ML17297A798
| ML17297A798 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/01/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| ANPP-18812-JMA, NUDOCS 8109100400 | |
| Download: ML17297A798 (27) | |
Text
REGULATOR~ NFORMATION DISTRIBUTION QTEM (RIDE)
ACCESSION NBR:810 FACILi;STN 50 528 STN"50 529 STN 50 530 AUTH',NAME" VAN BRUNTFEF.ED RECIP ~ NAME, TEDESCOFR
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- 9100400, DOC ~ DATE1: 81/09/01 NOTARIZED! YES Palo Ve'rde. Nuclear Stations Unit 1F Arizona Publi Palo Verde Nuclear StationF Unit 2F Arizona Publi Palo Verde-Nuclear Station~
Unit 3F Arizona Publi AUTHOR AFF ILIAT'ION Arizona Public-Service. Co.
RECIPIENT AF F IL1IATION Assistant Director for" Licensing DOCKEiT ¹ 05CEGZZtP 05000529 05000530
SUBJECT:
. Forwards responses to NRC 810714 L 0813 requests fori addi info'esponses will be'incorporated into FSAR amends DISTRIBUTION CODE:
B001S COPIES RECE1IVED:LTR ANGL SIZE'::
'ITLEI:
PSAR/FSAR AMDTS and Related Correspondence NOTES:Standardized Plant
~ 1 cy'.C Grimes Standardized Plant,i cy.'C Grimes Standardized Plant; 1
cy.'CA Grimes 05000528 05000529 05000530 RECIPIENT ID CODE/NAME(
ACTION:
A/D L'ICENSNG LIC BR ¹3 LA INTERNAL1: ACCID EIVAL BR26 CHEM ENG BR 11 CORE PERF BR 10.
EQ VIP QUAL BR'1 3 GEOSCIENCES 28 HYD/GEOA BR 30, IS,El 06 IE/EPLB 36" LIC'UAL BR 32'ECH ENG BR 18 OELD POi'E'ER SYS BR 19.
QA BR 21 REAC SYS BR 23i SI T ANAL BR 24 COPIES LTTR ENCLi 1
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RECIPIENT ID CODE/NAME L1I C BR ¹3 BC KERRIGANF JD 04 AUX SYS BR 27 CONT SYS BR 09 EFF TR SYS BR12'EMA"REP DIV 39 HUM FACT ENG 40 IEC SYS BR 16'E'/EPDB35 LC C QUID BR 33 MATLi ENG BR 17 MPA OP
- l. IC BR 34 PROC/TST, REV 20 RAD S
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P.o. BOX 21666 PHOENIX, ARIZONA85036 September 1, 1981 ANPP-18812-JMA/TFQ Mr. R. L. Tedesco Assistant Director fox Licensing Division of Licensing Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Palo Verde Nuclear Generating Stati (PVNGS) Units 1, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
81-056-026'G.l."10
Reference:
,(A)Letter from R. L. Tedesco, NRC, to E. E. Van Brunt, Jr.
dated August 13, 1981, subject:
Request for Additional Information and Draft SER Inputs (Materials Engineering Branch);{MTEB)
(B)Letter from R. L. Tedesco NRC, to E.
E. Van Brunt, Jr.
dated July 14, 1981, subject:
Request for Additional Infor-mation - PVNGS, (Core Performance Branch)
Dear Mr. Tedesco:
Attached are responses to NRC questions 121.1, from ref.(A), and 490.1 from ref.(B), for your use.
Note that Question 121.1 asked that we be consistent with NUREG-0212, rev.
1, but our response shows that ve vill be consistent with NUREG-0212, rev.
2.
These responses will be incorporated into the FSAR in a future amendment.
Please'ontact me if you have further questions on these matters.
Very truly ou s, e~
Cl u-<
E. E. Van Brunt, Jr.
APS Vice President, Nuclear Project ANPP Project Director EEVBJr/TFQ/bj Attachments cc:
J. Kerrigan (w/a)
P. Hourihan (w/a)
A. C. Gehr 8i09iooaoO ei090i PDR ADQCN 05000528 I
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STATE OP ARIZONA
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COUNTY OP MARICOPA)
I; Edwin E. Van Brunt, Jr., represent'hat I am Vice President Nuclear Projects of Arizona Public Service Company. that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that I have read such document
, and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
/
"~.
