ML20042F774
| ML20042F774 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/04/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005090376 | |
| Download: ML20042F774 (6) | |
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.4 TENNESSEE VALLEY AUTHORITY
~
CH ATTANOOGA, TENNESSEE 37401 SN 157B Lookout Place MAY041990 U.S.-Nuclear Regulatory Commission ATIN: Document Control Desk Hashington, D.C.
20555 Gentlemen:-
6 In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Autaority
)
50-328 SEQUOYAH NUCLEAR Pl. ANT (SQN) - COMPLETION OF THE EAGLE 21 VERIFICATION AND VALIDATION (V&V) A"TIVITIES This letter is to inform you of the completion of V&V activities associated with the SQN Eagle 21 process protection system upgrade. lNo significant disturbances were noted in the V&V activities from the time NRC completed its audit on April 20, 1990, and the completion of V&V.
From the total of 658 software verification problem reports, 22 were written since completion of the audit.
Ncne of these 22 required a coding change for resolution.
The validation activity resulted in 13 problem reports af ter the NRC audit. Of -
these 13, on'y one required a revision of software code.
This change was in.
the test secuence. processor analog input calibration routine.
The final version of the affected software has also been installed and tested in the Eagle 21 racks at SQN.
This-letter also provides as an enclosure-information concerning operability of Eagle 21 equipment in Mode 5.
This information supplements the information submitteJ by TVA's letter.to NRC' dated April 26, 1990.
The V&V final' report will-be transmitted by-future correspondence. Please direct questions concerning this issue to Russell R. Thompson at (615) 843-7470.
Very truly yoors.
TLNNESSEE VALLEY AUTHORITY b
(q vs E.G-Hallace,Nona.ger Nuclear Licensing and Regulatory Affoirs Enclosure cc: See page 2 O
9005090376 900504 h
PDR.ADOCK 0500032'7 i
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An Equal Opportunity Errployer
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.Vis. Nuclear Regulatory Commission-M 04 E
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cc'(Enclosure):
Ms. S. C. Black, Assistant Director forProjects.
TVA Projects Division U.S.-Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 q
NRC Resident Inspector l
Sequoyah Nuclear Plant i
2600.19o0 Ferry Road j
Soddy Daisy, Tennessee 37379 s
Mr., B.' A. H11 son, Assistant Director for Inspection Programs-TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900 i
Atlanta, Georgia. 30323-i l
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Westinghouse Energy Systems QSL,,,gy
_ Electric Corporation Mr. P. G. Trudel TVA-90-761 Project Engineer April 27. 1990 Tennessee Valley Authority Sequoyah Nuclear Plant F.0; Box 2000 Soddy Daisy, TN 37379-Tennessee Valley Authority Sequoyah Nuclear Plant Unit 1 Eaale-21 Mode 5 Onoration
Dear Mr. Trudel:
In response to TVA's recuest, Reactor Coolant System Wide Range Cold leg Temperature has been adced to the process protection channels required for Mode'5 operation at Sequoyah Nuclear Power Plant Unit 1.
This channel along with those previously addressed have been evaluated to provide supplemental information to address questions raised by the NRC staff with respect to Eagle-21 process protection channels required for Mode 5 operation at Sequoyah Nuclear Power Plant Unit 1.
The channels in question are Refueling Water Storage Tank Level. Rector Coolant System Wide Range Hot Leg Temperature. Reactor Coolant Sy' tem Wide Range Cold Leg Temperature and Reactor Coolant System Wide Range Pressure. Responses to
.the NRC staff questions are provided here below:
1._ For the subject channels, all units of code required for continuous on-line processing have completed software verification testing and for the remaining problem reports, final resolution will not require any code changes.
Also, for the subject channels, Validation testing has been successfully completed, the data has been evaluated and there were no test anomalies identified. Twelve (12) units of code remain to be re-verified for the Test Sequence Processor (tsp) subsystem and fourteen (14) units for the Man-Machine Interface (MMI).
The TSP subsystem and MMI have a passive relationship with respect to the processing of these channels. The TSP subsystem and MMI are electrically separated from and are only used to perform automatic surveillance test and provide diagnostic / monitoring capabilities-for the process protection system.
It is important to note that electrical power may be removed from the TSP subsystem and MMI with absolutely no impact to operation of the Loop Calculation Processor (LCP) subsystem, which is required for continuous on-line processing of the protection channels.
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For the overall Eagle-21 system for Sequoyah Nuclear Power Plant, the j
nature of the romaining verification closed may be categorized.as follows: problem-reports to be formally Remaining problem reports consist of approximately:
o 18% Generic a
11% Module Level "i
28% Type J (Header / Comments) p
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Q 17%TypeE(LogicAnomaly)
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7% Type G 0%TyseB((DataHandlingAnocaly)r
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Design Requirements Implemented. Incorrectly) 7./
13% Otaer p>
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.w.v All problem reports to-date have been screened to assure that-o none will cause an impact to the software currently installed at Sequoyah.
The current effort consists of completing the testing of the outstanding TSP and HMI code, and the formal close out of outstanding problem. reports.
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All problem reports associated with the loop calculation-o.
processor (LCP)anditsin)utshavebeenaddressedandthere-are-no open items which would qave any impact on code in place at Se,quoyah.
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3.
The software code. for the process channels' required to be operable for l
Mode 5 resides in LCP subsystem Programmable Read Only Memory (PROM)l components along with software required to process all other channels in the affected racks. However all LCP code has completed software verification testing.
II addition, Validation prudency tests have been completed to demonstrate that no adverse interactions exist between the. TSP subsystem, MMI and the'LCP. subsystems'These Validation prudency tests have also demonstrated that no interactions.
exist between the various channels which reside in the LCP subsystem.-
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In summary, it is concluded:
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s 1)
System validation testing for the subject process channels has been successfully completed.
L 2)
All software required for continuous on-line processing of the l'
subject channels has completed verification testing and code 1
changes are not required to close out remaining problem reports.
3)
The 26 units of code to be re-verified have no effect on the
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continuous on-line processing of the channels required for Mode.5 operation and.
4)
The process channels which are completing system Validation testing have no interactions with those channels required for Mode 5 operation.
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If any further clarification to the above is needed, or any other-information is required, we will be available to respond at your convenience.
i
-Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION B. J. 'arry,Managefj' TVA sequoyah Projec W customer Projects Department cc:
D. H.:Lafever R. G. Davis M. J. Burrynski 4
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