ML18114A424
| ML18114A424 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/06/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904100305 | |
| Download: ML18114A424 (9) | |
Text
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e VIRGINIA. ELECTRIC Al'l"D POWER COMPANY RICHMOND, VIRGIN!~ 23261 April 6, 1979 Mr. Harold:R. Denton; Directbr Office of-Nuclear* Reactbr*Regulation Attn: Mr. Albert Schwencer*, Chief Operating Reactbrs Branch*l Divisirin of Reactbr Licensing
- U. :S* Nuclear Regulatory Commission*
Washington, pc* 20555
Dear Mr. Denton:
Serial No. 159 LQA/JEE:jab Docket* No *. 280 License No.
DPR-32 SURRY POWER STATION UNIT ONE
- pRQPOSED:AMtNDMENT'TO'OPERATING 1lICENSE Pursuant to 10 CFR ~0.90, the Virginia Electric and Power Com-pany hereby requests an amendment to Operating License DPR-32 for the Surry Power Station Unit No. :l.
The proposed cha_nge is to extend operation for an additional seven months from the completion of the current steam generator inspec-tion with the same conditions and limitations as issued in the December 29, l 978 Amendment CNo e 4(;i).,
- The Unit No. l steam generator inspection program began on March 15, l 979 and will extend to approximately to April 6, 1°979.
Fol-lowing this outage Unit l will be ret~rned to power for the duration of Amendment Nri. 46.
- Details of the inspection program are included in the attachment.
The inspection program is based on a deter~ination of.those regions of the tube sheet where *significant deformation of*tubes might have riccurr~d.
This determinatiori*1s based on experience gained iri previous inspections and on th.e growth.of the 1_7.5% strain boundary as developed by finite element analysts.
- The basic plugging criteria will be the same as used in previous inspections.
- The Station*and System Nuclear Safety and Operating Committees have contl uded that operation of Unit l for an additional seven months of equivalent full power operation under current NRC conditions would not be inimical to the h.ealth and safety of the publjc.
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e VIRGINIA ELECTRIC AND POWER toMPANY TO Mr. Harold;R. Denton 2
This requ~st has.. been evaluated in ~cc6rdance with the criteria specified in 10 CFR 170.~2. *rhe requested amendment is a clearly defined issue that has acceptao.ility*identified by NRG positions as seen in recent Orders involving steam generator~ inspectioQs. *conseq~ently, the request is therefore cons.i.dered to be a Class III, and a check, no. 12353, in the amount of$40QO.OO is attached.
cc:
Mr~ James:P. O'Reilly, Direct6r Attachments Very truly yours,
- C. :M.. Stallings Vice P~es.ident-Priwer Supply and Production Operations
e Replace paragraph 3.E in its entirety with the following:
E.
Steam Generator Inspection (1)
Unit No. l shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within seven months of equivalent operation from (date of Amendment issuance).
Nuclear Regulatory Commission (NRC) approval shall be obtained before resuming power ~peration following this inspection.
. Equivalent o-peratio~: i*s defined as opei:-ation w
__ i~h the.*
rea_CtOf CO bl anf at or *above 35QOj:".
- (2) Reactor coolant leakage from the reactor coolant system
. -(RCS) to-the -i;eco.ndary system.(SS) through* the: steanr ** *
- generator-tubes sha,,.-oe::nm-ited to o*. 3 gpm"pe'"r steam generator ~\\i:s ifescri beci" in th~- N-RC Safety *Evaluation
. of May 6; 1977. - With any steam generator tuoe
- 1 eakage greater than this limit the reactor shall be brought to the cold shutdown condition wiHdn 2"4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
N-RC approva 1 shall *be obtained before resurhi ng reactor operation.
(3)
Reactor operation sha-11 be terminated if RCS to SS leakage which is attributable to 2 or more.steam. generator tubes
- occurs during a 20 day period.
NRC approval shall be obtained before resuming reactor operation.
(4)
The concentration of radioiodine in ~he re~ctor coolant shall be limited to 1 µCi/gram DOSE EQUIVALENT Iodine-131 during normal operation and to 10 µCi/gram DOSE EQUIVALENT Iodine-131 during power transients as defined in Appendix A-1 to the Technical Specifications of the license. Appendix A:..1 was issued with the May 6, 1977 Order and shall remain in effect for se_ven equivalent months_ from (date of Amendment issuance).
Attachment SURRY UNIT NO. 1 STEAM GENERATOR INSPECTION PROGRA}1
- 1.
Eddy current testing of u.:...bends** as :follows*:.
- a.
Unplugged tubes in all steam generators rows, 2-5 columns 1-92 tested at 100 KHZ using beaded flex probe.
- b.
Any tubes which give indications at 100 KHZ will be re-exam1ned at 400 KHZ.
- 2.
As was done during the previous inspection (results forwarded in letter of December :~29*, *1978,:, Seri'al No. 703B), the.:centr-.al. area of -e:ach tube bundle will be inspected to the first support plate* to moni.tor 0. D.
wastage.. The extent' of these. inspections is. shown in Figures 2, 3 and 4 for steam. generators A, B, and C_, respectively.
- Note that* *on<F;i..gur~ 2, 3 and 4, 'the i:nner en~losed atea represents the ooundary of the previous Regulatory Guide 1. 83 inspection.. All tubes in this area: which show'ed ~.fa.stage of 20% *or greater in the.
previous inspection will be* inspected. ** This area is surrounded by a two tube boundary in which all tubes will be inspected.
- 3.
Tube* gauging will be conducted in the hot legs of all steam generators.
utilizing thtee different eddy*curreht probe sizes (0.540", 0.610", and 0.650 diameters).
Extent of gauging is indicated in Figure 1 (solid line).
NOTE:
During gauging, 400 KHZ lo'tv gain will be used.
4~
Tube gauging will be conducted in the cold legs of all steam generators utilizing probe sizes 0.610" and 0.540".
Extent of gauging is as indicated on Figure 1 (dotted line).
- 5.
- Wrapper to shell annulus measurements will be performed in steam generator C.
- 6.
Handhole inspections using TV and/or photographs will be perform~d to inspect flow slots.******
- 7.
Preventive plugging based upon inspection resuits.
I
-**---* -**-**--*- *" ______.. ______.. _______ ---~ -... *--**-*-*---*---****- -.------------*---**-**--*** -~--**-**-*--
SERIES 51 Figure 1.
Surry Unit 1 Gauging Program Hot leg - solid line Cold° leg -: dotted line.
**1
..:::a-MANWAY Figure 2.
SERIES 51 O.D. Wastage Inspection Surry Unit 1 Steam Generator A
-...... ~-***-* -*--*******---.. ***-~---*---*--***i----**-*-*-****
I COLUMNS NOZZLE-~
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SERIES 51
~-MANWAV NOZZLE--'>
Figure 3, O. D. Wastage Inspection Surry Unit 1 Steam Generator B
- ~--MANWAY*
.Figure 4.
SERIES 51 O.D. Wastage Inspection Surry Unit 1 Steam Generator C I
COLUMNS NOZZLE--t:>
e
COMMONWEALTH OF VIRGINIA CITY OF RICHMOND
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) s. s.
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Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared C~ M. Stallings, who being duly sworn, made oath and said (I) that he is Vice President-Power Supply and Production Operations, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
Given under my hand and notarial seal this 6...1:li. day of A Id¥" i I
, 1224-*
r My Commission expires (SEAL}