ML20058B441
| ML20058B441 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/25/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058B435 | List: |
| References | |
| NUDOCS 9010300202 | |
| Download: ML20058B441 (6) | |
Text
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l p'.%q[g UNITED STATES -
fg NUCLEAR REGULATORY COMMISSION -
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l W ASHINGTON D. C. 20555 i
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ENCLOSURE l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM ENTERGY OPERATIONS. INC.
.l GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416
1.0 INTRODUCTION
The Technical Specifications for the Grand Gulf Nuclear Station, Unit 1 (GGNS-1) state that inservice examination of ASME Code Class 1, 2, and 3 components 1
shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Comission.
The licensee submitted the first Ten-Year Interval inservice Inspection (ISI)
Program for the Grand Gulf Nuclear Station, Unit 1, by letters dated May ll, June 3, June 29 July 25, September 20, 1984, and October 31, 1985. The staff, with assistance from its contractor, Science Applications International Corporation (SAIC), reviewed and approved the program for the period from July 1, 1985, to July 1, 1995. The staff's Safety Evaluation for that review was issued on July 22, 1986. The ISI Program for the Grand Gulf Nuclear Station, Unit 1 is based on the examination requirements of.Section XI of the ASME Code,1977 Edition, including Sumer 1979 Addenda.
By letter dated July 9, 1990, the licensee submitted Relief Request 1-00018, Revision 1, which requested permission to perform the leakage test of the l
reactor coolant system boundary to the requirements of ASME Section XI Code, l
1983 Edition, Sumer 1983 Addenda. Regulation 10CFR50.55a(g)(4)(iv) permits updating to the examination requirements of later approved editions and addenda I
of the ASME Code subject to Comission-approval. The purpose of this Safety Evaluation is to evaluate Relief Request 1-00018, Revision 1.
2.0 EVALUATION t
Relief Request 1-00018 Revision 1 Code Requirement - ASME Section XI Code 1977 Edition, Sumer 1979 Addenda, requires that Class 1 Pressure Retaining Components, Category B-P, Table IWB-2500-1, receive:a system leakage test at each refueling outage (Paragraph IWB-5221) and a system hydrostatic test at each inspection interval (ParagraphIWB-5222).
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i Requested Relief - Request is made to perform leakage test of Class 1 Pressure Retaining Components Category B-P, Table IWB-2500-1, to the requirement of ASME Section XI Code, 1983 Edition, Summer 1983 Addenda.
A list of the portion of systems that' are examined by the VT-2 method in 1-00018 Revision 1, but excluded frompressurizationisasfollows:
ITEM SYSTEM LINE CLASS DESCRIPTION 1
B21 1" DBA-87 LINE DOWNSTREAM OF Q1B21-F136B 2
B21 1" DBA-87 LINE DOWNSTREAM OF Q1B21-F136A 3
B33 2" DCA-24 LINE DOWNSTREAM OF Q1833-F051A 4
B33 2" DBA-42 LINE DOWNSTREAM OF Q1833-F029 5
B33 2" DCA-24 LINE DOWNSTREAM 0F Q1833-F051B 6
C41 1 1/2" DCA-3 LINE DOWNSTREAM OF Q1C41-F219 7
C41 3/4" DCA-33 LINE DOWNSTREAM 0F Q1C41-F219 8
C41 1" DCA-34 LINE DOWNSTREAM OF Q1C41-F210 9
C41 1 1/2" DCA-2 LINE UPSTREAM OF Q1C41-F222 10 C41 1" DCA-34 LINE UPSTREAM OF Q1C41-F222 11 C41 3/4" DCA-4 LINE UPSTREAM 0F Q1C41-F222 12 C41 1" DCA-34 LINE DOWNSTREAM OF Q1C41-F218 13 C41 3/4" DCA-4 LINE DOWNSTREAM 0F Q1C41-F026 14 E12 6" DBA-32 LINE UPSTREAM OF Q1E51-F066 15 E12 1" DBA-80 LINE UPSTREAM OF 01E51-F066 16 E12 1" DBA-80 LINE DOWNSTREAM OF Q1E12-F344 17 E12 14" DBA-26 LINE UPSTREAM OF Q1E12-F041B 18 E12 1" DBA-81 LINE UPSTREAM OF Q1E12-F041B 19 E12 1" DBA-81 LINE DOWNSTREAM OF Q1E12-F236 20 E12 20" DBA-64 LINE DOWNSTREAM OF Q1E12-F009 21 E12 14" DBA-29 LINE UPSTREAM 0F Q1E12-F041A 22 E12 1" DBA-4 LINE DOWNSTREAM OF Q1E12-F223 23 E12 12" DBA-38 LINE UPSTREAM OF Q1E12-F041C 24 E12 1" DBA-79 LINE UPSTREAM OF Q1E12-F041C-25 E12 1" DBA-79 LINE DOWNSTREAM OF Q1E12-F234 26 E21 14" DBA-1 LINE UPSTREAM OF Q1E21-F006-27 E21 1" DBA-31 LINE UPSTREAM OF Q1E21-F006 28 E21 1" DBA-31 LINE DOWNSTREAM OF Q1E21-F207 29 E22 12" DBA-5 LINF DOWNSTREAM 0F Q1E22-F005 30 E22 14" DBA-5 LINE UPSTREAM 0F Q1E22-F005 31 E22 1" DBA-78 LINE UPSTREAM 0F Q1E22-F005 1
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l ITEM SYSTEM LINE CLASS DESCRIPTION l
32 E22 1" DBA-78 LINE DOWNSTREAM OF Q1E22-F218 33 E38 1 1/2" DBA-87 LINE UPSTREAM OF Q1E38-F002A 34 E38 1 1/2" DBA-87 LINE UPSTf'EAM OF Q1E38-F002B 35 E51 10" DBA-24 LINE DOWNSTREAM 0F Q1E51-F063 36 E51 1" DBA-34 LINE' DOWNSTREAM 0F.Q1E51-F076 37 G33 6" DBA-86 LINE DOWNSTREAM OF Q1G33-F250 38 G33 1" DBA-86 LINE DOWNSTREAM OF Q1G33-F241 39 G33 3/4" DBA-82 LINE DOWNSTREAM 0F Q1G33-F002 l
A summary of changes in Relief Request 1-00018, Revision 1, from components approved in Relief Request 1-00018, Revisior 0, is as follows:-
Relief Request J
Revision #1 Change Item No.
