AECM-85-0212, Forwards Preliminary Data in Support of NRC Review of Safety Relief Valve in-plant Test Plan,Per 850626 Telcon.Addl Tests Unnecessary
ML20129E644 | |
Person / Time | |
---|---|
Site: | Grand Gulf ![]() |
Issue date: | 07/03/1985 |
From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
AECM-85-0212, AECM-85-212, TAC-57860, NUDOCS 8507170016 | |
Download: ML20129E644 (110) | |
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E6MMddB Helping Build Mississippi P. O. B OX 184 0 J A C K S O N, MIS SIS SIP PI 39215-1640 July 3, 1985 NUCLEAR LICENSING & SAFETY DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-29 File: 0260/0650 SRV In-Plant Test Plan, Additional Information AECM-85/0212 Mississippi Power & Light (MP&L) provided a summary of the Safety Relief Valve (SRV) test results conducted April 23 through April 25, 1985 at the Grand Gulf Nuclear Station (GGNS) by letter dated June 6, 1985 (AECM-85/0179). MP&L requested in this letter NRC concurrence with MP&L's position that no additional SRV testing is necessary. Additional information on this subject requested by the NRC staff was submitted by MP&L letter dated June 18, 1985 (AECM-85/0196). During a teleconference on June 26, 1985, the NRC staff requested further information regarding the GGNS test response spectra and comparison of GGNS with the Kuosheng Nuclear Plant test results. The attached information is provided in response to the NRC staff's request. This data should be regarded as preliminary and is submitted to support your review of the above referenced MP&L letters. A final comprehensive test report will be submitted as required by license condition 2.C.(34). As stated in AECM-85/0179, we believe the additional SRV tests would provide little additional information. In addition if the tests were to be performed, a plant shutdown and outage would be required to replace certain test valves which are currently exhibiting seat leakage. Further, the additional testing represents added duty on the SRV's and other components which would otherwise be avoided if additional testing is not conducted. 8 fDR507170016 850703 1 30 p ADOCK 05000416 PDR J13AECM85070302 - 1 Member Middle South Utilities System
e AECM-85/0212 Page 2 If we.can further assist your review of this matter, please contact this office. Yours truly, L. F. Dale Director MLC/JGC:vog Attachment cc: Mr. J. B. Richard (w/a) Mr. O. D. Kingsley, Jr. (w/a) Mr. R. B. McGehee (w/a) Mr.'N. S. Reynolds (w/a) Mr. G. B. Taylor (w/o)' Mr. R. C. Butcher (w/a) Mr. James M. Taylor, Director (w/a) Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a) U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia- 30323 J13AECM85070302 - 2
Page 1 of 5 CGNS SRV IN-PLANT TEST PRELIMINARY INFORMATION BASED ON RECORDED DATA REDUCTION
- 1.
Background:
A summary of the SRV in-plant test results conducted April 23 through April 25, 1985 at GGNS was provided to the NRC in the MP&L letter dated June 6, 1985 (AECM-85/0179). MP&L has concluded that all test objectives have been met and additional testing to complete the test matrix is not necessary. The NRC concurrence was requested for the conclusion of the SRV in-plant testing. The additional information requested by the NRC Staff to support their review on this subject was provided in the MP&L letter dated June 18, 1985 (AECM-85/0196). In a teleconference held on June 26, 1985, the NRC Staff requested further information based on reduction of the recorded data in progress. The information provided here is preliminary since DC offsets, ringing effects, and noise responses have not been eliminated from various response spectra plots.
- 2. Instrumentation Summary:
The thirty-two (32) pressure sensors installed in the Grand Gulf plant are shown in Figures 2.1, 2.2 and 2.3. The thirty four (34) strain gauges mounted in the plant are shown in Figures 2.4 and 2.5. The fifty-six (56) accelerometers installed in the plant are listed in Tables 2.1, 2.2 and 2.3, and are shown in Figures 2.6 through 2.11.
