ML20235R591
| ML20235R591 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/14/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 2NRC-7-175, TAC-63534, NUDOCS 8707210372 | |
| Download: ML20235R591 (4) | |
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M 2NFC-7-175 Beaver Valle /No. 2 Unit Froject Organization Telecopy (4 2 ' h 20 Ext.160 C.E.G. Building P.0, Box 328 July 14, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555
SUBJECT:
Beaver Valley Power Stetion Unit No. 2 Docket No. 50-412 BVPS-2 FSAR Chapter 14, Test Change Status Report Sentlemen:
Forwarded to NRC is a 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 Licease Condition C.(3).
DUQUESNE LIGHT COMPANY VJl./J. Care Senior Vice Prea dent i
I WRB/ijr l
NR/WRB/FS/CH14 Attachment AR/NAR cc:
Mr. P. Tam, Project Manager (w/a) l i
Mr. J. Beall, NRC Sr. Resident Inspector (w/a)
Mr. L. Prividy, NRC Resident Inspector (w/a)
INPO Records Center (w/a) l l
8707210372 870714 ii PDR ADOCK 05000412 g
P PDR 0
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BVPS-2 FSAR C_hapter 14 Test Change Status Report FSAR Section Title _
1.
14.2.12.58.01 Building Hot Water Heating System Test (SOV)
This test abstract requirements are being deleted as identified in Attach-ment A.
This system is non-safety related and adequately tested by Phase 1 Testing Group.
2.
14.2.12.8.16 Reactor Coolant System Flow Coastdown Test (IST)
Based on Westinghouse startup procedure DMW-SU-2.1.8 " Reactor Coole it Flow Coastdown" Revision 3 and BV2-SET-087 dated April 27, 1987, tri i, test abstract is being revised per Attachment B to measure RCS flow rate decrease only when all tnree RCS pumps are simultaneously tripped.
Westinghouse indicated, based on their experience and various analysis, that only the three (3) RCS pump trip should be tested and other pump conf.igurations are not necessary.
3.
14.2.12.25.3 and 4 Main Steam Isolation and Bypass Isola-tion Valve Performance Test (P0)
Pre-operational Test P0-2.21A.03, Main Steam Isolation and Bypass Isola-tion Valve Operability Test is written to meet the requirements of both test abstracts 14.2.12.25.3 and 4.
A previous FSAR commitment in ad-vertently stated that both test abstracts were to be completed prior to Mode 3.
Test abstract 14.2.12.25.3 (test sections VII A thru D) will be met prior to Mode 3, but test abstract 14.2.12.25.4 (test sections VII.E and F) will be met prior to 5% power per the original FSAR chapter 14 Initial Test Program Schedule (Amendment 13) due to initial testing condition requirements.
4.
14.2.12.75.01 Post-Design Basis Accident Hydrogen Control System Test (PO)
The ter,t written to meet this abstract, P0-2.46.01, was recently scheduled to be completed prior to Mode 3, however, it will not Le completed in time due to hardware problems in the system and manpower support.
Technical Specifications 3.6.4.1 and 3.6.4.2 state the applicable modes for both the hydrogen analyzers and hydrogen recombiner are Mode 1 and 2.
Based on Technical Specifications, the testing schedule commitment is being revised to require this test be completed prior to Mode 2.
1
l ATTACHMENT A J
14.2.12.58 Hot Water Heating System 14.2.12.58.1 Building Hot Water Heating System Test (SOV) w Test objectives To demonstrate the proper operation of the building hot water heating system.
k Prerequisites 4
{The applicable general prerequisites, as listed in Section 14.2.12.1.1, are met.
N N
Test Methods k
N 1.
Each hot water heating system pump will be tested to verify that the pump functions in accordance with design specifications and the cor. trol logic.
2.
The bypass flow control valve will be tested to verify that the valve will open to maintain minimum flow in the hot water heating l
system.
3.
The operability of the temperature control valves will be verified by monitoring heat exchanger outlet temperatures.
Acceptance criteria Proper operation of the building hot water heating system is demonstrated.
,/
Thi section has intentionally been deleted.
3 is
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ATT^CHMENT B 14.2.12.8.16 keactor Coolant System Flow Coastdown Test (IST) 5
' Test Objectives,
~
To measure the reactor. coolant system-(RdS) flow rate decrease r-subsequent to' reactor coolant pump -(RCP) trips.(atL various RCP G nfiW ration Q Prerequgites 1.
The plant is.in operational e. ode 3.
2.
The'RCS Flow Test is complete.
Test Methods S M UL78 N (**VS W Worg pt rWJtM K6 tu nWMfroAl 1.
?.t c ri;;: ?? :: fipr:ti:::, the RCPs will be tripped and the 4
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.
Accept'ence Crit 5ria The rate of reactor coolant flow decrease and associated trip delay--
times are in accordance with' design specifications.
I 1
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