ML20108E181
| ML20108E181 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/07/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20108E183 | List: |
| References | |
| DPR-66-A-200 NUDOCS 9605100045 | |
| Download: ML20108E181 (7) | |
Text
a UNITED STATES
[
E NUCLEAR REGULATORY COMMISSION E
f WASHtNGTON, D.C. 20eedK1001
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Dil00ESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated February 12, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; 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 (i) that the activities authorized by this amendment ca:i be conducted without endangering the health and safety of the public, and (ii) that such activities will be 1
conducted in comp 1'ance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
9605100045 960507 PDR ADOCK 05000334 p
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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. 200, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION 4~dd en
[JohnF.Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7, 1996 l
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~d ATTACHMENT TO LICENSE AMENDMENT NO.200 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert XI XI 3/4 6-14 3/4 6-14 8 3/4 6-10 B 3/4 6-10 B 3/4 6-11 B 3/4 6-11
kh l DPR-66 INDEX BASES SECTION R&GE 3/4.4.8 SPECIFIC ACTIVITY.
B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY.
B 3/4 4-11 l
3/4.4.11 RELIEF VALVES B 3/4 4-11 3/4.4.12 REACTOR COOLANT SYSTEM VENTS B 3/4 4-11 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS B 3/4 5-1 3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS B 3/4 5-1 l
3/4.5.4 BORON INJECTION SYSTEM B 3/4 5-2 l
3/4.5.5 SEAL INJECTION FLOW.
B 3/4 5-3 l
3/4.6 CONTAINMENT SYSTEMS
'3/4 6 1 PRIMARY CONTAINMENT l
3/4.6.1.1 Containment Integrity.
B 3/4 6-1 t
i 3/4.6.1.2 Containment Leakage.
B 3/4 6-1 3/4.6.1.3 Containment Air Locks.
B 3/4 6-1 3/4.6.1.4 AND 3/4.6.1.5 Internal Pressure and Air Temperature.
B 3/4 6-9 1
3/4.6.1.6 Containment Structural Integrity B 3/4 6-9 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 AND 3/4.6.2.2 Containment Quench and Recirculation Spray Systems.
B 3/4 6-10 3/4.6.2.3 Chemical Addition System B 3/4 6-11 3/4.6.3 CONTAINMENT ISOLATION VALVES B 3/4 6-11 3/4.6.4 COMBUSTIBLE GAS CONTROL.
B 3/4 6-11 k
i BEAVER VALLEY - UNIT 1 XI Amendment No.200
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~ DPR-66 3
CONTAINMENT SYSTEMS i
l SURVEILIANCE REQUIREMENTS (Continued) l
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Verify, at the frequency specified in the Inservice Testing
- Program, that each recirculation spray pump's developed i
head at the flow test point is greater than or equal to the required developed head as specified in the Inservice
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Testing Program and the Containment Integrity Safety j
Analysis.
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At least once per 18 months during shutdown, by:
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Cycling each power operated (excluding automatic) valve in the flow path not testable during plant operation, j
through at least one complete cycle of full travel.
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2.
Verifying that each automatic valve in the flow path j
actuates to its correct position on a test signal.
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Initiating flow through each River Water subsystem and its two associated recirculation spray heat exchangers, l
and verifying a flow rate of at least 8000 gpa.
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At least once per 5 years by performing an air or smoke I
flow test through each spray header and verifying each j
spray nozzle is unobstructed.
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BEAVER VALLEY - UNIT 1 3/4 6-14 Amendment No.200
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- DPR-66 2
o CONTAINMENT SYSTEMS BASES 4
4 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 and 3/4.6.2.2 CONTAINMENT OUENCH AND RECIRCULATION SPRAY SYSTEMS The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent return to subatmospheric t
j pressure will occur in the event of a LOCA.
The pressure reduction and resultant termination of containment leakage are consistent with 4
j the assumptions used in the accident analyses.
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The recirculation spray system consists of four 50 percent
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capacity subsystems each composed of a spray pump, associated heat exchanger and flow path.
Two of the recirculation spray pumps and motors are located outside containment (RS-P-2A and RS-P-2B) and two pumps and motors are located inside containment (RS-P-1A and
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RS-P-1B).
The flow path from each pump is piped to an individual 180 recirculation spray header inside containment.
Train "A"
electrical power and river water is supplied to the subsystems containing recirculation spray pumps RS-P-1A and RS-P-2A.
Train "B" electrical power and river water is supplied to the subsystems containing recirculation spray pumps RS-P-1B and RS-P-2B.
Verifying that each recirculation spray system pump's developed head at the flow test point is greater than or equal to the required developed head ensures that recirculation spray system pump performance has not degraded during the cycle.
The term " required developed head" refers to the value that is assumed in the Containment Integrity Safety Analysis for the recirculation spray pump's developed head at a specific flow point.
This value for the required developed head at a flow point is defined as the Minimum Operating Point (MOP) in the Inservice Testing Program.
Flow and differential head are normal test parameters of centrifugal pump performance required by Section XI of the ASME Code.
Since the recirculation spray system pumps cannot be tested with flow through the spray headers, they are tested on bypass flow.
This test confirms one point on the pump design curve and is indicative of overall performance.
Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance.
BEAVER VALLEY - UNIT 1 B 3/4 6-10 Amendment No. 200
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- DPR-66 CONTAINMENT SYSTEMS j
BASES j
3/4.6.2 DEPDRASURIZATION AND COOLING SYSTEMS (Continued) j 3/4.6.2.3 CHEMICAL ADDITION SYSTEM 1
3 The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.
The limits on NaOH minimum volume and concentration, ensure j
that 1) the iodine removal efficiency of the spray water is i
maintained because of the increase in pH value, and 2) corrosion
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effects on components within containment are minimized.
These assumptions are consistent with the iodine removal efficiency j
assumed in the accident analyses.
3/4.6.3 CONTAINMENT ISOLATION VALVES i
j The OPERABILITY of the containment isolation valves ensures
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that the containment atmosphere will be isolated from the outside
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envircnment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
containment isolation within the time limits specified ensures that i
the release of radioactive material to the environment will be
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consistent with the assumptions used in the analysis for a LOCA.
The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an j
accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action j
will prevent the release of radioactivity outside the containment.
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3/4.6.4 COMBUSTIBLE GAS CONTROL i
j The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment l
will be available to maintain the hydrogen concentration within i
containment below its flammable limit during post-LOCA conditions.
j Either recombiner unit is capable of controlling the expected i
hydrogen generation associated with 1) zirconium-water reactions, t
- 2) radiolytic decomposition of water, and 3) corrosion of metals within containment.
These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7,
" Control of Combustible Gas Concentrations in Containment Following a LOCA."
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BEAVER VALLEY - UNIT 1 B 3/4 6-11 Amendment No.200 l