Requested Comments.
NA Delete item item No. 1 in Revision 0.
The associated valve is locked open during restart, therefore, relief is not appropriate.
11 Correct Description Item No. 7 in Revision 0.
The valve number is ccrrected.to Q1041-F222, 33 Changed to two items item No. 17 in Revision 0.
This was made into two separate items in Revision 1 for clarity.
To preserve system order in Revision 1, the following items-from Revision 0 were re-numbered:
1 Re-number item Item No. 3 in Revision 0.
3 Re-number item Item No. 5 in Revision 0.
l
O, Relief Request Revision 1 Change Item No.
Requested Comments j
5 Re-number Item Item No. 6.in-Revision 0,
)
7 Re-number item item No. 9 in.
Revision O.
16 Re-number item item No. 10 in Revision 0.
28 Re-number item-Item No. 11 in Revision 0.-
29 Re-number item item No. 15 in Revision 0.
30 Re-number item Item No. 16 in Revision 0.
4 32 Re-number item item No. 17 in Revision 0.
38 Re-number item item No. 13 in Revision 0.
39 Re-number item item No. 12 in Revision 0.
i 6,9,10,12-Add Items Relief is requested for 15,17-27,31, components in addition and 35-37 to those approved by Revision 0, due to the hardship of testing and to attempt to decrease Emergency Core Cooling-Systems downtime during refueling outages.
Relief would allow system leak testing in accordance with the 1983 Edition, Sunner 1983 Addenda of ASME Section XI rather than the 1977 Edition, Sunner 1979 Addenda. The items added by Revision I were determined by review of the current configuration-
. 3 1
Relief Request Revision 1 Change item No.
Requested Coments -
of the entire reactor 1
l coolant pressure boundary, including some systems not addressed for l
Revision 0.
The components added 'oy Revision 1 include some high pressure to low pressure interface 1
piping.
Basis for Requesting Relief - The Grand Gulf Nuclear Station's Inservice Inspection Program is required to be updated every Ten-Year period to the latest Commission approved edition of Section XI of. the ASME Code. The initial update will begin in 1994 and be implemented in 1995. At that time, the testing proposed by Relief Request 1-00318, Revision 1, is scheduled to become a part of Grand Gulf Nuclear Station's Insergice Inspection Program. Updating the Inservice Inspection Program to a later edition of the f.SME Code by this relief request accelerates the updating process for a part of.the program, and potentially reduces the downtime for the emergency core cooling system.
The 1977 Edition, Sumer 1979 Addenda, of Sr.ction XI of the ASME Code requires the test boundary for both the system leakrge and the hydrostatic test to include the entire reactor coolant system. This boundary, as defined, requires portions of piping to be pressure tested that are isolated by normally closed valves. To accomplish testing of'the isolated piping, extensive efforts are required that may include the installation of mechanical jumpers, initiation of false signals to open valves or the erection of independent water and pressure sources. Later editions of Section XI of the ASME Code have redefined the test boundary for the system leakage test as follows:
"The pressure retaining boundary during the system leakage test shall correspond to the reactor coolant system, with all valves in the normal position, which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include-the second closed valve at the boundary extremity."
In addition, the licensee stated that the request for altering the Class 1 system leakage test boundaries as discussed herein should be granted for the following reasons:
1.
All components excluded from the system leakage test are designed, fabricated, installed and tested to the requirements of ASME Section III, SubsectionHB(Class 1).
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2.
The components excluded from the system leakage test are subjected to the system hydrostatic test once each 151 interval.
l 3.
This request for relief is consistent with the current NRC approved edition of ASME Section XI (1983 Edition, Sumer 1983 Addenda).
Alternative Test'- None Evaluation-Regulation 10 CFR 50.55a(g)(4)(iv) permits updating to the examination require-ments of subsequent approved editions and addenda of the ASME Code, or portions thereof, which are incorporated by reference in 10 CFR 50.55a(b),. subject to the limitations and modifications listed therein and subject to staff approval.
The 1983 Edition, Sumer 1983 Addenda of the ASME Code is included in 10 CFR 50.55a(b) and none of the limitations and modifications listed therein are applicable to this relief request.
3.0 CONCLUSION
Pursuant to 10 CFR 50.55a(g)(4)(iv), the staff approves the requested performance of leakage tests in accordance with the examination requirements-of the 1983 Edition, Sumer 1983 Addenda of the ASME Code..Therefore the licensee's request is granted, i
Dated:
October 25, 1990 Principal Contributor:
F. Litton
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