ML17083B860
| ML17083B860 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/03/1987 |
| From: | Ashar H Office of Nuclear Reactor Regulation |
| To: | Ballard R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16341E103 | List: |
| References | |
| TAC-62167, TAC-62168, NUDOCS 8703090088 | |
| Download: ML17083B860 (20) | |
Text
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~ 4 ENCLOSURE 3
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I lpC'pss Li ~ Ndl MEMORANDUM FOR:
THRU; FROM:
SUBJECT:
References:
Ronald L. Ballard, Chief Enaineerina Branch Division of PWR Licensina-0 David Jeng, Section Leader Structural 8 Civil Engineering Section Engineering
- Branch, DPLA Hans Ashar Structural 5 Civil Engineerina.Section Engineering
- Branch, DPLA MEETING NOTES:
MEETING WITH PATE ON THE SUBJECT OF MULTI-RACK IMPACT STUnIES, HIGH DENSITY SPENT FUEL RACKS FOR DIABLO CANYON, DOCKET g 50-275 AND 50-323 (TECH NOS: 62167 AND 62168) 1.
PGfiE submittal related to rack-to-rack interaction dated February 6,
- 1987, PGAE letter No. DCL-87-022.
2.
RAI related to Reference 1 from R. L. Ballard to Hans Schierling dated February 12, 1987.
The meetina was held at PGAE offices in San Francisco.
Hans Schierling coordinated the meeting.
Attachment 1 is a list of attendees.
- The, licensee responded to the RAI indicated in Reference 2 in chronoloaical order.
The responses are sumarized as follows:
1.
Rocking Springs:
The licensee's consultant (Dr. K. Singhl stated that the simplified model was developed for parametric studies related to the multi-rack impacts.
He further added that the model was similar to the one used by Dr. Ferguson in his analysis.
The rocking sprinas were not considered in either case.
- Moreover, he explained that the contribution of the rotational degree of freedom in the single rack rigorous analysis was due to the momentary lift-up of three support legs of the modelled rack; the contribution was about 20% of that of the translation motion.
He emphasized that this mode of rotational behavior can not be simulated in the two dimension analysis.
2.
Coefficient of Friction:
Dr. Singh stated that the coefficient of friction (ul used was 0.2, and was consistent with Dr. Ferauson's parameter, presumed to yield larger displacement and impact force.
The coefficient of friction of 0.8 was not used and it is possible that it could yield higher ratio of impact forces for multirack to those of a sinale rack.
He also explained that he could not extrapolate the results of the impact forces determined by using u
0.2 to those using u
0.8, due to the non-linear behavior.
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Fluid Coupling:
The mechanism of fluid flow around the racks was explained by Dr. Burton Paul of the University of Pennsylvania, who is consultant to Holtech International.
He presented the discussion related to fluid coupling effect for a single row of racks and for racks with adiacent rows of racks.
By equating the fluid kinetic energies for systems with and without adiacent rows of racks, Dr. Paul had determined that in order to account for the presence of adjacent rows of racks the spacing to the fixed adiacent rows of racks to be considered would be 1.3 times the actual spacing.
Furthermore, he indicated that the addition of more adiacent rows of racks would not make significant difference in the spacing consideration.
Tn the above derivations, Dr. Paul had assumed the adjacent rows of racks to he fixed when the modelled racks were undergoing displacements.
In response to a question on a specific case when the adjacent rows of racks move in phase with the modelled racks, Dr. Paul stated that he did not think that it would make much difference in the spacing consideration.
4.
Time-Histories:
Dr. Singh stated that the time-histories of displace-ments and impacts were not kept as they were looking for maximum impact values.
- However, he mentioned that it was possible to provide the values of maximum rack displacements and impacts for both the analyses.
After some discussions of these responses, the NRC staff and its consultant caucussed and formulated the following as the added request for information:*
1.
Compare the impact forces usino u
= 0.8 and u = 0.2 for (a> single rack, and (bl multiple rack, keeping the distance between adjacent racks constant.
2.
Using 7.5 in. distance for the two cases:
(al single rack and (b) multiple
- rack, compare the impact forces.
Include in your response the discussion of fluid coupling analyses as presented at the meetinq.
Also, address the influence to the impact forces of the modelled racks when the adiacent rows move (1) in phase,
{2) out of phase, and (31 fixed.
Attachment:
Attendance List cc:
See next page f
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g1 l'bg ans Ashar Engineering Branch Division of PWR Licensing-A See memo from R. Ballard to H. Schierling dated February 27, 1987 for expansion of the request.
