ML18114A605
| ML18114A605 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/24/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 395, NUDOCS 7905290001 | |
| Download: ML18114A605 (16) | |
Text
I VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 24, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. A. Schwencer, Chief Operating Reactors Branch No.
Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
Serial No. 395 LQA/DWSj r:esh Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OPERATING LICENSES SURRY POWER STATION, UNITNOS. l AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 24 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company here-by resubmits an earlier amendment request dated December 30, 1976, in the form of changes to the Technical Specifications to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. l and 2.
The proposed changes are enclosed and have been designated as Change No. 24.
At the request of Mr. Don J. Neighbors, Surry*s NRC Project Manager, we are resubmitting the attached change.
The change supercedes our previous proposal in its entirety.
Our current submittal updates inservice inspection of the steam generator tubes to the program required by the Standard Technical Specification.
No amendment fee is attached. since application for this change was sub-mitted prior to March 1978.
The enclosed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee.
It has been determined that the request does not involve an unreviewed safety question.
Attachment:
Change No. 24 cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region I I Very truly yours, Wttft.t 0 C. M. Stal (Jifgs Vice President-Power Supply and Production Operations
,z9052 906D I f
COMMONWEALTH OF VIRGINIA CITY OF RiCHMOND
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Before me, a Notary Pub] ic, in and for the City and Common-wealth aforesaid, today person~lly appea~ed W. C. Daley, who being duly sworn, made oath and said (l) that he is Manager-Production Opera-tions, of the Virginia Electric and Power CompAny, (2) that he is duly authorized to execute and fl le the foregoing 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 nota1*ial seal this~J,clay of
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- My Commission expires _J.&.JaWl9-- :Zt:2,, J2~J __.
(SEAL)
SECTION 4*.16 4.17 4.18 4.19 5.0 5.1 5.2 5.3 5.4 6.0 6.1 6.2 6.3 6.4 6.5 6.6 e
TS-iii TITLE PAGE LEAKAGE TESTING OF MISCELLANEOUS TS 4.16-1 RADIOACTIVE MATERIALS SOURCES SHOCK SUPPRESSORS (SNUBBERS)
TS l~.17-1 FIRE DETECTION AND PROTECTION SYSTEM TS 4.18-1 SURVEILLANCE STEAM GENERATOR INSERVICE INSPECTION TS 4.19-1 DESIGN FEATURES TS 5.1-1 SITE CONTAINMENT REACTOR FUEL STORAGE ADMINISTRATIVE CONTROLS ORGANIZATION, SAFETY AND OPERATION REVIE\\.l' TS 5.1-1 TS 5.2-1 TS 5.3-1 TS 5.4-1 TS 6.1-1 TS 6.1-1 ACTION TO BE TAKEN IN THE EVENT OF TS 6.2-1 AN REPORTABLE OCCURRENCE IN STATION OPERATION ACTION TO BE TAKEN IF A SAFETY LIMIT.
TS 6.3-1 IS EXCEEDED UNIT OPERATING PROCEDURES STATION OPERATING RECORDS STATION REPORTING REQUIREMENTS TS 6.4-1 TS 6.5-1 TS 6.6-1
TS 3.l-13a
- 6.
If the primary-to-secondary leakage through all steam generators not isolated from the Reactor Coolant System exceeds 1 gpm total and 500 gallons per day through any one steam generator not isolated from the Reactor Coolant System, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
TS 4.19-1 4.19 STEAi.~ GENERATOR INSERVICE INSPECTION Applicability Applies to the periodic inservice inspection of the steam generators.
Objective To provide assurance of the continued integrity of the steam generator pressure boundaries.
Specifications A.
Each steam generator shall be demonstrated operable pursuant to Specification 3.1.A.2 by performance of the following augmented inservice inspection program and the requirement of Specification 4.2.A.
B.
Steam Generator Sample Selection and Inspection -
Each steam generator shal.l be determined operable during shutdown by selecting and inspection at least the minimum number of steam generators specified in Table 4.19-1.
C.
Steam Generator Tube Sample Selection and Inspection -
The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in
TS 4.19-2 Table 4.19-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.19.D and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.19.E.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
- a.
Where experience 1.n similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
- b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- 1.
All nonplugged tubes that previously had detectable wall penetrations> 20%.
- 2.
Tubes in those areas where experience has indicated potential problems.
- 3.
A tube inspection (pursuant to Spe~ification 4.19.E.a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an
TS 4.* 19-3 adjacent tube shall be selected and subjected to a tube inspection.
c..
