ML19290C610
| ML19290C610 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/09/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001220167 | |
| Download: ML19290C610 (8) | |
Text
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UNITED STATES
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NUCLE AR REGULATORY COMMISSION E
WASHINGTON. D. C. 20555 0
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NOV 9 1979 MEMORANDUM FOR:
A. Schwen er, Chief Operating Reactors Branch di Division 01 Operating Rea ' ors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
POINT BEACH 1 AND 2 - INSERVICE TESTING PROGRAM Plant Name: Point Beach, Units 1 and 2 Docket Nos. : 50-266, 50-301 Responsible Branch: OR3=1 Project Manager:
C. Trammell Review Brancnes: Plant Systems Branch Reactor Safety Branch Description of Task: Review and evaluate Point Beach 1/2 Inservice Testing Program Review Status: Requesting additional information The ISI/T Review Group, Division of Operating Reactors, has reviewed, the Inservice Testing Program. The additional information is essential for tne completion of our review. Please request the licensee to have tne infor nation available for a meeting.
From past experience, we have found it necessary to arrange a meeting with the licensee to review in detail their response and to seek answers to additional questions that inevitably develop from our evaluation of their responses.
To expedite our review, it would be helpful for you to arrange a meeting with representatives at their plant for February 6 and 7, 1980.
/1/
L.hW
/ G. (ainas, Chief Plant Systems Branen Division of Opera:ing Reactors
Enclosure:
As stated Contac t:
A. Wang, X23338 cc: See next page 1785 088 9
8001220///
A. Schwencer NCV 3 7979 cc w/ enclosure:
D. Eisenhut R. Vollmer L. Shao W. Gammill C. Trammell C. Cheng G. Johnson A. Wang E. Adensam V. Nerses P. Check DBS 089
ENCLOSURE POINT BEACH NUCLEAR POWER PLANTS UNITS 1 AND 2 WISCONSIN ELECTRIC POWER COMPANY DOCKET NOS. 50-266 and 50-301 REQUEST FOR ADDITIONAL INFORMATION The folicwing are comments and questions on tne Inservice Testing Programs (IST) submitted by the Wisconsin Electric Pcwer Ccmpany for the Point Beach Nuclear Power Plants, Unit 1 on May 19,1977 and Jnit 2 on February 19, 1979. This rer;uest for additional information "n regards to the IST submittals is divided into four sections -
1.
General Cuestions and Comments - Pumps 2.
Specific Questicns and Comments - Pumps 3.
General Questions and Comments - Valves 4.
Specific Questions and Comments - Valves 1.
GENERAL QUESTIONS AND COMMENTS - PUMPS 1.1 Article IWP-1100 of Section XI of the Code states that Class 1, 2, and 3 pumps which are provided with an emergency power source are subject to inservice testing. Are there any pumps in the plant provided with emergency power that are not included in the IST program?
1.2 Table IWP-3100-1 lists pump speed as one of the parameters to be measured for a variable speed pump. The licensee does not list pump speed as a test parameter to be measured.
Are all the pumps listed constant speed pumps?
1.3 Table IWP-3100-1 requires that " Proper lubricant level or pressure be observed." Hcw is this requirement being met since the IST submittal makes no mention of performing this requirement?
2.
SPECIFIC CUESTIONS AND CCMMENTS - PUMPS 2.1 Hich Head Safety Injection Pumas (P 15A and 3) Page 1.1 2.1.1 What is the size of the test line and what is the expected
~
flow rate through the test line (percentage of total fics; rate) ?
2.1.2 What is the procedure for maintaining the water level in tne refueling water storage tank (RWST)?
2.2 Containment Soray Pumos (P IJA and 5) Page 1.3 2.2.1 Is tne suction line to tne refueling water s orage tank (RWST) si:ed so as to give tne pumo a ::nstant suction pressure?
O
. 2.3 Service Water Pumos (P 32A, B, C, 0, E, and F) Page 1.5 2.3.1 Are the pumps located in a fixed resistance system?
2.3.2 Will the pumps be tested individually?
3.
GENERAL QUESTIONS AND COMMENTS - VALVES 3.1 For all valves, provide information on the normal position and the emergency position of the valves.
3.2 For all Category A and B valves, list the limiting value for stroke time.
3.3 For check valves tested with the pump test, explain how it is determined, following the pump test, that the valve flapper has returned to its seat? Also, does the test provide a full flow test for the valves?
4.
SPECIFIC QUESTIONS AND COMMENTS - VALVES 4.1 Category A Valves. Provide exercise frequency for the follcwing valves listed in the IST program:
Val ve Val ve 816 DI-9 313 DI-10 Containment permanent test connection ( A-E)
WL-1786 WL-1787 Post-accident vent system valves 12 and 13 ( A-E).
Permanent test connection valve "B" ( A-E)
H -8 containment sample line ( A-E) 2 H -9 containment sample line ( A-E) 2 Post-accident containment ventilation valve No. 4 ( A-E)
Post-accident containment ventilation valve No. 6 ( A-E)
Post-accident containment ventilation valve No. 5 ( A-E)
Post-accident containment ventilation valve No. 7 ( A-E)
Val ve Val ve IA-35A 3244 IA-36A 3245 632 769 633 D-7 3&E 759A 3212 759B 1785 091 3213
. 4.2 Category B and C Check Valves.
The folicwing valves are listed in tne Unit 2 IST program. They are, however, not listed in the Unit 1 IST program:
Valve Val ve 842A and B (Cat. C) 8678 (Cat. C) 853A, B, C, and D (Cat. C) 889A and B (Cat. C) 854A and B (Cat. C) 852A and B (Cat. B)
Why are these valves missing from the Unit 1 IST program?