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Ronald L. Ballard MAR 0 8 1987 cc:
C.E. Rossi J.
YicGurren S.
Varaa K. Fishman, FRC M. Schierlina Distribution:
Docket File PAEB Reading File PAEB Plant File HAshar
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Name Hans Schierling Henry J. HcGurren Burton Paul Kris Sinah Hike Tresler Bruce Norton Richard F. Locke George C. Sarkisian Hark Mayer Dave W. Ogden Scott Johnson George C.
Wu John K. McCall Charles 0. Coffer Joseph Hartore Howard Fishman Hans Ashar Shan Bhattacharya Ed Lowry Rich Ferguson Li
-. o= ~,t-.one;=es NRC/PG and E MEETINC Fe ruarv 8,
1987 Oraanization NRC/NRR NRC/OGC PG
& E/Holtec International PG
& E/Holtec International PG
& E PCi
& E/TENERA PG
& E PG
& E PG
& E PG
& E PG
& E/Bechtel PG
& E PG
& E PG&E PG
& E/TENERA NRC/Franklin Research Center NRC/NRR PG
& E Sierra Club Sierra Club
MAR Pg eggy Docket No.:
50-275, 50-323 MEMORANDUM FOR:
Steve Varga, Director PWR Project Directorate g3 Division of PWR Licensing-A FROM:
Charles E. Rossi, Assistant Director Division of'WR Licensing-A RE(UEST INVOLVING TECHNICAL SPECIFICATION CHANGE FOR DIABLO CANYON 1 AND 2 PRESSURE ISOLATION VALVES (TAC NOS.':
60829 AND 60830)
In a letter dated February 13, 1986, Pacific Gas and Electric Company submitted an application for a licensing amendment to change the Technical Specification for Diablo Canyon Units I and 2.
The amendment proposes to add pressure isolation check valves in the Safety Injection and the Residual Heat Removal systems to Technical Specification 3.4.6.2, "Reactor Coolant System Operational Leakage."
The amendment was submitted to comply with an NRC staff
- request, details of which are provided in an NRC meeting minutes dated December 9, 1985 and SSER 31.
The enclosed staff evaluation indicates that the Technical Specification change is consistent with applicable guidelines and is acceptable.
The SALP evaluation is also enclosed.
Enclosure:
As stated cc:
H. Schierling L.B. Marsh B.D. Liaw R. Bosnak
.'. Ballard V. Benaroya G. Bagchi K. Dempsey
Contact:
K. Dempsey X24362 CAgl08f Ngn8d B~/
Charles E. Rossi, Assistant Director Division of PWR Licensing-A Distribution:
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SUBJECT:
REQUEST INVO VING TECHNICAL SPECIFICATION CHANGE FOR DIABLO CANYO 1 AND 2 PRESSURE ISOLATION VALVES (TAC NOS.:
6 29 AND 60830)
'In a letter dated Februar 13, 1986, Pacific Gas and Electric Company submitted an application r
a licensing amendment to change the Technical Specification for Diablo Canyon Units 1 and 2.
The amendment proposes to add pressure isolation check valves in the Safety Injection and the Residual Heat Removal systems to Technical Specification 3.4.6.2, "Reactor Coolant System Operational Leakage."
The a
ndment was submitted to comply with an NRC staff
- request, details of which are provided in an NRC meeting minutes dated December 9, 1985 and SSER 31.
The enclosed staff evaluation indicates that the Technical Specification cha ge is consistent with applicable guidelines and
, is acceptable.
The SALP evaluation is also enclosed.
Enclosure:
as'tated
Contact:
K. Dempsey X24362 cc:
H. Schierling L.B. Marsh B.D. Liaw R. Bosnak R. Ballard G. Bagchi K. Dempsey Charles E. Rossi, Assistant Director Division of PWR Licensing-A Distribution:
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SAFETY EVALUATION REPORT LICENSE AMENDMENT REQUEST FOR DIABLO CANYON I AND 2 INVOLVING ADDITION OF CHECK VALVES TO TECHNICAL SPECIFICATION 3.4.5. 2, "REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE" DOCKET NOS.: 50-275 AND 50-323 In a letter dated February 13, 1986, Pacific Gas and Electric Company submitted a license amendment request (LAR) relative to addition of check valves in Table 3.4-1 of the Diablo Canyon Power Plant (DCPP) Units I and 2
Technical Specification 3.4.6.2.
