswick Unit 1 B 3.8.1-28 Revision No. 38 l
BSEP 04-0160 Unit 2 Technical Specification Bases Replacement Pages
Unit 2 - Bases Book 1 Replacement Pages
BASES TO THE FACILITY OPERATING LICENSE DPR-62 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 CAROLINA POWER & LIGHT COMPANY REVISION 35
LIST OF EFFECTIVE PAGES - BASES Page No.
Revision No.
Title Page 35 List of Effective Pages - Book 1 LOEP-1 35 LOEP-2 35 LOEP-3 35 LOEP-4 35 i
30 ii 30 B 2.1.1-1 30 B 2.1.1-2 30 B 2.1.1-3 30 B 2.1.1-4 30 B 2.1.1-5 30 B 2.1.2-1 30 B 2.1.2-2 30 B 2.1.2-3 30 B 3.0-1 30 B 3.0-2 30 B 3.0-3 30 B 3.0-4 30 B 3.0-5 30 B 3.0-6 30 B 3.0-7 30 B 3.0-8 30 B 3.0-9 30 B 3.0-10 30 B 3.0-11 30 B 3.0-12 30 B 3.0-13 30 B 3.0-14 30 B 3.0-15 30 B 3.0-16 30 B 3.1.1-1 30 B 3.1.1-2 30 B 3.1.1-3 30 B 3.1.1-4 30 B 3.1.1-5 30 B 3.1.1-6 30 Page No.
B 3.1.2-1 B 3.1.2-2 B 3.1.2-3 B 3.1.2-4 B 3.1.2-5 B 3.1.3-1 B 3.1.3-2 B 3.1.3-3 B 3.1.3-4 B 3.1.3-5 B 3.1.3-6 B 3.1.3-7 B 3.1.3-8 B 3.1.3-9 B 3.1.4-1 B 3.1.4-2 B 3.1.4-3 B 3.1.4-4 B 3.1.4-5 B 3.1.4-6 B 3.1.4-7 B 3.1.5-1 B 3.1.5-2 B 3.1.5-3 B 3.1.5-4 B 3.1.5-5 B 3.1.6-1 B 3.1.6-2 B 3.1.6-3 B 3.1.6-4 B 3.1.6-5 B 3.1.7-1 B 3.1.7-2 B 3.1.7-3 B 3.1.7-4 B 3.1.7-5 B 3.1.7-6 B 3.1.8-1 B 3.1.8-2 B 3.1.8-3 B 3.1.8-4 B 3.1.8-5 Revision No.
30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 34 34 30 30 I
(continued)
Brunswick Unit 2 LOEP-1 Revision 35 l
LIST OF EFFECTIVE PAGES - BASES (continued)
Page No.
Revision No.
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B 3.2.1-1 B 3.2.1-2 B 3.2.1-3 B 3.2.1-4 B 3.2.1-5 B 3.2.2-1 B 3.2.2-2 B 3.2.2-3 B 3.2.2-4 B 3.2.2-5 B 3.3.1.1-1 B 3.3.1.1-2 B 3.3.1.1-3 B 3.3.1.1-4 B 3.3.1.1-5 B 3.3.1.1-6 B 3.3.1.1-7 B 3.3.1.1-8 B 3.3.1.1-9 B 3.3.1.1-10 B 3.3.1.1-11 B 3.3.1.1-12 B 3.3.1.1-13 B 3.3.1.1-14 B 3.3.1.1-15 B 3.3.1.1-16 B 3.3.1.1-17 B 3.3.1.1-18 B 3.3.1.1-19 B 3.3.1.1-20 B 3.3.1.1-21 B 3.3.1.1-22 B 3.3.1.1-23 B 3.3.1.1-24 B 3.3.1.1-25 B 3.3.1.1-26 B 3.3.1.1-27 B 3.3.1.1-28 B 3.3.1.1-29 B 3.3.1.1-30 B 3.3.1.1-31 B 3.3.1.1-32 B 3.3.1.1-33 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 B 3.3.1.1-34 B 3.3.1.1-35 B 3.3.1.1-36 B 3.3.1.1-37 B 3.3.1.1-38 B 3.3.1.1-39 B 3.3.1.1-40 B 3.3.1.1-41 B 3.3.1.1-42 B 3.3.1.1-43 B 3.3.1.2-1 B 3.3.1.2-2 B 3.3.1.2-3 B 3.3.1.2-4 B 3.3.1.2-5 B 3.3.1.2-6 B 3.3.1.2-7 B 3.3.1.2-8 B 3.3.1.2-9 B 3.3.2.1 -1 B 3.3.2.1-2 B 3.3.2.1-3 B 3.3.2.1-4 B 3.3.2.1-5 B 3.3.2.1-6 B 3.3.2.1-7 B 3.3.2.1-8 B 3.3.2.1-9 B 3.3.2.1 -10 B 3.3.2.1-11 B 3.3.2.1-12 B 3.3.2.1-13 B 3.3.2.1 -14 B 3.3.2.1-15 B 3.3.2.2-1 B 3.3.2.2-2 B 3.3.2.2-3 B 3.3.2.2-4 B 3.3.2.2-5 B 3.3.2.2-6 B 3.3.2.2-7 B 3.3.3.1 -1 B 3.3.3.1-2 B 3.3.3.1-3 30 30 30 30 30 30 30 33 33 30 30 30 30 30 30 30 30 30 30 30 30 30 32 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 I
