ML20238A152

Forwards Second Status Rept Identifying Changes to Initial Test Program Described in Chapter 14 of Fsar.Changes Made in Accordance W/Provisions of 10CFR50.59

ML20238A152
Person / Time
Site:	Beaver Valley
Issue date:	08/17/1987
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-193, TAC-63534, NUDOCS 8708200385
Download: ML20238A152 (11)

Text

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3 2NRC-7-193 l e AUGUST 17, 1987 J 'A@

DuquesneUdd Deaver Valley No. 2 Unit Project Organization i G.E.G. Bultding Telecopy ( 26 2 Ext.160 P.O. Box 328 Shippingport, PA 15077

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United States Nuclear Regulatory Commission l ATTN: Document Control Desk {

Washington, DC 20555 l

SUBJECT:

Beaver Valley Power Station Unit No. 2 Docket No. 50-412 BVPS-2 FSAR Chapter 14, Test Change Status Report Gentlemen:

• Forwarded to NRC is the second status report identifying changes to the Initial Test Program as described in Chapter 14 of the FSAR. These changes are made in accordance with the provisions of 10CFR50.59 and reported to NRC in accordance with 50.59(b) within one month of initiating changes per BVPS-2 5%

Power Operating License Condition C.(3).

DUQUESNE LIGHT COMPANY By _

L4. J. Jarey V Senior Vi(tG President  !

WRB/ijr '

NR/WRB/FS/CH14 Attachment AR/NAR cc: Mr. P. Tam, Project Manager (w/a) ,

Mr. J. Beall, NRC Sr. Resident Inspector (w/a)  !

Mr. L. Prividy, NRC Resident Inspector (w/a)

Mr. P. Wen, NRC Reactor Engineer, Region I (w/a)

INP0 Records Center (w/a) h, 8708200385 870817 /

PDR P

ADOCK 05000412 PDR

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BVPS-2 FSAR Chapter 14 Test Change St_atus_Repo_rt l

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REFERENCES:

(a) DMW-490 Precautions, Limitations and Setpoints Revision i

3, dated March 13, 1987 l

(b) WCAP-10073 Process Control Systems Scaling Manual Revi-sion 3, dated May, 1987 I

i F_SAR Section Title l l

1. 14.2.12.02.03 Verification of Reactor Plant Set- )

points (P0)

Test PO-2.01A.03,Section VII. A was scheduled to be completed prior to Mode

-4. The below setpoints were not completed by Mode 4 due to hardware prob-lems and manpower support.

1. Computer Generated Alarms

a. Delta Flux Alarm - Based on Technical Specification 4.2.1.1, this alarm is not required to be operable until Mode 1 at 15% power or, periodic monitoring will be performed to meet this Technical Speci-fication. Therefore, this alarm is now rescheduled to be available prior to Commercial Operations.

b. Rod Deviation Alarms - These are computer generated alarms used by but not required by Technical Specification 4.1.3.2. Operation of j these alarms is now rescheduled to be completed by Commercial Oper-ations.

2. Overtemperature Delta T and Overpressure Delta T Reference (a) made recent changes to these setpoints requiring recali-bration to the values in Reference (b). Prior to Mode 4, this work was in progress but not completed in time due to available manptwer. Based on Technical Specification 3.3.1.1 and Table 3.3-1 Items 7 and 8, these setpoints are not required until Mode 2, therefore, they were )

rescheduled and completed prior to Mode 2. '

3. Rod Insertion Limit Alarm (Bank C)

Reference (a) made recent changes to the al arm setpoint requiring recalibration. Based on Technical Specification 4.1.3.6, this alarm was not required until prior to Mode 2, therefore, it was rescheduled ano completed prior to Mode 2.

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FSAR Section _

Title .

2. 14.2.12.2.19 Engineered Safety Features Time Response Summary (P0)

Test P0-2.01A.11 was scheduled to be completed prior to Mode 4. With the exception of field testing of the Control Room High Radiation Isolation Monitor's response time, this test was completed by Mode 4. Based on Tech- 4 nical Specification 3.3.3.1, these monitors can be out of service providing I the Unit 2 Control Room Services Normal Air Intake and Exhaust Isolation  ;

Dampers are closed. Final testing of these monitors is now rescheduled to j be completed by Commercial Operations. l l

3. 14.2.12.20.01 Supplementary Leak Collection and l Release System Test (P0) i Test P0-2.16.01 was scheduled to be complete prior to Mode 4. Technical i Specification 4.7.8 requirements for the Supplemental Leak Collection and l l Release System Test have been met, however, a retest action is open to review and approve the final air balance report prior to Mode 1 at 50%

power.

