ML20244D069

Notifies That Review of Util 880913 Initial Simulator Certification Submittal Completed.Areas in Which Info & Data Inadequate to Ensure Complete Documentation of NRC Certifications Identified in Encl

ML20244D069
Person / Time
Site:	North Anna
Issue date:	04/13/1989
From:	Engle L Office of Nuclear Reactor Regulation
To:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 8904210128
Download: ML20244D069 (6)

Text

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' April 13,- 1989 Docket Nos. 50-338 DISTRIBUTION HBerkow and 50-339

%DocketMUe9 LEng1e-NRC & Local PDRs OGC (info. only)

PDII-2 Rdg.

EJordan, 3302MNBB SVarga,14/E/4 BGrimes; 9/A/2 Mr. W. R. Cartwright' Glainas, 14/H/3 ACRS(10)

Vice President - Nuclear DMiller BWilson Virginia Electric and Power Company 5000 Dominion Blvd.

Glen Allen, Virginia 23060

SUBJECT:

NORTH ANNA UNITS 1 AND 2 - SIMULATOR CERTIFICATION The staff has completed its review of your initial Simulator Certification submittal dated September 13, 1988. This review has identified several areas in which there is, as yet, inadequate'information and data to ensure complete documentation of our certifications. These areas are described in the enclosure.

You are requested to provide the additional data and your reply to the questions no later than May 31, 1989, so that this information may be promptly incorporated in the staff's records.

If you cannot meet this schedule, please contact me as soon as possible.

As indicated above, our review is only to ensure completeness of your documenta-tion. The review does not, nor is it intended to, verify the accuracy of the data or statements made in the certification, nor provide NRC approval of the accept-ability of a particular simulator for use in administering operat og tests.

If you require additional information or clarification about this letter or its enclosure, please contact me on (301) 492-1484.

i The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by 8904210128 8904]

on B. Ende, Wed Manage P

ADOCK 05000 38 Project Directorate 11-2 PDR PNU Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation l'

Enclosure:

As stated cc w/ enclosure:

See next page

[NA-1&2 SIMUL.CERTIFI T j(LTR]

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2 Pi 172 D:PDI -f

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r LEngle:bd HBerk sw 04/

89 04/12/89 04/ /89

Mr. W. R. Cartwright _

North' Anna Power Station Virginia Electric & Power Compan; Units 1 and 2 i.

cc:

Mr. William C. Porter, Jr.

C. M. G. Bu ttery, M.D., M. P.H.

County Administrator Department of Health Louisa County 109 Governer Street P.O. Box 160 Richmond, Virginia 23219 Louisa, Virginia 23993 Regional Administrator, Region II Michael W. Maupin, Esq.-

U.S. Nuclear Regulatory Commission Hunton and Williams 101 Marietta Street N.W., Suite 2900

'P. O. Box 1535 Atlanta, Georgia 30323 Richmond, Virginia 23212 Mr. W. T. Lough Virginia Corporation Commission Mr. G. E. Kane Division of Energy Regulation P. O. Box 402 P. O. Box 1197 Mineral, Virginia 23117 Richmond, Virginia 23209 Old Dominion Electric Cooperative c/o Executive Vice President Innsbrook Corporate Center

'4222 Cox Road, Suite 102 Glen Allen, Virginia 23060 Mr. W. L. Stewart Senior Vice President - Power Virginia Electric and Power Co.

Post Office Box 26666 Richmond, Virginia 23261 Mr. Patrick A. O' Hare Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Resident Inspector / North Anna c/o U.S. NRC Senior Resident Inspector Route 2, Box 78 Mineral, Virginia 23117 I

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ENCLOSURE 1.

Throughout Attachment 3, " Simulator Test Results," very few discrepancies were noted and in the " Transient Test Results" and " Malfunction Test Results" sections of this attachment, no discrepancies were noted.

However, in Attachment 8, " Discrepancy Backlog /and Resolution Schedule,"

167 discrepancies were documented as open items at the time of certification.

These included such seemingly important deficiencies as:

SMR NUMBER SYS DESCRIPTION 8803311115 CN (partial)"Condenservacuum doesn't change when steam to air ejectors is stopped."

8602141602 EL (partial) " Currently all recorders continue to operate during loss of power simulation."

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8703041700 FW "The energy balance of the FW heaters is not correct. After turbine trips heaters are not able to generate any heat transfer causing the feedwater temp to drop from approx 450 F to approx 75 F in a few seconds."

8710221300 IA "From 101 with I A containment TV's shut & no IA compressors running in the containment, air pressure does not decrease.

I understand the system in the simulator does not have leakage.

Air leakage is normal in all air sys & must be simulated with 1

some small amount!"

8703191050 HC "ECA0.0 requires operators to vent off H2 in main generator.

Unable to do.

Modify with a vent valve to depressurize (several other procedures also have you perform this evolution!)."

8509121534 PC

" Anytime core is aged to E0L conditions the AFD alarm comes in

& creates unnecessary problems.

It appears when you age the core it still looks at i

the BOL target & thus creates 1

this problem. **This situation needs to be corrected prior to NRC exams."

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' i SMR NUMBER SYS DESCRIPTION 8806060840 MS

" Simulation shows an excessive load decrease when main steam intercept & reheat stop valves.

are closed. The simulation shows 130MW decrease.

It should be I

around a 40 MW decrease."