The tubes selected as the second and third samples (if required by Table 4.19-2) during each inservice inspection may be.
subjected to a partial tube inspection provided:
- 1.
The tubes sele~ted for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
- 2.
The in~pections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category C-1 C-2 Inspection Results Less than 5% of the total tubes inspected are degraded tubes and none of* the inspected
.tubes are defective.
One or more tubes, but not more than 1%
of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
TS 4.19-4 C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant> 10% further wall penetrations to be included 1n the above percentage calculations.
D.
Inspection Frequencies -
The above inservice inspections of steam generator tubes shall be performed at the following frequencies:
- a.
The fir.st inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result 1n all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional d2gradation has occurred, the inspection interval may be ext~nded to a maximum of once per 40 month~.
TS 4.19-5
- b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.19-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increas-ed to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.19.D.a; the interval may then be ex.tended to a maximum of once per 40 months.
- c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.19-2 during the shutdown subsequent to any of the following conditions:
- 1.
Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds).in excess of the limits of Specification 3.1.C.6.
- 2.
A seismic occurrence greater than the Operating Basis Earthquake.
- 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
- 4.
A major main steam line or feedwater line break.
[_*
TS 4.19-6 E.
Acceptance Criteria
- a.
As used in this Specification:
- 1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfec-tions.
- 2.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
- 3.
Degraded Tube means a tube containing imperfections
)20% of the nominal wall thickness caused be degradation.
- 4.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
- 5.
Defect means an imperfect ion of such severity that it exceeds the plugging limit.
A tube containing a defect is defective.
TS 4.19-7
- 6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.
- 7.
Unserviceable describes the condition of a tube if
- 8.
it leaks or contains a defect large enough to affect is structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.19.D.c, above.
Tube,Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
- 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed using the equipment and techniques expected to be used during subsequent inservice inspections.
- b.
The steam generator shall be determined operable after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.19-2.
TS 4,19-8 F.
Reports
- a.
Following each inservice inspection of. steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
- b.
The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed.
This report shall include:
- 1.
Numb'er:- and extent of tubes inspected.
- 2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3.
Identification of tubes plugged.
- c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specificatin 6.6 prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
TS 4.19-9 BASIS The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The unit 1.s expected to be operated in a manner such that the secondary coolant will be maintained within those parameter limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these parameter limits, localized.corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitatin of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage of 500 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operatin will have an adequate margin of safety to
-*~
TS 4.19-10 withstand the loads imposed during normal operatin and by postulated accidents.
Operating plant have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blo~vdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with the all volatile treatment (AVT) of secondary coolant.
However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam g 0 nerAt.or tube examinations.
Plugging will be required of all tubes with imperfections exceeding the plugging limit which, by the definition of Specification 4.19.E.a is 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.6 prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
TABLE 4.19-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Pre service Inspection No Yes No. of Steam Generators Two I Three I Four Two Three Four First Inservice Inspection All One Two Two Second & Subsequent Inservice Inspections Onel Onel One2 One3 Table Notation:
- 1.
The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner.
Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators.
Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
- 2.
The other steam generator not inspected during the first inservice inspection shall be inspected.
The third and subsequent inspections should follow the instructions described in 1 above.
~
- 3.
Each of the other two steam gemerators not inspected during the first inservice inspections shall be inspected during the second and third inspections.
The fourth and subsequent inspections shall follow the instructions described in 1 above.
TABLE 4.19-2 STEAM GENERATOR TUBE INSPECTION 1st SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required Result Act ion Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A s Tubes per S.G.
C-2 Plug de feet ive tubes C-1 None N/A N/A and inspect additional C-2 Plug defective tubes C-1 None 2S tubes in this S.G.
and i~spect additional C-2 Plug defective tubes S = 3 ~
n 4S tubes 1n this S.G.
C-3 Perform action for C-3 result of first sample C-3 Perform action for N/A N/A C-3 result of first sample C-3 Inspect* all tubes in All o.ther
.None N/A N/A this S.G., plug defec-S.G. s are tive tubes and inspect C-1 2S tubes in each other S.G, Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second Prompt notification additional sample to NRG pursuant to.
S.G. are*
specificatin 6.6.
C-3 Additional Inspect all tubes S.G. is C-3 in each S.G. and plug defective tubes.
Prompt notification N/A N/A
- to NRG pursuant to specification 6.6.
Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection e