ML20236V631
| ML20236V631 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/01/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 2NRC-7-211, TAC-62534, NUDOCS 8712040427 | |
| Download: ML20236V631 (4) | |
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y 2NRC-7-211 (412)393 7546 Beaver Valley No. 2 Unit Project Organization
. December ll',
1987 Telecopy(412)393 7889 i S.E.G. Buildin9 P.O. Bos 328 Shippingport. PA 15077 United States Nuclear Regulatory Commission 1
ATTN: Document Control Desk
~Vashington, DC-20555
SUBJECT:
Beaver Valley Power Station Unit No. 2 l
Docket No. 50-412 BVPS-2 PSAR Chapter 14, Test. Change Status' Report Gentlemen:
Forwarded to NRC is the fifth status report identifying changes to the Initial Test Program as described in Chapter 14,'of the PSAR. These changes are made in accordance with the provisions of' 10CPR50.59 and reported to NRC in-accordance'with 50.59(b) within one month of initiating changes per BVPS-2 Facility Operating License Condition C.(3).
DUQUESNE LIGHT' COMPANY:
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M11/VRB/NRC/ STATUS l
Atta ment' l
AR cc: Mr. P. Tam,- Project Manager (w/a)
H Mr. J. Beall, NRC Sr. Resident Inspector (w/a)
Mr. P. Ven, NRC Reactor Engineer, Region I (w/a)
'INP0 Records Center (w/a)
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8712040427 871201
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BVPS-2 FSAR Chapter 14 Test Change Status Report FSAR Section Title
- 1) 14.2.12.04.02 Alignment of Nuclear Instrumentation (IST 2.02.01)
System (IST)
Test IST-2.02.01,Section VII.K. " Power Range Detector High Voltage check,"
cannot be performed prior to Commercial Operations because tsf schedular d
restraints. This section of the test requires that one of four operating power range channels be taken out of service at a time and obtain a high voltage plateau curve while the plant is at or near full power.
These actions are within the requirements of Technical Specification 3.3.1.1.
l This test will be completed prior to December 31, 1987.
b2 5b Test P0-2.01A.03,Section VII.B,
" Final Verification of Reactor Plant Setpoints," cannot be performed in total because several systems (such as Feedvater) do not have their final setpoint values in place. This test is l
only a paper check of the final setpoint value. This test secticn does not determine or physically set any setpoints or affect Technical I
Specifications. This section of the test will be completed by the First i
Refueling.
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- 3) 14.2.12.25.06 Measurement-of Steam Generator Moisture.
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(S0V-2.21A.01)
Carryover (50V) l Test S0V-2.21A.01, vill not be completed prior to Commercial Operations due to schedular constraints. There are no Technical Specification requirements associated with this test. The test is expected to be completed prior to December 31, 1987.
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- 4) 14.2.12.33.01 Automatic Steam Generator Vater Level (SOV-2.24C.01)
Control Test (SOV)
Test SOV-2.240.01,Section VII.F vill not be completed prior to Commercial Operations due to schedular constraints. This section of the procedure vill I
obtain flow data at 100% power for information only and demonstrate repeatability of the Feedvater and Steam Flow Transmitters at 30, 50, 75 and 100% reactor power during a plant startup.
Initial transmitter calibration and testing is completed to meet Technical Specification 3.3.1.1.
This test l
section vill be performed during a plant startup and is expected to be
< completed by the First Refueling.
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BVPS-2 FSAR Chapter 14 Test Change Status Report I
(continued)
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FSAR Section Title 5)
Plant Communications Test (SOV)
Test S0V-2.40A.01 is approximately 70% complete. Communications required by i
Technical Specification 3.9.5 to support refueling vere tested
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satisfactorily and used during the Initial Core Loading. The remaining j
portions of this test are to be completed by December 31, 1987.
j 6) 14.2.12.34.01 Steam Generator Blowdown System Test (SOV) i (SOV-2.25.01)
Due to schedular constraints a portion of test 50V-2.25.01 vill not be completed on time. The "B" Evaporator [2SGC-EV21B] and Ion Exchanger [2SGC-
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IE21A, B] remains to be tested in accordance with Sections VII.N and 0 of Technical Specification requirements for the the procedure. There are no untested portion of the system.
This test is expected to be completed by j
the First Refueling.
- 7) 14.2.12.40.02 Auxiliary Boiler Test (SOV)
(SOV-2.27.02) i Due to schedular constraints a portion of this test vill not be completed on time. Additional performance runs on both the A and B Boilers vill occur with the vendor present to verify design capacity. There are no Technical i
Specification requirements associated with this system.
This test is expected to be completed by the First Refueling.
1 8) 14.2.12.05.03 Measurement of Core Parameters During (BVT-2.1-2.2.3)
Steady State Conditions (IST)
Test BVT-2.1-2.2.3, " Nuclear Power Range Calibration," vill be performed to meet this test abstract requirement at 100% power.
This test will not be completed prior to Commercial Operations due to present plant conditions.
In compliance with Technical Specification 4.3.1.1.1.(2), the present power range calibration vill be checked and/or calibrated 'as required by the Technical Specification. This test is expected to be completed by December 31, 1987.
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I BVPS-2 FSAR Chapter 14 Test Change Status Report I
(continued)
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l FSAR Section Title l
- 9) 14.2.12.02.13 Full Power Demonstration Test (IST)
(IST-2.01A.08)
During performance of test IST-2.01A.08, the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run at 99-100% power with blevdown secured was not possible to attain.
The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run was a
performed at >97% power and with blowdown in service. This 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run meets j
the intent of the test.
However, a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run at conditions closer to l
warranty values (99-100% if possible and with blowdown secured) vill be performed prior to December 31, 1987.
This test does not affect any
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Technical Specification requirements.
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- 10) 14.2.12.23.02 Gaseous Waste System Test (S0V)
(S0V-2.19.02) l Test SOV 2.19.02 was required to be completed prior to Commercial Operation.
Due to modifications per ACN 5448 on the condenser air ejector vent portions l
of the system, this test will not be completed on time. The modification vill entail adding blowers between the Air Ejectors and the Charcoal Delay
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Beds.
Subsequent to these modifications, the system vill be tested in j
accordance with Section VII.E of the test procedure. The Air Removal (Steam I
Side) Main Condenser System is Non-Safety Related and is not addresscd in any Technical Specification.
Technical Specification 3.11.2 addresses J
gaseous effluent dose rates.
ACN 5448 modifications vill not affect the
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basis of this Technical Specification.
This test is expected to be completed prior to the First Refueling.
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- 11) 14.2.12.06.08 Verification of Plant Performance (IST-2.04-06)
Following Plant Load Rejection / Trip From Power (IST)
Test IST-2.04-06 vill not be completed prior to Commercial Operations due to schedular constraints. Response time test of the Reactor Coolant System (RCS) Hot Leg Resistance Temperature Detectors (RTDs) during a turbine trip is being deferred.
Westinghouse per letter BV2-SET-151 has evaluated previous test data and concluded that the data indicates time response for the OTDT and OPDT protection system is in compliance with the FSAR analysis (6 seconds) and Technical Specification (4 seconds) requirements. The OTDT and OPDT trip setpoints are set at a conservative value until the RTD i
response time data is obtained and acceptable.
Completion of this test is scheduled prior to the First Refueling.
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