I (continued)
Brunswick Unit 2 LOEP-2 Revision 35 l
LIST OF EFFECTIVE PAGES - BASES (continued)
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B 3.3.3.1-4 B 3.3.3.1-5 B 3.3.3.1-6 B 3.3.3.1-7 B 3.3.3.1-8 B 3.3.3.1-9 B 3.3.3.1-10 B 3.3.3.1-11 B 3.3.3.1-12 B 3.3.3.2-1 B 3.3.3.2-2 B 3.3.3.2-3 B 3.3.3.2-4 B 3.3.3.2-5 B 3.3.3.2-6 B 3.3.4.1-1 B 3.3.4.1-2 B 3.3.4.1-3 B 3.3.4.1-4 B 3.3.4.1-5 B 3.3.4.1-6 B 3.3.4.1-7 B 3.3.4.1-8 B 3.3.4.1-9 B 3.3.5.1-1 B 3.3.5.1-2 B 3.3.5.1-3 B 3.3.5.1-4 B 3.3.5.1-5 B 3.3.5.1-6 B 3.3.5.1-7 B 3.3.5.1-8 B 3.3.5.1-9 B 3.3.5.1-10 B 3.3.5.1-11 B 3.3.5.1-12 B 3.3.5.1-13 B 3.3.5.1-14 B 3.3.5.1-15 B 3.3.5.1 -16 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 33 30 30 30 30 30 30 30 30 33 33 33 33 B 3.3.5.1 -17 B 3.3.5.1-18 B 3.3.5.1 -19 B 3.3.5.1-20 B 3.3.5.1-21 B 3.3.5.1-22 B 3.3.5.1-23 B 3.3.5.1-24 B 3.3.5.1-25 B 3.3.5.1-26 B 3.3.5.1-27 B 3.3.5.1-28 B 3.3.5.1-29 B 3.3.5.1-30 B 3.3.5.1-31 B 3.3.5.2-1 B 3.3.5.2-2 B 3.3.5.2-3 B 3.3.5.2-4 B 3.3.5.2-5 B 3.3.5.2-6 B 3.3.5.2-7 B 3.3.5.2-8 B 3.3.5.2-9 B 3.3.5.2-10 B 3.3.5.2-11 B 3.3.6.1 -1 B 3.3.6.1-2 B 3.3.6.1-3 B 3.3.6.1-4 B 3.3.6.1-5 B 3.3.6.1-6 B 3.3.6.1-7 B 3.3.6.1-8 B 3.3.6.1-9 B 3.3.6.1 -10 B 3.3.6.1 -11 B 3.3.6.1-12 B 3.3.6.1-13 B 3.3.6.1-14 30 33 33 30 30 30 30 30 30 30 30 30 30 30 33 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 31 30 30 30 30 30 30 (continued)
Brunswick Unit 2 LOEP-3 Revision 35 l
LIST OF EFFECTIVE PAGES - BASES (continued)
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B 3.3.6.1-15 B 3.3.6.1 -16 B 3.3.6.1-17 B 3.3.6.1-18 B 3.3.6.1-19 B 3.3.6.1-20 B 3.3.6.1-21 B 3.3.6.1-22 B 3.3.6.1-23 B 3.3.6.1-24 B 3.3.6.1-25 B 3.3.6.1-26 B 3.3.6.1-27 B 3.3.6.1-28 B 3.3.6.1-29 B 3.3.6.1-30 B 3.3.6.1-31 B 3.3.6.1-32 B 3.3.6.2-1 B 3.3.6.2-2 B 3.3.6.2-3 B 3.3.6.2-4 B 3.3.6.2-5 B 3.3.6.2-6 B 3.3.6.2-7 B 3.3.6.2-8 B 3.3.6.2-9 B 3.3.6.2-10 B 3.3.6.2-11 B 3.3.7.1-1 B 3.3.7.1-2 B 3.3.7.1-3 B 3.3.7.1-4 B 3.3.7.1-5 B 3.3.7.1-6 B 3.3.7.1-7 B 3.3.7.2-1 B 3.3.7.2-2 B 3.3.7.2-3 B 3.3.7.2-4 B 3.3.7.2-5 B 3.3.7.2-6 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 33 30 30 30 30 30 30 B 3.3.7.2-7 B 3.3.8.1 -1 B 3.3.8.1-2 B 3.3.8.1-3 B 3.3.8.1-4 B 3.3.8.1-5 B 3.3.8.1-6 B 3.3.8.1-7 B 3.3.8.2-1 B 3.3.8.2-2 B 3.3.8.2-3 B 3.3.8.2-4 B 3.3.8.2-5 B 3.3.8.2-6 B 3.3.8.2-7 30 30 30 30 30 30 30 30 30 30 30 30 30 30 30 Brunswick Unit 2 LOEP-4 Revision 35 l
Unit 2 -Bases Book 2 Replacement Page
LIST OF EFFECTIVE PAGES - BASES Page No.
