3F1197-28, Forwards Addl Info to Clarify Matl Included in Attachment G to EDG Test Plan of .Info Does Not Alter Any Conclusions of TS Change Request Notice 210 & Ltr Contains Info Requested by NRC in 971028 Meeting.Commitments Encl

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Forwards Addl Info to Clarify Matl Included in Attachment G to EDG Test Plan of .Info Does Not Alter Any Conclusions of TS Change Request Notice 210 & Ltr Contains Info Requested by NRC in 971028 Meeting.Commitments Encl
ML20198P214
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/05/1997
From: Rencheck M
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F1197-28, NUDOCS 9711070026
Download: ML20198P214 (7)


Text

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Florida Power cowouta e

6 60 t November 5, i997 3FI 197-28 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Additional Information Provided for Technical Specification Cnange Request Notice 210

Reference:

FPC to NRC letter dated Septe.mber 25,1997 (3F0997-30) " Supplement to Technical Specification Change Request Notice 210" DCdr Sir:

Florida Power Corporation (FPC) hereby submits additional information to clarify the material included in Attachment G, Emergency Diesel Generator (EDG) Test Plan, of the above referenced letter. This additional information does not alter any conclusions of Technical Specification Change Request Notice (TSCRN) 210. This letter contains infonnation requested by your staff in a meetirig held at your offices on October 28,1997.

The NRC staff requested additional information concerning the number of starts and load runs to be performed on the EDGs. In the meeting, FPC confirmed that it would perform at least 22 starts and load-runs on the EDGs (13 load-runs on "A" EDG and 9 load-runs on "B" EDG) as part of the post-modification i testing. The details of this testing are described in Attachment B.

If you have any questions concerning this additional information to TSCRN 210, please contact Mr. David Kunsemiller, Manager, Nuclear Licensing at (352) 563-4566.

Sincerely, I

/

gL jf0 di M. W. Rencheck, Director Nuclear Engineering and Projects

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. . a -.ients P PDR Regional Administrator, Region 11 !k i i ,

, ,ce; iP G, ]~ Senior Resident inspector

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~ NRR Project Manager CRYSTAL RIVER ENERoY COMPLEX: 15760 W. Power Line Street + Crptal River. Hormia 34428 4708 e (352) 795-6486 A Rorkla Progress Company

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR 'D ADDITIONAL INFORMATION PROVIDED FOR TECHNICAL SPECIFICATION CHANGE REQUEST NOTICE 210 ATTACHMENT A LIST OF COMMITMENTS 1

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U.S; Nuclear Regulatory Commission Attachment A 3F1197-28 Page1 of1  ;

o i ATTACHMENT A .

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- List of Regulatory Commitments -  ;

i The following table identifies those action.e committed to by Florida Power Corporation in this-.

. document. Any other actions discussed in the submittal represent _ intended or planned actions oy l Florida Power Corporation.- They are described to the NRC for the NRC's information and are not -i regulatory commitments. Psease notify the Manager, Nuclear Licensing of any questions regarding -

. this document or any associated regulatory commitments.

. ID Number - Cornmitment - Due Date - i--

3F1197-28-1 A minimum of 22 combined EDO starts and load- Prior to MODE 4 entry from  ;

runs will be performed as described in this letter. the current outage r

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ADDITIONAL INFORMATION PROVIDED FOR TECHNICAL SPECIFICATION CHANGE REQUEST NOTICE 210 ATTACHMENT B ADDITIONAL INFORMATION CONCERNING THE EDG TEST PLAN

j U.S. Nuclear Regulatory Commission Attachment B 3F1197-28 Page 1 of 3 EDG OPERATION nFTER ENGINE AND RADIATOR MODIFICATIONS The following information was requested by the NRC o-ff. Questions are followed by FPC's response.

1) Define the FPC start and load test and how the number of start and load-runs are counted.

FPC has defined a Start Test and a Load-Run Test as shown below. These definitions were adopted from Sections 2.2.1 and 2.2.2 ofIEEE 387-1977.

Start Test: Demonstate proper startup from standby conditions, and verify that the required design voltage and frequency is attained. For these tests, the emergency diesel generator can be slow-started and reach rated speed on a prescribed schedule that is selected to mmimize stress and wear.

Load-Run Test: Demonstrate 90 to 100 percent of the continuous rating of the emergency diesel generator, for an interval of not less than I hour and until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power. The leading and unloading of an emergency diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.