Additional retesting to improve negative fuel building air pressure results 1 is scheduled to be completed prior to Commercial Operations. Technical Specification 3.9.12 does not apply to the Fuel Building portion of the SLCRS at this time, since it does not contain irradiated fuel.

4. 14.2.12.10.03 Containment Drains and Unidentified i Leak Rate Systems Tests (S0V) 1 Test 50V-2.09.03 was scheduled to be completed prior to Mode 4. This test cannot be completed due to forthcoming wiring changes on the Containment l Sump Limit Switches. These switches are part of the Containment Sump Dis- l charge Flow Instrument System. Based on Technical Specification 3.4.6.1, the Containment Sump Discharge Flow Instrument System is not required to be operable since the Containment Sump Narrow Range Level Instrument is avail-able for operations. The out of service equipment was rescheduled to be operable prior to entering Mode 2.  !

Portion of Section VII.A, which verify operability of Program Controller for Unidentified Leakage (PCUIL), was not completed prior to Mode 2 due to project scheduling requirements. The applicable portions of the test have been satisf actorily completed to demonstrate system operability as defined in Technical Specifications 3.4.6.1 and 3.4.6.2. Final testing is scheduled prior to Commercial Operations.  ;

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FSAR Section , _ Title

5. 14.2.12.69.02- Miscellaneous Secondary Plant Heat-

ing, Ventilation, and Air Condition- '

f L ing System Test (S0V) 1 Test 50V-2.44F.01 was- scheduled to be completed prior to Mode 3. The test

! is waiting for the final air balance report to support test completion.

There are no Technical- Specification requirements with the systems involved. This~ test was rescheduled and completed prior to Mode 2.

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6. 14.2.12.69.01 Miscellaneous Safety Related Heat - I L ing, Ventilation, and Air Condition-L ing Systems Test (P0)  !

l; Test P0-2.44F 01 was scheduled to be . completed prior to Mode 3. The ' test l was waiting for. the final air balance report to support test completion.

There are no. Technical Specifications requirements with the - systems.

e involved. This test wss rescheduled and completed prior to Mode 2.-

7. 14.2.12.25.01 Atmospheric Steam Dump Valves and  ;

Residual Heat Release Valve Test (PO)

Test P0-2.21A.01's retest 21A.001, which performs logic testing, was sched- '

uled and completed at <350*F (prior to Mode 3). Due to forthcoming design changes, to the controT logic of the ASOVs, retest 21A-001 was not -couple-ted prior to Mode 3. Since there are no Technical Specifications associ-ated with this procedure to preclude testing prior to Mode 2, . retest  ;

21A.001 was rescheduled and completed during Mode 3. .i i

Retest 21 A-002 which strokes the Atmospheric- Steam Dump Valves was not i completed prior . to Mode . 2 due to troubleshooting of the "C" Atmospheric Steam Dump Valve. There are no applicable Technical . Specifications for Atmospheric' Steam Dump ' Valves. Two out of three Atmospheric Steam Dump Valves- are operable as well as the Residual Heat Release Valve 2SVS*HCV104.

Retest 21A-002 was scheduled and completed prior to Mode 1.

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t FSAR Section Title

8) 14.2.12.8.15 Reactor Coolant System Flow Measure-ments(IST) l Based on Westinghouse startup procedure DMW-SU-2.1.6 " Reactor Coolant Sys-tem Flow Measurement", Revision 2, and Technical Specification 3.4.1.1, this test abstract is being revised per Attachment A, which measures RCS flow with all three RCP operating, as opposed to other RCP configurations.

9) 14.2.12.3.4 Control Rod Drop Time Measurement Test (IST)

Based on Westinghouse's consideration that Control Rod Drop Times for " Hot No Flow" conditions will bound in the times for " Hot Full Flow" conditions, this test abstract is being revised per Attachment B to delete the need of ,

obtaining times for " Hot No Flow" conditions. There are no Technical Specifications requirements associated with this change.

10) 14.2.12.10.01 Primary Drains Transfer System Test (S0V)

Test 50V-2.09.01's retest 09-001 (Section VIIE), which checks the primary drains cooler heat transfer capability, was not be completed prior to Mode 2.due to project scheduling requirements. There are no Technical Specifi-cations associated with this non-safety related system. The retest is expected to be completed prior to Commercial Operations.

11) 14.2.12.43.01 Service Water System Test (P0)

Test PO-2.30.01's retest 30-002 ("C" pump high vibration) was not completed prior to Mode 2. Per Technical Specification 3.7.4.1, two Service Water Subsystems are required to be operable in Modes 1, 2, 3 and 4. Testing to ,

i support this specification has been completed. The "C" Service Water Pump, although deemed acceptable for short term use by Engineering, is still awaiting further modifications to reduce vibration levels for long term use. This work and retest 30-002 is expected to be completed prior to Commercial Operations.