Edwin E.,Van Brunt, Jr."-"
Sworn to before me this'y of c
a v I
~
, 1981.
Ho ary Public My Commission expires:
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PVNGS RESPONSE'O QUESTION FROM CORE PERFORMANCE BRANCH NUCLEAR FUELS SECTION NRC UESTION 490.1 We note that the PVNGS,FSAR references Section 4,.2.3.1.2 of the CESSAR FSAR which, in turn, references the use of the analytical methodology from the CE topical report CENPD-178.
This report has not,been approved for licensing applications and is currently undergoing revision.
By letter dated March 23, 1981, CE has pro)ected the submittal of the revised report to be in the second quarter of 1981.
We anticipate that the revised report will present methods that conform to the requirements of NUREG-0609.
However, plant-specific results using these methods will be needed for PVNGS.
The PVNGS FSAR should thus provide the results of an analysis that demonstrates the ability of the System 80 fuel design to withstand combined seismic-and-LOCA loadings at the PVNGS site in accordance with the require-ments of NUREG-0609.
RESPONSE
According to CE, the revised CENPD-178 is scheduled for submittal to the NRC for review by September 1, 1981.
This report was revised in response to a Round Zero question asked on the CESSAR docket, STN-50-470, on March 23, 1979.
The methods delineated in the revised CENPD-178 will be applied to PVNGS to obtain plant specific seismic and LOCA combined loading structural analysis.
This plant spe'cific analysis will be submitted to the NRC for their review during the second quarter of 1982.
A discussion of the analysis results will be incorporated into the FSAR by a future amendment.
~
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~ t 121.0 Materials En ineerin Branch Inservice Ins ection Section K
121.1 Information supplied in FSAR Technical Specification Section 16.3/4.4.5 concerning steam gener'ator tube inspection is either incomplete, or inadequate.
In order to demonstrate compliance with NRC requirements, revise the following areas of this FSAR sections to be consistent with NUREG-0212, Revision 1, "Standard Technical Specifications for Comb'ustion Engineering Pressurized Water Reactors":
(1)
Change the wording with regard. to the first tube samples in section F 4.5.2.b to be consistent with the corresponding section in NUREG-0212; (2)
Change the wording with -regard. to the second.
and third. tube samples in Section 4.4.5.2.c to be consistent with the corresponding section in NUREG-0212; h
(3)
Include the additional requirements listed in NUREG-0212 regarding eddy current testing in Section 4.4.5.2.b.3; (4)
Change the wording in Section 4.4.5.3.b to be consistent with the corresponding in NUREG-0212; (5)
Include additional requirement listed in NUREG-0212 regarding preservice inspection in Section 4.4.5.4.a.9; (6)
Include additional, requirement listed in NUREG-0212 with regard. to
. the reporting requirements in Sections 4.4.5.5.a, 4.4.5.5.b, 4.4.5.5.c.
RESPONSE
The response is given in amended. section 16.3/4.4.5
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PVNGS FSAR 16.3/4.4.5 Steam Generators LIMITING CONDITION FOR OPERATION Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4
ACTION:
With one or more steam generators inoperable, restore the inop-erable generator(s) to OPERABLE status prior to increasing T
above 210F.
SURVEILLANCE RE UIREMENTS 1.
Steam Generator Sam le Selection and Ins ection.
Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in table 16.3/4.4.5-1.
2.
Steam Generator Tube Sam le Selection and Ins ection.
The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in table 16.3/4.4.5-2.
The inservice inspection of steam generator tubes.shall be performed at the freguencies specified in section 16.3/4.4.5 SR(3) and the inspected tubes shall be verified acceptable per the acceptance criteria of section 16.3/4.4.5 SR(4).
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 in 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.