This LAR proposes to add the following check valves to Table 3.4-1, "Reactor Coolant System Pressure Isolation Valves":
8949 A, B, C and D
RHR and SIS first off check valves from RCS hot legs SeaS A, B, C and D
8740 A and B
SIS second off check valves from RCS hot legs RHR second off check valves from RCS hot legs 8802 A and B
SIS to RCS hot legs isolation valves 8703 RHR to RCS hot legs isolation valve The licensee states that the initial surveillance for these valves will be performed prior to heatup following the first refueling for each unit, Subsequently, surveillance will be performed every refuelinq outage during startup and prior to returning the valve to service following maintenance, repair or replacement work on the valve in accordance with the Technical Specifications.
An added footnote to Table 3.4-1 states that, for flowpaths
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with three pressure isolation valves, at least two of"three shall meet the requirements of Specification 3.4.6.2.f.
Additiona'1 changes reflecting the new footnote were made to the Limiting Condition for Operation and Surveil-lance Requirements of Specification 3.4.6.2 to maintain consistency.
These changes were made by the licensee to comply with a staff request which is detailed in an NRC meeting minutes dated December 9, 1985 and the DCPP SSER 31.
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The Staff has evaluated this LAR in accordance with the guidelines of SRP 3.9.6 and the ASME Boiler and Pressure Vessel Code Section XI.
The staff also checked the LAR for consistency against the recommendations specified in the NRC meeting minutes dated December 9,
1985 and DCPP SSER 31, Section 5.2.8. 1, which called for the inclusion in Specification 3.4.6.2 of two check valves in series for both the Safety Injection and the Residual Heat Removal Systems to ensure adequate isolation between the Reactor Coolant System and the lower pressure support systems.
Because these plants have three valves in series which isolate these
- systems, the LAR calls for demonstration of operability in any two out of the three valves.
The staff review indicates that these changes proposed by the licensee are consistent with applicable guidelines.
On the basis of this review, the staff concludes that the Technical Specification changes are in accordance with guidelines of (I) SRP 3.9.6, (2) the ASME Boiler and Pressure Vessel Code,Section XI, and (3) the staff request contained in the NRC meeting minutes dated December 9, 1985 and DCPP SSER 31, Section 5.2.8.1.
The staff therefore concludes that this LAR is acceptable.
LICENSEE:
PGE(E REVIBIER:
K. Dempsey, EB LICENSING ACTIVITY:
Management involvement in assuring quality REMARKS RATING EVALUATION CRITERIA 1.
Management Involvement and Control in Assuring Quality SALP REPORT
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Diablo Canyon, Unit 1 and 2
DOCKET NO.: 50-275, 50-373 TAC ¹: 60829, 60830 2.
Approach to Resolution of Technical Issues from a Safety Standpoint 3.
Responsiveness to NRC Initiatives 4.
Enforcement History NA Evaluation in support of the Technical Specification change was thorough and technically sound.
5.
Reporting and Analysis NA 6.
Staffing 7.
Training and Qualification NA Effectiveness Overall Rating for Licensing Activity Functional Area:
1
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Docket No.:
50-275, 50-323 MAR 09
$987 MEMORANDUM FOR:
Steve Varga, Director PWR Project Directorate P3 Division of PWR Licensing-A FROM:
SUBJECT:
Charles F. Rossi, Assistant Director Division of PWR Licensing-A RE(UEST INVOLVING TECHNICAL SPECIFICATION CHANGE FOR DIABLO CANYON 1 ANO 2 PRESSURE ISOLATION VALVES (TAC NOS.:
60829 AND 60830)
In a letter dated February 13, 1986, Pacific Gas and Electric Company submitted an application for a licensina amendment to change the Technical Specification for Diablo Canyon Units 1 and 2.
The amendment proposes to add pressure isolation check valves in the Safety Injection and the Residual Heat Removal systems to Technical Specification 3.4.6.2, "Reactor Coolant System Operational Leakaae."
The amendment was submitted to comply with an NRC staff request, details of which are provided in an NRC meeting minutes dated December 9, 1985 and SSER 31.
The enclosed staff evaluation indicates that the Technical Specification change is consistent with applicable auidelines and is acceptable.
The SALP evaluation is also enclosed.
Enclosure:
As stated cc:
H. Schierling L.B. Marsh B.O. Liaw R. Bosnak R. Ballard V. Benaroya G. Bagchi K. Dempsey
Contact:
K. Dempsey X24362 QriginsI Figaro 9~I Charles E. Rossi, Assistant Director Division of PWR Licensing-A Distribution:
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