ML19098B426
| ML19098B426 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/29/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Case E, Reid R Office of Nuclear Reactor Regulation |
| References | |
| Serial No. 057 A/021177 | |
| Download: ML19098B426 (23) | |
Text
' e e VIRGINIA ELECTRIC AND POWER COMPANY.
RIOHMOND, VIRGINIA. 23261 April 29, 197T ,
R~;u.LAYD~Y aac~aJ HlE coei --
Mr. Edson.G. Case Serial No. 057 A/021177 Acting Director of Nuclear Reactor Regulation PO&M/ALH:das
.U. s*. Nuclear Regulatory Commission Docket No. 50-280 Washington, .D *. C. 20555 License No. DPR-32 Attn: Mr. Robert.W. Reid, Chief Operating Reactors Branch 4
Dear Mr. Case:
The Surry Unit No. 1 steam generator inspection program described in our letter serial no. 057 /021177 dated April 15, 1977 has been completed.
The results of this program are presented in Attachment 1 to this letter.
It is noteworthy that the inspection results are very similar to the re-sults of the Surry Unit Wo. 2 program which was completed in March, 1977.
A steam generator tube plugging pattern has been implemented as a re-sult of the inspection program. The criteria used to determine this pattern is identical to that previously used for Surry Unit No. 2 except that more tubes will be plugged to allow six effective months of operation. The tube plugging pattern and analysis are presented in Attachment 2 to this letter.
The inspection of Surry Unit No. 1 steam generators did not reveal any new or unknown phenomena r_egarding int_egrity. Therefore, the analyses re-garding safe operation under normal and accident conditions presented in our letter serial no. 353B/113076 dated March 21, 1977 ,* which your staff has al-ready thoroughly reviewed, apply to Surry Unit Wo. 1. Further, the perfor-mance of Surry Unit No. 2 since its startup on April .11, 1977 indicates that the models used to develop the tube plugging patterns are adequate.
Therefore, we.request that Surry Unit ijo. 1 be permitted to operate as follows:
. . 1. Unit No. 1 shall be brought to the cold shutdown .condition in order to perform an inspection of the steam generators within six equivalent months of operation. Nuclear Regulatory Commission approval shall be obtained before resuming power operation following this inspection. For purpose of this re-quirement, equivalent operation is.defined as operation with a primary coolant temperature greater than 350 d_egrees - .F.
VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Edson.G. Case Page 2
- 2. Primary to.secondary. leakage through.the steam generator tubes shall be limited to . 0. 3_ gpm per steam generator.
With any steam generator tube leakage greater than this limit the reactor shall be brought to* the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The leaking tube(s) shall be evaluated and pl°:gged prior to resuming power operation .
. 3. Reactor operation will be terminated if the primary to
.secondary leakage limit of. 0.3 gpm per steam generator is exceeded twice in any 20 day period. Nuclear Regulatory Commission approval will be.obtained before resuming reac-tor operation *
. 4. The concentration of radioiodine in the primary coolant shall be limited 1 microcurie/gram dose equivalent I-131 during normal operation and to 10 microcurie/gram dose equivalent I-131 during power transients.
We believe.the operation of-Surry Unit J:,J'o. 1 as.described above will in no way endanger the health and safety of the general public.
Very truly yours,
- w. 2/J!? ,~~d~r
.C. M. Stallings Vice President-Power Supply and Production Operations Attachment cc: Mr. Norman:C. Moseley
VIRGINIA ELECTRIC AND POWER COMPA RICHMOND, VIRGINIA 23261 April 29, 1977 Mr. Edson G. Case Serial No. 057A/021177 Acting Director of Nuclear Reactor Regulation PO&M/ALH:das U. S. Nuclear Regulatory Commission Docket No. 50-280 Washington, D. C. 20555 License No. DPR-32 Attn: Mr. Robert W. Reid, Chief Operating Reactors Branch 4
Dear Mr. Case:
The Surry Unit No. 1 steam generator inspection program described in our letter serial no. 057/021177 dated April 15, 1977 has been completed.
The results of this program are presented in Attachment 1 to this letter.
It is noteworthy that the inspection results are very similar to the re-sults of the Surry Unit No. 2 program which was completed in March, 1977.
A steam generator tube plugging pattern has been implemented as a re-sult of the inspection program. The criteria used to determine this pattern is identical to that previously used for Surry Unit No. 2 except that more tubes will be plugged to allow six effective months of operation. The tube plugging pattern and analysis are presented in Attachment 2 to this letter.
The inspection of Surry Unit No. 1 steam generators did not reveal any new or unknown phenomena regarding integrity. Therefore, the analyses.,re-garding safe operation under normal and accident conditions presented in our letter serial no. 353B/113076 dated March 21, 1977, which your staff has al-ready thoroughly reviewed, apply to Surry Unit No. 1. Further, the perfor-mance of Surry Unit No. 2 since its startup on April 11, 1977 indicates that the models used to develop the tube plugging patterns are adequate.
Therefore, we request that Surry Unit No. 1 be permitted to operate as follows:
.. 1. Unit No. 1 shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six equivalent months of operation. Nuclear Regulatory Commission approval shall be obtained before resuming power operation following this inspection. For purpose of this re-quirement, equivalent operation is defined as operation with a primary coolant temperature greater than 350 d.egrees - F.