Revision No.
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Title Page N/A B 3.4.7-4 30 B 3.4.7-5 30 List of Effective Pages - Book 2 B 3.4.8-1 30 B 3.4.8-2 30 LOEP-1 35 B 3.4.8-3 30 LOEP-2 33 B 3.4.8-4 30 LOEP-3 35 B 3.4.8-5 30 LOEP-4 30 B 3.4.9-1 30 LOEP-5 30 B 3.4.9-2 35 B 3.4.9-3 35 i
30 B 3.4.9-4 30 ii 30 B 3.4.9-5 35 B 3.4.9-6 35 B 3.4.1-1 30 B 3.4.9-7 30 B 3.4.1-2 30 B 3.4.9-8 30 B 3.4.1-3 30 B 3.4.9-9 35 B 3.4.1-4 30 B 3.4.10-1 30 B 3.4.1-5 30 B 3.4.10-2 30 B 3.4.1-6 30 B 3.4.2-1 30 B 3.5.1-1 30 B 3.4.2-2 30 B 3.5.1-2 30 B 3.4.2-3 30 B 3.5.1-3 30 B 3.4.2-4 30 B 3.5.1-4 33 B 3.4.3-1 30 B 3.5.1-5 33 B 3.4.3-2 30 B 3.5.1-6 30 B 3.4.3-3 30 B 3.5.1-7 30 B 3.4.3-4 30 B 3.5.1-8 30 B 3.4.4-1 30 B 3.5.1-9 30 B 3.4.4-2 30 B 3.5.1-10 30 B 3.4.4-3 30 B 3.5.1-11 30 B 3.4.4-4 30 B 3.5.1 -12 30 B 3.4.4-5 30 B 3.5.1-13 30 B 3.4.5-1 30 B 3.5.1-14 30 B 3.4.5-2 30 B 3.5.1 -15 30 B 3.4.5-3 30 B 3.5.1-16 30 B 3.4.5-4 30 B 3.5.1 -17 30 B 3.4.5-5 30 B 3.5.2-1 30 B 3.4.6-1 30 B 3.5.2-2 30 B 3.4.6-2 30 B 3.5.2-3 30 B 3.4.6-3 30 B 3.5.2-4 30 B 3.4.6-4 30 B 3.5.2-5 30 B 3.4.7-1 30 B 3.5.2-6 30 B 3.4.7-2 30 B 3.5.3-1 30 B 3.4.7-3 30 B 3.5.3-2 30 (continued)
Brunswick Unit 2 LOEP-1 Revision 35 l
LIST OF EFFECTIVE PAGES - BASES (continued)
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Revisi6n No.
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Revision No.