8405160850 RD "During recovery of rod, in bank select C, drove rod bank in (with malf active) & reactor tripped on high power (spike). This action results in no actual rod motion

& therefore no reactivity change.

I.E. power spiked & should not have."

8704131235 TV (partial) " Malfunction causes trip, cycles turbine valves and wild plant response.

Should only cause low pressure alarm and start the stby. pump."

Please explain why the documented results of your performance testing appear to conflict-with the documented discrepancies. Also, please-provide a description of the baseline data used to determine fidelity to the reference plant.

If the baseline data used was the judgement of a panel of experts, then documentation of their review, sufficient for a third party to evaluate the adequacy of the tests and results, should be included. This documentation may include such items as the makeup and qualification of the panel and any differinc professional opinions as to the outcome of the tests.

4 2.

The " Steady State Stability" test at 100 percent power described on page 18 of Attachment 3 appears to be the only test performed for steady state operation.

ANSI /ANS-3.5-1985, Section 4.1, specifies the performance criteria for steady state operation and requires that "During testing, the accuracy of computed values shall be determined for a minimum of three points over the power range."

Please provide performance test abstracts for the tests required by ANSI /ANS-3.5-1985, Section 4.1 or provide justification for exception to these requirements.

3.

The " Full Power Trip and Recovery" test described on page 19 of appears to be intended to fulfill the requirement of ANSI /ANS-3.5-1985, Section 3.1.1(4), " Reactor trip followed by recovery to rated power." However, this test only returned the plant to hot standby conditions.

Please provide justification for exception to

" recovery to rated power."

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The tests described in Attachment 3 do not appear to include tests for ANSI /ANS-3.5-1985, Section 3.1.1 " Normal Plant Evolutions," items:

"(5) Operations at hot standby";

"(7) Startup, shutdown and power operations with less than full reactor coolant flow"; and

"(9) Core performance testing such as plant heat balance, determination of shutdown margin, and measurement of reactivity coefficients and control rod worth using permanently. installed instrumentation."

Please provide performance test abstracts for these tests or provide justification for exception to performance of these tests.

5.

Is the " Main Turbine Trip" test described on page 26 of Attachment 3 intended to satisfy the requirement of ANSI /ANS-3.5-1985, Appendix'B, item B.2.2(6), " Main turbine trip (maximum power level which does not result in immediate reactor trip)"?

If so, please confirm that 10 percent power is the " maximum power level which does not result in immediate reactor trip."

If not, please provide the performance test I

abstract for the test meeting this requirement or provide justification for exception.

6.

Upon review of the " Transient Test Results" and " Malfunction Test Results" in Attachment 3 it is not clear that.the simulator includes all of the " Plant Malfunctions" required by ANSI /ANS-3.5-1985, Section 3.1.2, especially items:

"(6) Loss of service water or cooling to individual components";

"(11) Loss of protective system channel"; and I

"(14) Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alarms."

Please confirm that the simulator includes all the malfunctions required by l

ANSI /ANS-3.5-1985 or provide justification (s) for any exceptions.

This may be done by providing a cross reference of the malfunction numbers to the malfunctions listed in ANSI /ANS-3.5-1985, Section 3.1.2.

7.

Are the " Periodic Tests" listed on page 85 of Attachment 3 inclusive of all " Operator conducted surveillance testing on safety-related equipment or systems" as required by ANSI /ANS-3.5-1985, Section 3.1.1, item (10)?

If not, please confirm that the simulator is capable of meeting this requirement or provide justification for exception.

8., the " Simulator Test Schedule," states "The Transient Performance Tests of ANS-3.5-1985 Appendix B section B.2.2 will be conducted annually." ANSI /ANS-3.5-1985, Appendix B, Section B.2.1,

" Steady State Performance" tests'are also required annually. Please confirm your intent to perform steady state tests as well as transient I

tests or provide justification for exception.

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. 9.

In Attachment 5, " Physical Fidelity Report," on page 5, Item 6 of the "Overall Control Room Items" indicates that the sound powered phone system is not-functional and will remain as such.

Also, in Attachment 5, on page 45, items 2 and 6 under " Shift Supervisor Console" indicate that other communications systems do not work., " Control Room /

Simulator Panel and Environment Comparison," on pages 14 and 15, in regard to the Shift Supervisor's Console, also indicates that some communications systems are not completely functional.

ANSI /ANS-3.5-1985, Section 3.2.3,

" Control Room Environment" requires that " communication systems that a control room operator would use to communicate with an auxiliary operator or other support activities shall be operational to the extent that the simulator instructor, when performing these remote activities, shall be able to communicate over the appropriate communication system." Please confirm that the simulator meets this requirement or provide justification for exception.

10. Attachment 6, on page 14, under " Plant Computer Station" states that "The reference plant computer station is fully simulated with the exceptions of some tasks that are beyond the scope of simulation." ANSI /ANS-3.5-1985, Section 3.2.2, " Controls on Panels," requires that "... plant computer interface hardware and other components or displays that would function during normal, abnormal, and emergency evolutions shall be included in the simulator."

Please confirm that this requirement is met or provide justi-fication for exception.

11. For Unit 2, two NRC Forms 474 were included in your submittal.

One was unsigned but had the box for exceptions checked. The other was signed but did not have the box for exceptions checked.

Please confirm that, for Unit 2, the Unit I simulator meets the guidance contained in ANSI /ANS-3.5-1985, as endorsed by NRC Regulatory Guide 1.149, without exception or provide justification for any exceptions taken.

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