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VIROINIA ELZCTRIC AND Pow1rn COMPANY TO Mr. Edson G. Case Page 2 _
_2. Primary to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator.
With any steam generator tube leakage great.er than this limit the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The leaking tube(s) shall be evaluated and p~ugged prior to resumiilg power operation.
- 3. Reactor operation will be terminated if the primary to secondary leakage limit of 0.3 gpm per steam generator is exceeded twice in any 20 day period. Nuclear Regulatory Commission approval will be obtained before resuming reac-tor operation *
.4. The concentration of radioiodine in the primary coolant shall be limited 1 microcurie/gram dose equivalent I-131 during normal operation and to 10 microeurie/gram.dose equivalent I-131 during power transients.
We believe the operation of Surry Unit No. 1 as described above will in no way endanger the health and s~fety of the general public.
Very truly yours,
.._.r ', . ') ,., ;,_**, - " '*
~/. / . .:. */ ( .*, ."27:c..t.:l~-<--<---r-~
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_C. M. Stallings Vice President-Power Supply.
and Production Operations Attachment cc: Mr. Norman C. Moseley
.~.
- e ATTACHMENT 1 SURRY UNIT NO. l STEAM GENERATOR INSPECTION PROGRAM RESULTS
- 1. U-Bend eddy current inspection All available tubes in all columns of rows 1-5 in each steam generator were inspected through the u-bends using eddy current techniques. No discernable flaw indications were found. Seven row two tubes and two row three tubes would not permit the eddy current probe to pass through the u-bend, but this is believed to be due to the small bend radius of row two and three tubes and the existence of some ovality. These tubes will be plugged as a preventive measure.
All eddy current results were carefully reviewed by Vepco and an inde-pendent consultant. No new or unknown phenomena were present.
- 2. Tube dent sizing and eddy current program A tube dent sizing and accompanying eddy current program has been accom-plished on the hot leg side of the interior tube lane region, the wedge regions and the patch plate region of each steam generator. No eddy-current flaw indications were present in any of the tubes inspected.
The dent sizing information for*each steam generator is presented on the enclosed drawings.
- 3. Photography and inspection program A photography and visual inspection program was accomplished through the lower handholes of each steam generator. The attached sketches show the condition of the lower tube support plate in each steam generator. The con"dition of the lower tube support plates is very similar to that* discovered in Unit No. 2 steam generators in February 1977. The upper tube support plates in all steam generators were inspected. The flow slot blocking devices were intact, and no detri-mental conditions were noted .. The photographs showing these conditions are not reproducible, but are available at the site for inspection.
- 4. Shell to wrapper annulus guaging program Shell to wrapper annulus measurements were made in Band C steam gen-erators. The data collected provides a representative sample to be used in correlating predicted and actual tube support plate expansion.
No detrimental conditions were noted during the program.
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Attachment 2 e
SURRY UNIT NOo 1 STEAM GENERATOR TUBE PLUGGiNG PATTERN AND BASIS The steam generator tube plugging pattern is presented in the attached drawings. This plugging pattern results in 18.5% of the steam generator tubes being plugged. This is within the 20% plugging level permitted by" the current approved EGGS analysis. The criteria for tube plugging and its basis are presented below.
- 1. Criteria
- a. All tubes which do not pass the 0.540 inch probe will be plugged.
- b. Additionally, for six (6) months operation, three (3) tubes beyond (i.e. higher row numbers) any tube in columns 15 to 80 which did not pass the 0.540 inch probe will be plugged; for such tubes in columns 1 to 14 and 81 to 94 four (4) tubes beyond will be plugged.
- c. All tubes which did not pass the 0.610 inch probe will. be plugged.
- d. The tubes in any column for which pl~gging under criteria (a), (b) or (c) above is implemented will also be plugged in the lower row numbered tubes back to the tube lane if not already *plugged,
- e. As a conservative measure, tubes completely surrounding all known leaking
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- f. Additional preventive plugging will be implemented for tubes R46C41 and R46-C54 in each steam generator, even though no eddy current indications were reported for these tubeso This action will be taken to alleviate concern for those unique - tube locations which are:
- 1. At the perimeter of the plate 2.* ;,Adjacent to a discontinuity (cut) in the plate created by the patch plate 3 *. Adjacent to plug ~elds in circulation holes.
- 2. Basis For Six Month Plugging Pattern Criteria stated in (b) for plugging the tubes beyond those which do not pass a 0.540 inch probe is based on the movement of the region of tubes which are severely dented. Figure 1 is an updated plot of tube hoop strain versus plate strains with the one Surry 2 leaker, which has been closely examined, superimposed on the plot. Based on this data~ as well the history of previous leak locations (with the exclusion of the patch plate leaks which are.treated separately), the movement of the 14% hoop strain contour is a good measure of the movement of the region of tubes which are severely dented. This movement is shown in Figure 2 which indicates the growth rate of strain contour without flow slot blocking device. This represents the conservative estimate of strain con-tour growth rate for Surry 1. The detailed discussion of this basis was presented in our letter serial no. 031B/011977 dated March 25, 1977.
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