B 3.6.4.3-4 30 B 3.7.7-1 30 B 3.6.4.3-5 30 B 3.7.7-2 30 B 3.6.4.3-6 30 B 3.7.7-3 30 B 3.7.1-1 30 B 3.8.1-1 30 B 3.7.1-2 30 B 3.8.1-2 30 B 3.7.1-3 30 B 3.8.1-3 33 B 3.7.1-4 30 B 3.8.1-4 30 B 3.7.1-5 30 B 3.8.1-5 30 B 3.7.1-6 30 B 3.8.1-6 30 B 3.7.2-1 30 B 3.8.1-7 30 B 3.7.2-2 30 B 3.8.1-8 30 B 3.7.2-3 30 B 3.8.1-9 30 B 3.7.2-4 30 B 3.8.1 -10 30 B3.7.2-5 30 B3.8.1-11 30 B 3.7.2-6 30 B 3.8.1-12 30 B 3.7.2-7 30 B 3.8.1-13 30 B 3.7.2-8 30 B 3.8.1-14 30 B 3.7.2-9 30 B 3.8.1-15 30 B 3.7.2-10 30 B 3.8.1-16 30 B 3.7.2-11 30 B 3.8.1-17 30 B 3.7.2-12 30 B 3.8.1-18 30 B 3.7.2-13 30 B 3.8.1-19 30 B 3.7.2-14 30 B 3.8.1-20 30 B 3.7.3-1 30 B 3.8.1-21 30 B 3.7.3-2 33 B 3.8.1-22 30 B 3.7.3-3 30 B 3.8.1-23 30 B 3.7.3-4 30 B 3.8.1-24 30 B 3.7.3-5 30 B 3.8.1-25 30 B 3.7.3-6 30 B 3.8.1-26 30 B 3.7.3-7 33 B 3.8.1-27 30 B 3.7.4-1 30 B 3.8.1-28 35 B 3.7.4-2 30 B 3.8.1-29 30 B 3.7.4-3 30 B 3.8.1-30 30 B 3.7.4-4 30 B 3.8.1-31 30 B 3.7.4-5 30 B 3.8.1-32 30 B 3.7.5-1 30 B 3.8.1-33 33 B 3.7.5-2 30 B 3.8.1-34 30 B 3.7.5-3 30 B 3.8.2-1 30 B 3.7.6-1 30 B 3.8.2-2 30 B 3.7.6-2 30 B 3.8.2-3 30 B 3.7.6-3 30 B 3.8.2-4 30 B 3.7.6-4 30 B 3.8.2-5 30 (continued)
Brunswick Unit 2 LOEP-3 Revision 35 l
RCS P/T Limits B 3.4.9 BASES BACKGROUND (continued)
Kic for development of P/T limit curves has been approved by the ASME through Code Case N-640 (Ref. 4).
The actual shift in the RTNDT of the vessel plate and weld materials will be established periodically by removing and evaluating representative irradiated reactor specimens from selected reactors in accordance with BWRVIP-86A (Reference 5) and Appendix H of 10 CFR 50 (Reference 6).
For BNP, the limiting reactor vessel material with respect to P/T curves is the N16 nozzle material. The shift in the RTNDTof this material has been established in accordance with Regulatory Guide 1.99, Revision 2 (RG 1.99) (Reference 7).
In development of the P/T curves (Reference 8), it is assumed that the 1/4t (ID) flaw with a cooldown is controlling based on the following:
- 1.
Due to attenuation effects, the fluence is significantly higher at the 1/4t location compared to the 3/4t location. Therefore, the ARTNDT is significantly higher at the 1/4t location.
- 2.
The thermal tensile stress due to a 1 000F/hr heatup (for a 3/4t flaw) is about the same as the thermal tensile stress due to a 1000F/hrcooldown (for a 1/4t flaw).
- 3.
The allowable material property (i.e., KIA or KIC) is lower at the end of a cooldown transient where thermal stresses are a maximum compared to the end of the heatup transient.
- 4.
For the reactor pressure vessel (reactor pressure vessel ) (i.e., a thin cylinder), the pressure stress is essentially constant through the wall, so the 1/4t and 3/4t pressure stresses are not significantly different.
The criticality limits include the Reference 2 requirement that they be at least 400F above the noncritical heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.
The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident. In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.
ASME Code, Section Xl, Appendix E (Ref. 9), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.
I (continued)
Brunswick Unit 2 B 3.4.9-2 Revision No. 35 l
RCS P/T Limits B 3.4.9 BASES (continued)
APPLICABLE SAFETY ANALYSES The P/T limits are not derived from Design Basis Accident (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed.
Reference 8 provides the curves and limits in this Specification. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.
RCS P/T limits satisfy Criterion 2 of 10 CFR 50.36(c)(2)(ii) (Ref. 10).
LCO The elements of this LCO are:
- a.
RCS pressure and temperature are within the applicable limits specified in Figures 3.4.9-1 and 3.4.9-2, and heatup or cooldown rates are
- 1 00F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS heatup and cooldown;
- b.
RCS pressure and temperature are within the applicable limits in Figure 3.4.9-3, 3.4.9-4, or 3.4.9-5 and heatup or cooldown rates are < 300F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, during RCS inservice leak and hydrostatic testing;
- c.
The temperature difference between the reactor vessel bottom head coolant and the RPV coolant is < 1450F during recirculation pump startup;
- d.
The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is
- 500F during recirculation pump startup;
- e.