- 3. Test Results and Discussion 3.1 Suppression Pool Pressure Data The pressure data reported here was collected from sensors located on the basemat, drywell wall, and quencher supports. For each test, pressore sensors were located within a radius of 2r of the quencher to read peak bubble pressure.
A 100 Hz low pass filter was used in the playback to eliminate acoustic response, and provide results comparable to the analytical cut-off frequency used in the original plant design. The reduced pressures recorded for all tests, are presented in Table 3.1. 3.1.1 Single Valve Actuations (SVA) Three SVA tests have been completed. The peak measured pressures during SVA was +4.88/-5.78 psid. A statistical evaluation on the measured data, Table 3.2, produces a 95-95 peak pressure of
+5.37/-5.38 psid. These results compare very favorably with the design value of +18.2/-7.7 psid. Some typical pressure time histories for SVA are shown in Figures 3.1 through 3.5. The Power Spectral Density (PSD) plots are shown in Figures 3.6 through 3.10.
NMEREP 112 SRV IN-PLANT TEST
Pags 2 of 5 The pressure time histories at similar locations and PSD's for the Kuosheng test for SVA are shown in Figures 3.11 through 3.15. The pressure time histories and PSD's clearly show repeatability of the Grand Gulf SVA test and sufficient data has been collected to perform statistical evaluation. 3.1.2 consecutive Valve Actuations (CVA) Even though not originally planned and required by the NRC approved plan, the optional CVA tests were performed to provide infor-mation to confirm the adequacy of the Grand Gulf design for which the most limiting SRV loading is the CVA. Each SVA was followed by a CVA test. The peak measured pressures during CVA was +7.47/-4.47 psid. A statistical evaluation on the measured data, Table 3.3, produces a 95-95 pressure of +8.52/-4.62 psid. These results are easily bounded by the Grand Gulf CVA design value of +18.2/-7.7 psid (adjusted for the 75% power level test conditions). Some typical pressure time histories and PSD's for CVA are shown in Figures 3.16 through 3.25. Once again, repeatability of.the Grand Gulf CVA tests is clearly established and sufficient data has been collected to confirm the adequacy of the Grand Gulf unique design. The pressure time histories at similar locations and PSD's for the Kuosheng test for CVA are shown in Figures 3.26 through 3.29. 3.1.3 Multiple Valve Actuations (MVA) One MVA (4-valve) test was conducted at GGNS. The test program was temporarily suspended following the single MVA test because test valves were exhibiting seat weepage, as anticipated. Pressures measured during the MVA were less than or equal to those measured during various SVA's at GGNS. The peak measured pressures during MVA was +4.06/-2.60 psid. A statistical evaluation of the measured data, Table 3-4, produces a 95-95 pressure of +5.57/-3.46 psid. These results compare very favorably with the SVA results, and are well below the Grand Gulf design value of +18.2/-7.7 psid. Some typical pressure time histories and PSD's for MVA are shown in Figures 3.30 through 3.41. The pressure time histories at similar locations and PSD's for the Kuosheng test for MVA are shown in Figures 3.42 through 3.45. NMEREP 112 SRV IN-PLANT TEST
p. Page 3 of 5
'3.2 SRVDL and Quench'er Internal Pressures Pressure tranducers were located in the SRV Discharge Line (S RVDL) ,2 and in the quencher hub and arm, for quencher V-12 as ~s hown on-Figures 2.2 and 2.3. Pressure sensors P21 (SRVDL) and P23 (quencher hub) were recorded as real time datc. The peak line pressure observed was a high frequency spike with a magnitude of 450 psi, compared.to the 550 psi design. The peak 4-hub 1 pressure of 250-psi observed for both tests is less than half -
the design value of 550 psi. 13.3 Strain Data The measured strains for all tests, are presented in Table
-3.5.