FPC uses the following criteria for counting start and load-runs in the EDG test prog am. A run of one hour is considered sufficient to achieve temperature equilibrium. Fast starts with one hour of loading and hot starts with one hour of loading will be included in the count.

Slow engine starts from hot conditions with one hour of loading will also be counted, although none are presently planned. All load tests are performed above 2600 kW (greater than 90% of the continuous rating,2850 kW) with a typical load of 2700 kW.

All credited starts and load-runs have met the 9bove criteria except for one Train "A" EDG load-run which had a duration of 46 minutes. This run was terminated when the EDG was tripped due to an operator error. Although this load-run was less than an hour, the run was credited because the EDG had reached temperature equilibiium conditions. All planned EDG starts will be performed and will meet the above definition for stuts and load-runs.

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U.S. Nuclear R* gulatory Commission Attachment B 3F1197-28 Page 2 of 3

2) Provide a Table of start and load-runs that will be completed for each diesel after all of the modifications have been completed.

The testing described in the Table below occurs after EDG turbocharger /intercooler and radiator modifications are complete. Testing for the "A" EDG is being performed in two separate electrical train outages, therefore, the testing was split into two columns, " POST RADIATOR TESTING" and "UPRATE TESTING." The "B" Train EDG will be modified in a single electrical train outage. Therefore, " POST RADIATOR TESTING" and "UPRATE TESTING" will be done sequentially. Again, the number of start and load-run tests shown were performed or will be performed after completion of the turbocharger /intercooler and radiator modifications. ,

EDG POST RADIATOR UPRATE TESTING TOTAL TESTING TESTING Start & Load Hours Start & Load Hours Start & Load Hours EDG-1A 9 (notes 1 54.5 4 63 13 117.5 and 2) (note 2)

EDG-1B 5 37 4 63 9 100 (note 2) l Notes:

1. One POST RADIATOR load-run on EDG-1A was for 46 minutes, this run was credited even though it was less than the one hour. The EDG had reached temperature equilibrium conditions.
2. Values for EDG-1A POST-RADIATOR are actual values for the tests performed.

All other values are the minimum projected by the EDG test plan. All values for

! EDG-1B are the minimum projected by the EDG test plan.

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Attachment B 54 U.S. Nuclear Regulatory Commission 3F1197-28 Page 3 of 3

3) Confirm FPC's commitment to a cumulative number of start and load tests on both-diesels to demonstrate reliability of the diesel generator unit.

The above Table lists the actual and planned EDG starts and load-runs for the EDGs following the radiator modification. As can be seen from the Table, FPC will perform a total of 13 starts and load-runs on the A" EDG and 9 starts and load-runs on the "B" EDG for a cumulative total of 22 start and load-runs for both EDGs after completion of the ,

turbochargerrmtercooler and radiator modifications. FPC believes the EDG test plan, as described in the referenced letter, will adequately demonstrate EDG performance.

4) Note how many actual start and load tests have been completed to date as demonstration of the turbocharger /intercooler modifications and the radiator modifications.

As indicated in the Table, the actual number of start and load-run tests that have been performed to date on the "A" Train EDG is 9. All of the starts performed on the "A" EDG aller the radiator replacement were slow starts from engine ambient conditions except for one engine ambient fast start.

5) Confirm status of modifications at the time the tests will be done (i.e., scheduled anodifications complete, additional work will not affect results).

During the test program, the radiator fan clutch shoes were replaced on the "A" Train EDG. Seven of the start and load-runs for the "A" Train EDG were performed before this change and two were performed after this change. Replacement of the radiator fan clutch shoes does not affect the start and load-run capability of the EDG.

For the "A" EDG only, the radiator fan support shaft is planned to be changed to a different material prior to the uprate testing. The radiator fan support shaft will be the same size and configuration. In addition, the taper joints on the drive train will be tightened. These changes are being performed to conservatively establish additional design margin. These changes will not impact the start and load-run capability of the EDG. Four start and load-run tests will be performed after these changes.

The "B Train EDG will be modified in a single electrical train outage. Therefore, all 9 start and load-runs are planned to be performed after all radiator modifications are complete. The "B" Train EDG radiator may use water instead of antifreeze-water mix during the first few starts and load-runs, following the radiator modification, for the purpose of collecting data to optimize the use of antifreeze. The radiator fan pitch may also be adjusted. However, these changes will not impact the start and load-mn capability of the EDG.