ML19305E264
| ML19305E264 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/21/1980 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML19305E260 | List: |
| References | |
| 2-SU-1, NUDOCS 8004230238 | |
| Download: ML19305E264 (14) | |
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l APPENDIX C SPECIAL (LOW POWER) TESTS l
Requirements and Administrative Controls I.
Program j
II.
Requirements I
III. Documentation I
IV.
Attachments A.
Individual Training Record l
6 B.
Training Log j
i C.
Safety Evaluation i
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-- TSS, 8004230
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Program This concept and a program were discussed at the 236th meeting (December 6 - 8, 1979) of the ACRS with the NRC and TVA (Sequoyah Unit 1).
The purpose of these tests is to provide improved operator training and to develop additional experimental information on the behavior of a nuclear unit and its systems under transient conditions. The Special Test program includes the following:
1.
Natural Circulation Test (2-ST-8) 2.
Natural Circulation with Simulated Loss of Offsite AC Power (2-ST-9) 3.
Natural Circulation with Loss of Pressurizer Heaters (2-ST-10) 4.
Effect of Steam Generator Secondary Side Isolation on Natural Circulation (2-ST-11) 5.
Natural Circulation at Reduced Pressure (2-ST-12) 6.
Cooldown Capability of the Charging and Letdown Systems (2-ST-6) 7.
Simulated Loss of All Onsite and Offsite AC Power (2-ST-13) 8.
Establishment of Natural Circulation from Stagnant Conditions (2-ST-14) 9a.
Forced Circulation Cooldown (2-ST-7) 9b.
Boron Mixing and Cooldown (2-ST-15)
The special test number (2-ST __)
indicates the preferred order of performance. Tests 6 and 9a are performed at the beginning of the program. Test 6 will provide specific information concerning the l
CVCS capabilities and Test 9a will yield information to be used for l
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2-SU-1 Attachse u'_ 5.6 Page 3 of 14 other tests. Tests 1, 2, 3, 4, and 5 are all " basic" natural circula-tion tests and form the core of the program. Tests 7, 8, and 9b are more involved and should result in considerable knowledge with respect to facility performance.
Various letters to the NRC provide the commitments for this program.
The tests were developed fro.3 work performed by Westinghouse and TVA l
and are specific to North Anna Unit 2.
Generally, a test engineer will be assigned to perform these special tests and control the
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documentation. Operations personnel will participate and observe, as applicable, these tests consistent with the requirements of l
10CFR50, 10CFR55, and previous commitments.
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II.
Requirements These special tests will be conducted following the low power physics test program and at a thermal power level less than or equal to five (5) percent rated thermal power.
l The Operating License (NPF-7) for North Anna Unit 2 requires that the NSSS vendor (Westinghouse) and that the NRC both review these tests prior to the facility operating at a power level greater than zero (0) percent power.
Lessons learned will be applied to the Company-owned simulator in an effort to improve the modeling of natural circulation and to provide a benchmark for licensed operator training.
e Tests I through 5 are similar to nature and Test 6 does not impact the facility significantly. Therefore, Tests 1 through 6 will be performed at least once. Licensed Shift RO's and SRO's will partici-pate in one of the first five (5) tests and observe at least two (2) others in the series of Tests 1 through 6.
Participate used here means that personnel will be performing their normally assigned duties on the shift. This includes manipulation of controls and monitoring. Observe used here means that personnel will not be actively involved in participation.
Licensed Shift RO's and SRO's will participate in Tests 7, 8, 9a and 9b. It is expected that this will require that the tests be repeated several times.
2-SU-1.6 Page 5 of 14 Note that it may be possible to combine several tests because of common test conditions. Any combining will not be permitted where test results could be affected and a variance from the commitments on test program scope would result.
The following criteria are imposed:
1.
Tests should provide meaningful information; 2.
Tests should provide supplemental operation training; 3.
Tests should not pose undue risk to the public; 4.
Risk of plant damage should be low; and 5.
Post test radiation levels should not preclude implementation of future TMI-2 requirements.
Should a specific test not meet the above criteria or be unsuccessful, the specific test will be omitted from the program.
A final review of the test procedures will be conducted before performance by the applicable test engineer and operations personnel to assure familiarity with the test.