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l f~ FSAR Section Title

12) 14.2.12.61.01 Radiation Monitoring Systems Test (PO)

Test P0-2.43.01 Section VII.0, which tests Non-safety Related process and effluent monitors that are not interlocked with non-DRMS equipment, was not completed prior to Mode 2 due to project scheduling requirements. All )

radiation monitors required by Technical Specification 3.3.3.1 have been i tested satisfactorily. The remaining area monitors in Section VII.D. are

! expected to be tested prior to Commercial Operations. There are no Tech-nical Specifications associated with the untested monitors, j

13) 14.2.12.68.01 Auxiliary and Waste Handling Build-ing Heating, Ventilation, and Air-Conditioning Systems Test (S0V)

Test SOV-2.440.01's retest 440-001, which verifies the final air balance for the Emergency Exhaust System and vibration levels on [2HVP-ACU211A],

will not be completed prior to Mode 2. The remainder of the test has been completed. The Emergency Exhaust System is safety rel ated , however no Technical Specifications apply. The retest is scheduled to be completed prior to 50% power.

14) 14.2.12.70.01 Condensate. Polishing Building Heating, Ventilation and Air-Conditioning Systems Test (SOV)

Test SOV-2.44G.01 sections VII . A. (Process Air Filtration System Logic),

VII.H. (Health Physics and Chem. Lab System Logic), and VII.I (overall system performance) have been tested and the systems are operational.

Several minor test deficiencies were generated and are presently being addressed on Maintenance Work Requests (MWR's) and Engineering Memorandums (EM's) which were not completed prior to Mode 2. The Subsystems are non-safety related and no Technical Specifications apply. Appropriate retests are scheduled to be conducted upon completion of deficiency resolutions prior to 50% power.

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FSAR Section Title l 15) 14.2.12.63.01 Engineered Safety Features Equipment l Venti ~iation Test (PO)

Test P0 2.448-01's retest 44B-001 which checks the vibration of three safe-ty related air conditioning units and verifies the Cable Vault and Rod Control Area final air balance, were not completed prior to Mode 2.

Section VII.A. (Main Steam Valve Area Ventilation System) was not completed prior to Mode 2 because the "B" Train Fan motor is being repaired. The "A" Train Fan has been tested and is operational . The remainder of the test i have been completed. These subsystems are safety related, however no Tech-nical Specifications apply.Section VII.A and Retest 44B-001 is scheduled to be completed prior to 50% power.

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16) 14.2.12.34.01 Steam Generator Blowdown System Test (SOV)

Test SOV-2.25.01's retest of Section VII.P (Retest 235-003) will reverify the performance of the Blowdown Tank Orain Cooler which was not completed I prior to Mode 2. The remainder of Section VII.P satisfactorily tested the l design of the blowdown system at rated flows from the Steam Generators. {

There are no Technical Specifications associated with the cooler which is i non-safety related. The cooler performance is scheduled to be verified prior to Commerical Operations.

17)14.2.12.61.03 Plant Radiation Survey and Verifica-tion of Shielding Effectiveness (IST)

This test abstract is being revised per Attachment C to allow the shielding survey to be performed at <5% power instead of 2-5% power. There are no Technical Specification reqliirements associated with this survey change.

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l ATTACHMENT A BVPS-2 FSAR

2. The lw f1w alarm actuates in accordance with design specifications.

14.2.12.8.15 Reactor Coolant System Flow Measurement (IST)

Test Ohfectives To verify predicted _ reactor coolant system (RCS) flow rates prior to lQ criticality getta various operating reactor coolant Dump _ (RCP 50, 75, y , and Tconfigurationt and prior to escalation above 100 percent power with three loops operating. 9 Prerequisites

1. The plant is in operational mode 3.

2. Instrumentation used for measuring the parameters shall be available.

Test Method Prior to criticality, loop elbow diffaraaHal nrannure 11 be used to measure the RCS flow ratecTor each RCP configuration $ Prior to l escalation above 50, 75, 90, and 100 percent power, secondary side calorimetric data will be used to verify RCS flow rate.

Acceptance Criteria The measured RCS flow rates are within design flow limits.

14.2.12.8.16 Reactor Coolant System Flw Coastdown Test (IST)

Test Objectives To measure the reactor coolant system (RCs) flow rate decrease subsequent to reactor coolant pump (RCP) trips at various RCP configurations.

Prerequisites

1. The plant is in operational mode 3.

2. The RCS Flow Test is complete.

Test Methods

1. At various RCP configurations, the RCPs will be tripped and the rate at which reactor coolant flow rate decreases will be measured.