RCS pressure and temperature are within the criticality limits specified in Figure 3.4.9-2, prior to achieving criticality; and
- f.
The reactor vessel flange and the head flange temperatures are 2 700F when tensioning the reactor vessel head bolting studs.
(continued)
I Brunswick Unit 2 B 3.4.9-3 Revision No. 35 l
RCS P/T Limits B 3.4.9 BASES ACTIONS A.1 and A.2 (continued)
Besides restoring operation within acceptable limits, an engineering evaluation is required to determine if RCS operation can continue. This engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. The evaluation must verify the RCPB integrity remains acceptable and must be completed if continued operation is desired. Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.
ASME Code, Section Xl, Appendix E (Ref. 9), may be used to support the evaluation. However, its use is restricted to evaluation of the vessel beltline.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to accomplish the evaluation of a mild violation. More severe violations may require special, event specific stress analyses or inspections. A favorable evaluation must be completed if continued operation is desired.
Condition A is modified by a Note requiring Required Action A.2 be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action A.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
B.1 and B.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the RCS remained in an unacceptable P/T region for an extended period of increased stress, or a sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the RCS at reduced pressure and temperature. With the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.
(continued)
Brunswick Unit 2 B 3.4.9-5 Revision No. 35 l
RCS P/T Limits B 3.4.9 BASES ACTIONS B.1 and B.2 (continued)
Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that has been verified as safe by stress analyses.
The Required Action must be initiated without delay and continued until the limits are restored. With the applicable limits of Figure 3.4.9-3, 3.4.9-4, or 3.4.9-5 exceeded during inservice hydrostatic and leak testing operations, the maximum temperature change shall be limited to 10OF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during restoration of the P/T limit parameters to within limits.
Besides restoring the P/T limit parameters to within limits, an engineering evaluation is required to determine if RCS operation is allowed. This engineering evaluation will determine the effect of the P/T limit violation on the fracture toughness properties of the RCS. This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to > 212 0F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components. ASME Code, Section Xl, Appendix E (Ref. 9), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.
Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.
(continued)
Brunswick Unit 2 B 3.4.9-6 Revision No. 35 l
RCS P/T Limits B 3.4.9 BASES SURVEILLANCE SR 3.4.9.6. SR 3.4.9.7, and SR 3.4.9.8 (continued)
REQUIREMENTS The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature limits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.
SR 3.4.9.6 is modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs.
SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated 30 minutes after RCS temperature is s 800F in MODE 4.
SR 3.4.9.8 is modified by a Note that requires the Surveillance to be initiated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature is
- 100F in MODE 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the specified limits.
REFERENCES
- 1.
Calculation 0B21-1029, "Instrument Uncertainty for RCS Pressure/Temperature Limits Curve," Revision 0
- 2.
- 3.
1989 Edition of the ASME Code, Section Xl, Appendix G.
- 4.
ASME Code Case N-640, "Alternative Reference Fracture Toughness for Development of P-T Limit Curves Section Xl, Division 1."
- 5.
EPRI Report TR-1003346, BWRVIP-86-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, October 2002.
- 6.
- 7.
Regulatory Guide 1.99, Revision 2, May 1988.
- 8.
Calculation OB1 1-0005, "Development of RPV Pressure-Temperature Curves For BNP Units 1 and 2 For Up To 32 EFPY of Plant Operation," Revision 1.
- 9.
ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.
- 10.
Brunswick Unit 2 B 3.4.9-9 Revision No. 35 l
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.10 Consistent with Regulatory Guide 1.9 (Ref. 11), paragraph C.2.2.12, this Surveillance demonstrates that DG non-critical protective functions (e.g.,
high jacket water temperature) are bypassed on an ECCS initiation test signal. The non-critical trips are bypassed during DBAs and provide an alarm on an abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. The DG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not immediately detrimental to emergency operation of the DG.
I The 24 month Frequency is based on engineering judgment, takes into consideration plant conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths. Operating experience has demonstrated that these components will pass the SR when performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
The SR is modified by a Note. To minimize testing of the DGs, the Note allows a single test (instead of two tests, one for each unit) to satisfy the requirements for both units. This is allowed since the main purpose of the Surveillance can be met by performing the test on either unit. If the DG fails one of these Surveillances, the DG should be considered inoperable on both units, unless the cause of the failure can be directly related to only one unit.
SR 3.8.1.11 Brunswick Nuclear Plant performs a 60 minute run greater than or equal to the continuous rating (3500 kW) which bounds the maximum expected post-accident DG loading. The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for (continued)
Brunswick Unit 2 B 3.8.1-28 Revision No. 35 l