16.3/4.4-4
PVNGS FSAR Table 16.3/4.4.5-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVXCE XNSPECTXON C
Inservice Inspection First inservice inspection Second and subsequent inservice inspections Number of Steam Generators To Be Inspected
[Later]
[Later]
16.3/4.4-5
1st Sample Inspection Table 16.3/4.4.5-2 STEAM GENERATOR TUBE INSPECTION 2nd Sample Inspection 3rd Sample Inspection Sample Size Result Action Required Result Action Required Result Action Required A minimum of S tybys per SG C-1 C-2 C-3 None Plug defective tubes and inspect addi-tional 2S tubes in this SG Inspect all tubes in this SG, plug defec-tive tubes and inspect 2S tubes in other SG N/A C-1 C-2 C-3 Other SG is C-1 Other SG is C-2 Other SG is C-3 N/A None Plug defective tubes and inspect addi-tional 4S tubes in this SG Perform action for C-3 result of first sample None Perform action for C-2 result of second sample Inspect all tubes in each SG and plug defec-tive tubes.
N/A N/A C-1 C-2 C-3 N/A N/A N/A N/A N/A N/A None Plug defective tubes Perform action for C-3 result of first sample N/A N/A N/A N/A a.
S
= (6/n)% where n is the number of steam generators inspected per unit.
zk
~e/
The fz.rst znservice inspection subsequent to the pre-service inspection) of each steam generator shall include:
Qyscck4~ g 2.
All nonplugged tubes that previously had detec-table wall penetrations
(>20%),
and Tubes in those areas where experience has indi-cated potential problems.
C.
on those po s of the tubes e second and third inservice than a
u be inspection by inspection on those a
inspections may b conce a.ng the e tube sheet array and w
tubes with rfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Ca~ecaor r
C-1 Ins ection Results Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 C-3 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.
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 in the above percentage calculations.
16.3/4.4-7
w
% ~
t
INSERT A to Page,"16.3/4.4-7 3.
A tube inspection (pursuant to Section 16.3/4.4.5.4.A.9) 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 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 16.3/4.4.5.2) during each inservice inspection may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections include those portions of the tubes where imper-fections were previously found.
Ins ection Fre uencies.
The above required inservice inspections of steam generator tubes shall be performed at the following frequencies.
A.
The first 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, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no addi-tional degradation has. occurred, the inspection interval may be extended to a maximum of once per.40 months.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in table 16.3/4.4.5-2 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 CESSAR Chapter 16, Section 3.4.6.2 LCO(C).
2.
A seismic occurrence greater than the operating basis earthquake.
3.
A loss-of-coolant: accident requiring actuation of the engineered safeguards.
4.
A main steam line or main feedwater line break with subsequent SG depressurization.
16.3/4.4-8
'1
INSERT B To Page 16.3/4.4-8 B. If the results of the inservice inspection of a steam generator conducted in accordance with Table 16.3/4.4.5.2 at 40 month intervals fall into Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Section 16.3/4.4.5.3.A; the interval may then be extended to a maximum of once per 40 months.
Acce tance Criteria.
A.
As used in this specification:
finish or contour required by drawing or specification.
2.
- wastage, wear, or corrosion.
tions
>20% wall penetration caused by degradation.
4.
De radation means the percentage of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity'hat it exceeds the plugging limit.
A tube con-taining a defect is defective.
6.
Plu in limit means the imperfection depth at or
~be ond which the tube shall be removed from service
~ ac+~ foe%
A v
..v MA ~/'fs.
(a) 7.,
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its 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 section 16.3/4.4.5 SR(3B).
8.
Tube ins ection 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.
a
~
o be determined in accordance with the re ea tions of Regulatory us-t 16.3/4.4-9
INSERT C To Page 16.3/4.4-9 9.
Preservice Ins ection 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 prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
PVNGS FSAR Figure 16.3/4.4.5-1.
Steam. Generator Tube Plugging Limit vs.
Tube Location I,Later]
16.3/4.4-10
The steam generator shall be determined OPERABLE after
~ completing the corresponding actions required by table 16.3/4.4.5-2.
ts.
The results of these steam generato vice inspections shal te nual basis for the P
period in whic spection was comp gppoam 1
Following each inservice inspection of steam generator
- tubes, the number of tubes plugged in each steam generator shall bh reported to the Commission within 15 days.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following com-pletion of the inspection.
This Special Report shall include:
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification
- 6. 9. 1 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.
16.3/4.4-11
'C