2. The delay times associated with low flow trip, RCP bus undervoltage trip, and underfrequency trip will be measured.

Amendment 17 14.2-60 May 1987 ,.

e ATTACHMENT B (PAGE 1 0F 2)

BVPS-2 FSAR Acceptance Criteria The control rod position indication system performs indication and alarm functions over the entire range of travel in accordance with design and the Technical Specifications.

14.2.12.3.3 Control Rod Drive Mechanism Timing Test (IST)

Test objectives To verify proper slave cycles timing and proper operation of each full length control rod drive mechanism (CRDM).

Prerequisites The plant is in operational mode 5 or 3 as required.

Test Hethods

1. With the reactor coolant system (RCS) in the cold shutdown condition, each CRDH will be manually operated with a rod cluster control assembly (RCCA) attached. Recorder traces will be obtained while control rods are withdrawn and inserted. The traces will be evaluated to verify proper slave cycles timing and mechanism operation.

2. With the reactor coolant system (RCS) in the hot standby condition. each CRDH will be manually operated with a rod cluster control assembly (RCCA) attached. Recorder traces will be obtained while control rods are withdrawn and inserted. The traces will be evaluated to verify proper slave cycle timing and mechanism operation.

Acceptance Criteria' control rod drive mechanism timing and operation are in accordance with design specifications.

14.2.12.3.4 Control Rod Drop Time Hessurement Test (IST)

Test Objectives ,

I To verify the drop time for each rod cluster control assembly (RCCA) j f under no flow and full flow reactor coolant system (RCS) conditions, l i with the reactor in the cold shutdown =d ir. t.;t mdy conditionp3 and odd.ttoru\\y verif 3 The dr<.,p tirne for each RCC A undec Qt R fic, Prerequisites Rg conddgons eth the rec <. Ace in The hot standq sondhon. '

The plant is in operational mode 5 or 3 as required.

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Amendment 18 14.2-33 June 1987 l

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.- ATTACHMENT B  !

(PAGE 2 0F 2)

I BVPS-2 FSAR f

I Test Methods

1. The drop time will be determined by monitoring the rod position indication signal following de-energitation of the stationary winding of the RCCA drive mechanism. The drop time will be determined in the same manner for each of the M RCS conditions.

2. Rods having drop times which fall outside the two-sigma limit k will undergo additional drop testing to verify performance.

3. The effectiveness of the thimble dashpot region for decelerating ,

the rod will be monitored during each drop time measurement.

Acceptance Criteria i

1. Drop times do not exceed the times stated in the Technical '

l Specifications.

2. Ruds having drop times which fall outside the two-sigma limit )

exhibit consistent drop times during the additional drop testing. J

3. Control rod deceleration through the dashpot region is similar  !

for all rods being dropped under the same plant conditions.  !

14.2.12.3.5 Rod Control System Test (IST)  !

Test objectives ]

To demonstrate and document that the full length rod control system '!

satisfactorily performs the required control and indication functions.

l Prerequisites' j

, 4 The plant is in operational mode 3. ]

Test Methods

1. Rod motion, rod direction, rod speed and rod position indication will be verified using the digital step counters, rod position ,

system indicator, and rod speed indicators while operating in the

" individual rod bank control" mode. .

2. The control rod bank overlap will be verified by setting the bank l overlap digital thumb-wheel switches in the rod control system i logic cabinet to a specified position and using the digital step j

. counters while operating in the " manual" mode.

.3 . The operability of the control rod withdrawal inhibit functions will be demonstrated.

Amendment 18 14.2-34 June 1987

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l ATTACHMENT C

\ e BVPS-2 FSAR Prerequisites i- The applicable general prerequisites, as listed in l Section 14.2.12.1.1. are met.

Test Methods l

1. Prior to core load, the proper operation of each effluent monitor. including indication. alarms, and initiation of required control functions will be verified.

2. Monitor response to check sources and sample flow rates will be recorded.

3. During power ascension, effluent will be sampled and the effluent

. monitor perfo rmance will be verified through radiochemical analysis.

Acceptance Criteria  ;

1 The installed effluent monitors function in accordance with design specifications and properly indicate the radioactive content of the effluent.

14.2.12.61.3 Plant Radiation Survey and Verification of Shielding Effectiveness (IST)

Test objectives, To determine the effectiveness of the biological shielding and to verify the operability of area radiation monitors (ARMS).

Pr< requisites

• The plant is initially in operational mode 2 ($5 percent power ]

level). Parts of the test will be done in operational mode 1 J (50 percent and 100 percent power levels). l Test Methods 1: Radiation surveys will be made during steady state plant conditions at various power levels ()65 percent, 45-50 percent,95-100 percent) to determine gamma and neutron dose rates at preselected points.

2. The response of ARMS will be compated with the survey instrument readings.

Acceptance Criteria

1. Radiation levels are within the limits for the zone designation' l of each area surveyed.

l Amendment 11 14.2 128 January 1986

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