ML20246P813
| ML20246P813 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/12/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20246P819 | List: |
| References | |
| DPR-66-A-142, NPF-73-A-018 NUDOCS 8907200327 | |
| Download: ML20246P813 (13) | |
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i UNITED STATES NUCLEAR REGULATORY COMMISSION c
3 WASHINGTON, D. C. 20586 1.,
j DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER CGIPANY DOCr.ET NO. 50-334 BEAYER VALLEY POWER STATI0d, UNIT NO. 1
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. DPR-66 1.
The Nuclear Regulatory Conraission (the Conslission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated April 21,,1989 complies with the standards and requirements of the Atomic Enirgy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility w;11 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Consnission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comanon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comunission's regulations and all applicable requirements have been satisfied.
i 8907200327 890712
't PDR ADOCK 05000334 P
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications,.
The Technical Specifications contained in Appendix A, as revised through Amendment No.142, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY C0ttilSSION
'~
hn 'F.
Stolz, Director ro et Directorate I-4 sio'n of Reactor Pro ects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 12,1989 i
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L i-ATTACHMENT TO LICENSE AMENDMENT NO. 142,_
FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A (Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by, amendment number and contain vertical lines 16dicating the areas of change.
l Remove Insert 3/4 4-23 3/4 4-23 l
l 3/4 4-26 1
B 3/4 4-10 B 3/4 4-10 3/4 4-25 3/4 4-25 a
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REACTOR COOLMfT SYSTEM SURVEILLANCE REQUIREGDETS l
4.4.9.1 a.
The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per.30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testin,g operations.
b.
The Reactor Coolant System temperature and pressure f
conditions shall be determined to be to the right of the l
critica)ity limit line within 15 minutes prior to achieving reactor criticality.
BEAVER VALLEY - UNIT 1 3/4 4-23 Amendment No. M2,142
]
j anacron_ cooIAuTmam BASES vesseA Insaas raalus are essensla12y zuenszcat, une measurou transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel.
The heatup and cooldown curves must be recalculated when the a RT determined from the NDT surveillance capsule is diEferent from the calculated ARTNDT f0Y the equivalent capsule radiation exposure.
The pressure-temperature limit ' lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic. testing have been. provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice leak and hydrostatic testing.
The number of. reactor vessel irradiation surveillance specimens and-the frequencies for removing and testing these specimens are provided in UFSAR Table 4.5-3 to assure compliance,with the requirements of l
Appendix H to 10 CFR 50.
The limitations imposed on the pressurizer heatup and cooldown'ratest and spray water temperature differential Ore provided to assure that, s
the pressurizer is operated within the design criteria assumed foro the fatigue analysis performed in accordance with the ASME' Code requirements.
The OPERABILITY of two PORV's or'an RCS vent opening of. greater than 3.14 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR-Part 50 when one or more of the RCS cold legs are 1 275'F.
Either.PORV has adequate relieving c.:.pability to protset the RCS from over-pressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator 5 25'F above the RCS cold leg temperature or (2) the start of a charging pump and its injection into a water solid RCS.
3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2,
and 3
components ensure that the structural integrity and operational readiness of these components will ne maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the ASME Boiler and Pressure.
Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific writ 3en relief has been granted by l
the Commission pursuant to 10 CFR Part 60.55a(g)(6) (i).
1 3/4.4.11 DRTTEF VALVES The relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable.
The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure j
the ability to seal this possible RCS. leakage path.
BEAVER VALLEY - UNIT 1 B 3/4 4-10 Amendment No.M,W,142
7---_.-__
MATERIAL PROPERTY BASIS' CONTROLLING MATERIAL:
WELD METAL l
COPPER CONTENT:
0.31 WT1 PH0SPH0RUS CONTENT:
0.015 WT1 RT INITIAL:
0'F MDT RT AFTER 9.5 EFPY:
1/4T,274'F-NDT 3/4T.137'F CURVE APPLICABLE FOR C00LDOWN RATES UP TO 100'F/HR FOR THE PERIOD UP TO 9.5 EFPY.AND CONTAINS MARGl.15 0F-10'F AND 60 PSIG POSSIBLE INSTRUMENT ERRORS 3000 I
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UNACCEPTABLE
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i OPERATING REGION
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1000 f
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A M
I ACCEPTABLE C00LDOWN 1
M Ef OPERATING REGION RATES *F/HR 1
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40
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II 60-i e
100 u
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100 200 300 400 500 INDICATED TEMPERATURE ('F)
FIGURE 3.4-3 BEAVER VALLEY UNIT N0. 1 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICA8LE FOR THE FIRST 9.5 EFPY 3/4 4-25 (next page is 3/4 4-27)
I fnendment No. %W.141
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UNITED STATES
'e NUCLEAR REGULATORY COMMISSION I
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DUQUESNE LIGHT COMPANY i
OHIO EDISON COMPANY THECLEVELANDENCTRICILLUMINATINGCOMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT NO. 2 t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment Sy Duquesne Light Company, et al.
(the licensee) dated April 21, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's rules and regulations set fort'? in 10 CFR Chapter It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amrendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted ir compliance with the Connission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security er to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
J
1 2-2.
Accordingly, the license.is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications I
The Technical. Specifications contained in Appendix A, as revised through Amendment No.18, and the Environmental Protection Plan contained in Appendix B both of which are attached hereto are hereby incorporated in the license. DLCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective on issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COM4ISSION Johh F. Stolz, Directopf' P
ject Directorate I W ision of Reactor Projects I/IL Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 12,1989
)
l 1
j ATTACHMENT TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. NPF-73
)
DOCKET NO. 50-412 Replace the following pages of Appendix A (Technical Specifications) with the j
enclosed pages as indicated. The reyised pages are identified by amendment number and contain vertical lines ihdicating the areas of change.
)
Remove Insert 3/4 4-30 3/4 4-30 3/4 4-33 B 3/4 4-14 8 3/4 4-14
+
B 3/4 4-15 B 3/4 4-15 3/4 4-32 3/4 4-32 i
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6
REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE, LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 9
3.4.9.1 The Reactor Coolant System *(except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on i
Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
a.
A maximum heatup of 60 F in any 1-hour period, b.
A maximum cooldown of 100 F in any 1-hour period, and A maximum temperature change of < 5 F in any 1-hour period during c.
hydrostatic testing operations a5cve system design pressure.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an analysis to determine the effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T,yg and pressure to less than 200'F and 500 psig, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.9.1 a.
The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
b.
The Reactor Coolant System temperature and pressure conditions shall be determined to be to the right of the criticality limit line within 15 minutes prior to achieving reactor criticality.
l 1
BEAVER VALLEY - UNIT 2 3/4 4-30 eaandment No. 18 lL_______--
REACTOR COOLANT SYSTEM BASES 3/4.'4.9 PRESSURE / TEMPERATURE LIMITS (Continued)
The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrcatatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice leak and hydrostatic testing.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in UFSAR Table 5.3-6 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.
The limitations imposed on the pressurizer heatup and cooldown rates and auxiliary spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.
.j.
The OPERABILITY of two PORVs or an RCS vent opening of greater than 3.14 square inches ensures that the RCS will be protected from pressure tran-sie
. which could exceed the limits of Appendix G to 10 CFR Part 50 when one or.wre of the RCS cold legs are < 350 F.
Either PORV has adequate relieving capability to protect the RCS fro'ii overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water tempera-ture of the steam generator < 50 F above the RCS cold leg temperature or (2) thf startofachargingJumpanditsinjectionintoawatersolidRCS.
OVERP'< ESSURE PROTECTION SYSTEMS The Maximum Allowed PORV Setpoint for the Overpressure Protection Systems (OPPS) is derived by analysis which models the performance of the OPPS assuming various mass input and heat input transients.
Operation with a PORV setpoint less than or equal to the maximum setpoint ensures that nominal 10 EFPY Appen-dix G limits will not be violated with consideration for:
(1) a maximum pressure overshoot beyond the PORV setpoint which can occur as a result of time delays in signal processing and valve opening; (2) a 50*F heat transport effect made possible by the geometrical relationship of the RHR suction line and the RCS wide range temperature indicator used for OPPS; (3) instrument uncertainties; and (4) single failure.
To ensure mass and heat input transients more severe than those assumed cannot m.., h ehnical Specifications require lockout of all but one centrifugal charging pump while in r65E5 4, 5, and 6 with the reactor vessel head installed and disallow start of an RCP if secondary coolant temperature is more than 50 F above reactor coolant temperature.
Exceptions to these requirements are acceptable as described below.
Operation above 350 F but less than 375'F with only one centrifugal charg-ing pump OPERABLE is allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. As shown by analysis LOCAs occurring at low temperature, low pressure conditions can be successfully niti-gated by the operation of a single centrifugal charging pump and a sing'.le !.HSI pump with no credit for accumulator injection.
Given the short time duration BEAVER VAM.EY - UNIT 2 B 3/4 4-14 Amendment No. 18
p,~-
REACTOR COOLANT SYSTEM E ES OVERPRESSURE-PROTECTION SYSTEMS (Continued) l that the condition of having only one centrifugal charging pump OPERABLE is allowed and the probability of a L0EA occurring during this time, the failure of the single centrifugal charging pump is not assumed.
Operation below 350 F but greater than 325 F with all centrifu0al charging pumps OPERABLE is allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
During low pressure, low tempera-ture operation all automatic Safety Injection actuation signals are blocked.
In normal conditions a single failure of the ESF actuation circuitry will result in the starting of at most one train of Safety Injection (one centrifugal charging pump, and one LHSI pump).
For temperatures above 325'F, an overpress-ure event occurring as a result of starting these two pumps can be successfully mitigated by operation of both PORVs without exceeding Appendix G limit. Given the short time duration that this condition is allowed and the low probability of a single failure causing an overpressure event during this time, the single failure of a PORV is not assumed.
Initiation of both trains of Safety Injection 4'
during this 4-hour time frame due to operatot trror or a single. failure occurring during testing of a redundant channel are not cnsidered to be credible accidents.
The maximum allowed PORV setpoint f N the Overpressure Protection System will be updated based on the results of examinations of reactor vessel material irradiation surveillance specinens performed as required by 10 CFR Part 50, Appendix H and in accordance with the schedule in UFSAR Table 5.3-6.
l 3/4.4.10 STRUCTURAL INTEGRITY l
The inservice inspection and te: ting programs for ASME Code Class 1, 2
and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a (g)(6_)(i).
BEAVER VALLEY - UNIT 2 B 3/4 4-15 Amendment No. 18
a MATERIAL PROPERTY BASIS Controlling Meterial
- Plate Metal Copper Content
- Conservatively Aneumed to be 0.10 wt%
Phosphorus Content
- 0.010 wt%
RT I"III*I I I NDT NOT After 10 EFPY
- 1/ 47. 139'F RT 3/4T.114'F 3000 i
CURVE APPLICASLE FOR COOLDOWN R ATES UP TO 100'F/HR FOR THE SERVICE PERICO UP TO 10 EFPY AND CONTAINS MARGINS OF 10'F AND 80 PSIG FOR POSSISLE INSTRUMENT ERRORS.
2500 s
to Q. 2000 UNACCEPTABLE ACCEPTASLE w
OPERATION OPERATION 4
W 3W O
W 1500 g
c.
OW H<
9 1000 0
E COOLDOWN RATES (*F/HR) i 500 g
8100d 0
100 200 300 400 500 INDICATED TEMPERATURE (DEG.F)
FIGURE 3.4-3 BEAVER VALLEY UNIT NO. 2 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE FOR THE FIRST 10 EFPY BEAVER VALLEY - UNIT 2 3/4 4-32 (NEXT PAGE IS 3/4 4-34) l Amendment NO.18 c