The maximum recorded strain for the quencher support was 29
. micro in/in, which is equivalent to a stress value of 870 psi. The maximum recorded' strains for'the basemat and the containment liners are 50 and 46 micro in/in, which is equivalent to stress values of 1400 and 1300 psi, respectively. The maximum recorded strain for the submerged piping was 12 micro in/in, which is
- equivalent to a stress value of 360 ' psi.
_ Typical strain time histories are shown in Figures 3.46 through 3.49. Also, some typical equivalent stress time his-tories based on measured strains for the Kuosheng test are shown in Figures 3.50 and 3.51. The GGNS test strain data confirms the conclusions from the Kuosheng test results which showed that recorded strain data was always considerably less than expected values. 3.4 AcceIerometer Data The peak measured accelerations for all tests are presented in Table 3.6. There were twenty-six (26) accelerometers mounted on the Reactor Building structures and four (4) were mounted on the Auxiliary Building structures. Additionally, there were eleven (11) accelerometers mounted on equipment and fifteen (15) were mounted on valves and supports. i The peak measured accelerations at all locations are well below predicted and' design values. I i f-t
.NMEREP 112.SRV IN-PLANT TEST
Page 4 of 5
- 4. Response Spectra Response Spectra have been generated utilizing measured acceleration time histories for various locations in the Reactor Building. The enveloped spectra for SVA, CVA and MVA are presented in Figures 4.1 through 4.20. The corresponding Grand Gulf SRV design spectra are also plotted on these curves. Most of the spectra are entirely enveloped by the Grand Gulf SRV Design Spectra. In a few cases there appears to be some minor exceedance at very high frequency (approximately above 70 Hz) which will have very minimal, if any, structural responses.
For a quick comparison envelopes of SVA, CVA and MVA for the CGNS test results are plotted with those from the Kuosheng test results. The Grand Gulf and Kuosheng plant SRV design spectra for similar locations are also shown in these plots. These results are shown in Figures 4.21 through 4.30. The various node locations for the GGNS is shown in Figure 4.31. These results clearly show similarity between the GGNS and Kuosheng plant SRV test results and also show that most of the spectra are well below the design values.
- 5. Comparison With Kuosheng Plant SRV Test Data A comparison of the suppression pool pressure is presented in Table 5.1. The peak pressures observed at GGNS were considerably lower than those observed at Kuosheng for SVA, CVA and MVA tests. The pressure time histories at similar locations compare favorably with the Kuosheng results.
The measured strains on the basemat and the containment liners, the quencher supports and the submerged structures also compare favorably with those measured during the Kuosheng test which showed that equivalent measured stresses were always considerably less than their expected values. The enveloped spectra for SVA, CVA and MVA compare favorably with the Kuosheng SVA spectra at similar locations.
- 6. Conclusions Major conclusions drawn from the data reduction of the SRV test conducted at GGNS are as follows:
o The measured peak pressures during SVA, MVA and CVA are well below the GCNS design values. o The pressure time history data compare favorably to the GESSAR methodology. Air clearing / water spike is less pronounced at GGNS. The CVA time histories are very similar to that in GESSAR with the correct ratio of peak positive and negative pressures. NMEREP 112 SRV IN-PLANT TEST
Prge 5 of 5 o The measured strains in the basemat and the containment liners, the quencher supports and the submerged structures are considerably less than the predicted values. o The peak measured accelerations at all locations are well below predicted and design values. o The enveloped spectra for SVA, MVA and CVA are well below the CGNS SRV Design Spectra. o Based on the above it is concluded that the GESSAR methodology used for generating SRV discharge loadings is conserystive and there is considerabic margin in the CGNS design for SRV discharge loading.