4.3 Category D Valves - Page 1.11.
Are there any explosive operated valves in tne IST program?
4.4 Valves 858A and B, Containment Soray Pumo Suction Check glves (Drawing 110E017)
The licensee states that it is impractical to test these valves as the piping desi;n does not allow design flow through the valves except when they are actually spraying into the containment vessel.
The containment spray pumps (P 14A and B) are tested monthly during periods when the plant is above cold shutdown conditions.
During these tests water is passed from the refueling water storage tank (RWST) through the valves 858A and B to the spray pumps and returned through a test line to the RWST. Why cannot the valves be tested together witn the pumps? What percentage of full ficw would pass througn the valves during such a test?
4.5 Valves 362A and 3, Containment Soray Pumo Discharge Check Valves.
( Drawing 110E017)
The licensee states that is impractical to test these valves other than the leakage test now being perfor-ed as the piping design does not allow design ficw through these valves except when they are actually spraying into the con tainment.
The valves are Category AC valves and CIV's.
The drawing 110ED17 shcws tnat a test line is located upstream of the valves 862A and 3 between these valves and the nor" ally 0;:en valves 868A and 3.
To test the valves 862A and 3 would require closing valves 268A and 3 and coening the normally closed valves 36aA and 3 in the test line. This can only ::e cone at refueling outages wnen tne system is not neeced. Why, treraf re, cannot the valves be at least part strokec during refueling outages? What percentage of full ficw would pass through the valves during sucn a test?
[7BS 092
. The licensee should also provide information on how the valve leakage test is being conducted.
4.6 Valves 842A and B, "A" and "B" Safety Injection Accumulator Discharge Check Valves (Page 1.11)
The licensee should provide additional information en why it is impractical to test these valves, and justify the basis for requesting relief from full-stroke exercising the valves.
4.7 Containment Isolation Check Valves The licensee should provide information on the radiation exposure received during testing of each of the following valves, to justify the impracticality of not testing these valves more than once a year because of radiation exposure.
Val ve 767
- Component Cooling System 755A and B - Component Cooling System 304C and 0 - Chemical and Volume Cont, ol Sys tem 370
- Chemical and Volure Control System 528
- Nitrogen Supply System 529
- Reactor Makeup Water Supply 4.2 Valves 33A and 34A, Instrument Air to the Containment.
Containment Isolation Check Valves (Page 1.26)
The valves 33A and 34A are not in the listing of category A containment isolation valves (CIV's) on page 1.7 of the IST program. The valves IA-35A and 36B are, however, listed as instrument air to containment check valves, category AC valves.
Should the valves 33A and 348 have been listed as IA-35A and 36A valves?
4.9 Additional Containment Isolation Valves (CIV's)
Valves 2017 and 2018 are main steam check valves and shown as CIV's on drawing M-201.
They are not included in the list of CIV's shcwn in pages 1.7 and 1.3 of tne IST program.
We recommend reviewing these valves for inclusion in :ne IST program.
4.10 Additional Category B Valves We recommend reviewing the following valves for.1nclusicn in the IST program:
)785 093 Valves 826A, B, and C (Motor operated boric acid tank isolation valves), shown on drawing 110E017.
Valve 2033 (Supply trip valve), shown on drawing M-201, sheet 1.
Valves 4000's (2) and 4001's (2) (Motor operated gate valves), located in the auxiliary feed pump discharge lines to the steam generators and shown on drawing M-217.
Valve 595 (gate valve), located in the nitrogen supply to the Pressurizer Relief Tank and shown on drawing 541F091.
Are the above valves safety related? If they are safety related, they should be included in the IST program.
4.11 Other Category B Valves The following valves are listed as category B valves:
Val ve SA-9
- Steam supply to radwaste system SA-10
- Steam supply to radwaste system Hcw are these valves safety related? If they are not safety related, they could be deleted from the IST program.
4.12 Additional Category C Valve We recommend reviewing the following valve for inclusion in the IST program:
Valve 867A (first off high head safety injection check valve), shcwn on drawing Il0E035.
Is the above valve safety related? If it is safety related, it should be included in the IST program.
4.13 Additional Catecory E Valves Although IWV-1300 of the 1974 Edition of Section XI of the ASME Soiler anc Pressure Vessel Code excludes valves used for opera-ing convenience and maintenance only from testing requirements, it is the staff's opinion and recom-mendation that any sucn valve which is in the normal or alternate ficw patn of cooling water of the ECCS system, from the scur:e to the reactor coolant pressure boundary, snculd ::e inc!uced in tne valve testing or: gram.
If the valve is nor : ally locked coen or closed, it snould be reflectet in the aragram and designated " Category E."
Tnis mcomencation also applie s to engineered safety systems wnicn are cesigned c remove decay neat from the reac cr 1785 U94
es
- core fcilcwing a loss of coolant accident.
Based on the above, determine if the folicwing valves located in the auxiliary feedwater system should be included in the IST program.
Val ve Valve 57 19 45 44 56 18 32 31 The above gate valves are located in the auxiliary feed pump discharge lines to the steam generators, as shown on drawing M-217.
4.14 The following category E valves are listed in the Point Beach 1 IST program; however, they are not included in the Point Beach 2 IST program.
Clarify the discrepancy between the two programs.
Valves a
841 A, B
- Drawing 110E017 878 B, D, E, F - Drawing 110E017 866 A, B
- Drawing 110E017 888 A, B
- Drawing 110E017 709 A, B
- Drawing 110E017 715 A, B
- Drawing 110E017 716 A, B
- Drawing 110E017 896 A, B Drawing 110E017 827 A
- Drawing 110E017 1785 095