Existing administrative and procedural controls consistent with Technical Specifications and 10CFR50, Appendix B will be imposed.
Training records will be developed and filed appropriately for applicable individuals. The special tests will be reviewed before implementation by the SNSOC and after performance by the SNSOC and by the SyNSOC via a brief synopsis of test results.
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2-SU-1 Attachment S.6 Page 6 of 14 III. Documentation Each completed special test will be reviewed for completeness and critiqued by a test enginear. Participants and observers may comment on the appropriate training record provided with this procedure.
The SNSOC will review and comment on, when requited, each completed i
special test. Various attachments provided with this procedure l
provide for operatior training documentation. Each special test contains space for appropriate comments and conclusions.
For completeness, a copy of the individual training record should be attached to the applicable special test.
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2-SU-1.6 Page 7 of 14 IV.
Attachments A.
Individual Training Record B.
Training Log C.
Safety Evaluation
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Attachment A i
Individual Training Record I
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Date:
Time:
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2-ST-O OBSERVED O
PARTICIPATED t
Remarks:
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2-SU-1.6 Page 9 of 14 Attachment B Training Log 2-ST-Name **
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2-SU-1.6 Page 10 of 14-Training Log (Cont.)
2-ST-Name **
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10 11 12 13 14 15 i
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l Completed by
2-SU-1.6 Page 11 of 14 Notes:
2.
For all other tests, each licensed shift RO and SRO rust participate in one of Tests 2-ST-8, 9, 10, 11, and 12 and observe at least two of Tests 2-ST-6, 8, 9 l
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10, 11, and 12.
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Place a "P" in block for participate and "0" in block i
for observe.
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"**" List all licensed RO's and SRO's.
(Note Section II on requirements.)
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Attachment C Safety Evaluation 10CFR50.59 (a)(1)(iii) requires that for these special tests prior Commission approval is required since temporary Technical Specification changes are required to conduct these tests.
These proposed tests do not involve an unreviewed safety question.
The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report is not increased since these test procedures provide suitable test controls and a review of test prior to performance to gain familiarity will be conducted. Test conditions are such that a test may be suspended immediately. Appropriate reactor protection system trips will be operable.
(NIS trips are set conservatively low and manual reactor trip is available). Appropriate ESF equipment can be returned to service if warranted since these tests do not severly alter the facility status. The possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis report will not be created since core subcooling will be monitored and controlled by the test procedures. A wide range of RPS and ESF actuations will remain operable or can be restored to operable status in a timely manner. Additionally, the core will be operated at less than or equal to five (5) percent of j
rated thermal power. Appropriate review of these procedures by the NSSS vendor will provide for an independent review of test configura-tions. The margin of safety as defined in the basis for any technical specification is reduced. However, this reduction is controlled by an approved procedure with minimal alteration of facil4ty status
2-SU-1.6 Page 13 of 14 For example, both emergency busses are deenergized. However, appropriate and i
timely operator action will reenergize these busses. Furthermore, for this case, since the reactor core is operating at less than or equal to five (5) percent of rated thermal power, a single failure during restoration will not severly affect the facility status if ESF actuation is required. Thus, while technically the margin must be reduced to conduct the test, there is sufficient:
i margin overall to preclude the existence of an unreviewed safety question.
The attached table provides further clarification of Technical Specification impact.
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1 TECHNICAL SPECIFICATION IMPACT GRID l
TEST TECH SPEC 1
2 3
4 5
6 7
8 9a 9b C0fNENTS 2.1.1 x
x x
x x
x x
x x
2.2.1 x
x x
x x
x x
x OPAT+0 TAT x
x x
x x
x x
x x
x S/G LEVEL 3.1.1.3 x
x x
3.1.1.4 x
x x
3.3.2.1 x
x x
x x
x x
x x
x STEAM t2P x
x x
x x
x x
x x
x STEAM FLOW x
x LOW PRESSURE x
x x
x x
x x
x x
x AUX FEED i
3.4.4 x
x x
3.5.1.2 x
x x
x x
x x
x x
x
(
3.7.1.2 x
x 3.3.1.1 x
x 3.8.2.1 x
x 3.8.2.3
.x x
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