- 7. Justification For Concluding The SRV In-Plant Testing One MVA test was conducted at CGNS. The four test valves used for MVA are located about 90* from one another. It was axpected that there would be very little interaction of hydrodynamic loa
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Table 3.7 PEAft MEASURED ACCELEllATIONS (0) (Concluded) SVA Tests CVA Tests Nean Value NA/UA NA/ A Sensor NVA Test De sig n Predicted MT10 MT20 MT30 MT70 MT11 MT21 MT31 SVA cvA Value value A30 0.001 0.001 0.001 0.002 0.00 0.001 0.001 0.001 0.001 N/A N/A A31 0.01 0.01 0.01 0.02 0.01 0.01 0.01 0.01 0.01 N/A N/A A32 0.01 0.03 0.02 0.02 0.01 0.01 0.01 0.02 0.01 N/A N/A A33 0.02 0.02 0.02 0.03 0.02 0.01 0.01 0.02 0.01 N/A N/A A34 0.01 0.02 0.02 0.03 0.01 0.01 0.01 0.02 0.01 N.A N/A A35 0.02 0.03 0.03 0.03 0.02 0.02 0.02 0.03 0.02 N/A N/A A36 0.02 0.02 0.03 0.03 0.03 0.01 0.02 0.02 0.02 N/A N/A A37 0.03 0.G 0.05 0.07 0.03 0.03 0,44 0.05 0.03 N/A N/A A38 0.03 0.03 0.03 0.05 0.02 0.02 0.03 0.03 0.02 0.36 0.29 A39 0.02 0.02 0.02 0.04 0.01 0.02 0.03 ?.02 0.02 0.41 0.33 A40 0.004 0.005 0.004 0.07 0.005 0.005 0.007 0.0G? 0.005 0.25 0.20 A41 0.05 0.07 0.11 0.21 0.08 0.10 0.09 0.08 0.09 N/A N/A A42 0.09 0.11 0.10 0.38 0.16 0.08 0.11 0.10 0.12 1.21 0.97 A43 0.06 0.1 0.12 0.15 0.12 0.14 0.11 0.10 0.12 1.59 1.27 A44 0.04 0.06 0.04 0.05 0.04 0.04 0.04 0.05 0.04 2.00 1.60 A45 0.01 0.02 0.01 0.03 0.01 0.03 0.02 0.01 0.02 2.01 1.60 A46 0.07 0.06 0.04 0.04 0.07 0.05 0.05 0.06 0.06 2.81 2.25 A47 0.30 0.50 0.45 0.38 0.30 0.13 0.14 0.42 0.19 2.01 1.60 A49 0.01 0.03 0.02 0.04 0.01 0.02 0.03 0.02 0.02 1.97 1.56 A50 0.05 0.04 0.01 0.02 0.04 0.03 0.01 0.03 0.03 2.52 1.80 ASI 0.13 0.10 0.03 0.06 0.13 0.06 0.03 0.09 0.07 1.20 0.96 l A52 0.16 0.18 0.04 0.06 0.15 0.08 0.03 0.13 0.09 2.84 2.27 l A53 0.01 0.02 0.02 0.04 0.01 0.02 0.02 0.02 0.02 N/A N/A i AS 4 0.01 0.02 0.02 0.03 0.01 0.02 0.02 0.02 0.02 N/A N/A l A55 0.01 0.01 0.01 0.005 0.01 0.003 0.004 0.01 0.01 N/A N/A l A56 0.004 0.005 0.004 0.003 0.003 0.002 0.003 0.004 0.003 N/A N/A 1 1 1
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Table 5.1 Comparison of Pressure During SRV In-Plant Testing for GGNS and Kuosheng Nuclear Plant (1) PLANT SVA NVA CVA DESIGN 95-95% +5.37/-5.38 +5.57/-3.46 +8.52/-4.62 +18.2/-7.7 GGNS Max./ Min. +4.88/-5.78 +4.06/-2.60 +7.47/-4.47 95-95 +7.62/-5.71 N/A N/A +16.6/-7.38 Max./ Min. +12.05/-7.15 +10.11/-8.89 +9.81/-9.44 NOTE: (1) All pressures are in paid i l l 4 i NMEREF 112 TA81.E 5.1
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