ML20195C989
| ML20195C989 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/04/1996 |
| From: | Cacciani G, Dometrovich A, Woessner K DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20195C987 | List: |
| References | |
| NUDOCS 9906090064 | |
| Download: ML20195C989 (21) | |
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ATTACHMENT 1 BVPS-2 CONTAINMENT PENETRATIONS :,
OVERPRESSURE PROTECTION ANALYSIS / REVIEW REPORT I
i Prepared by: 8 X Av w' /o/y/pg K. E. Woessner Date Reviewed by: .
. ro/4/qg i G. V. Cacciani ' D ate Reviewed by: &Ghd fo-y-%
V'A. J. Dometrovich Date Reviewed by: .
.do/4/6/o G. E. Mickinac Date Reviewed by: /d -f-N M. S. Ressler Date Reviewed by: I_G. S. RitzM /o-g-sg Date Approved by: Dd JJbM jo /4!9/,
' Date D. M. M)ff
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9906090064 990602 PDR ADOCK 05000334 P PDR ,
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- 1.0 - Purpose 4
ne purpose of this report is to summaria the Design Basis Accident (DBA) thermal ,
overpressure protection requirements for the Beaver Valley Power Station Unit 2 (BVPS-2) j i
containment penetrations. His report also documents compliance with the applicable design criteria and regulatory commitments. l 2.0 Executive Summary The adequacy of the Design Basis Accident thermal overpressure protection for BVPS-2 containment penetrations has been confirmed using a multi-discipline team approach, i.e., the BVPS-2 Containment Penetration Review Team. Design criteria and licensing commitments
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for these penetrations and associated piping systems are contained in the BVPS-2 Updated Final Safety Analysis Report (UFSAR), Code of Federal Regulations Title 10 Part 50 (10 CFR 50), Appendix A General Design Criteria (GDC) 54,55,56 and 57, American Society -
of Mechanical Engineers (ASME) Code Section III, BVPS-2 Technical Specifications and other related documents. These references were applied in the team review of the one-hundred twenty-eight (128) BVPS-2 containment penetrations utilized for piping and for access to verify and document their adequacy. It should be noted that penetrations for electrical equipment, which are gas-filled, are designed against the concem of thermal overpressure due to entrapped fluids and were, therefore, excluded from this review.
The BVPS-2 containment penetrations were grouped into ten (10) review categories based on their design.' A separate approach was established for each of the resiew categories to I i
document the method of regulatory and code compliance. The valve configuration of each j FMon was reviewed and field installations were verified, as rmss iy, tojustify each approach methodology. Administrative controls were also implemented to maintain the plant Page 1 of 20 l
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conditions necessary to assure penetration adequacy. These reviews were summarized on individual penetration review sheets and included such information as design requirements, I
overpressure protection / justification, short term and long term corrective actions, validation of
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i orientation and pressure relief path as well as references.
s 3.0 BVPS-2 Containment Penetration Design Criteria and Licensing Commitments Appendix A of 10 CFR 50 contains three (3) General Design Criteria, i.e., GDC 55,56 and 57, f
which establish the requirements for containment penetration design. These requirements define acceptable methods for provision of containment isolation valves. GDC 54 provides the requirements for piping systems penetrating contamment, such as for leak detection and j
isolation. BVPS-2 compliance with these GDC is stated in UFSAR Section 3.1, Conformance with U.S. NRC General Design Criteria, which references Section 6.2.4, Containment Isolation System.
UFSAR Section 6.2.4 provides the BVPS-2 design bases for containment isolation and describes the need and methods for providing thermal overpressure containment penetration protection. Based on information provided in this section, the design oasis for piping systems penetrating the reactor containment must meet ASME Code Section III Class 2, i.e., Safety Class 2, based on their use in protecting containment integrity. Containment isolation features are further summarized in UFSAR Table 6.2-60.
Design Basis Accident conditions similar to those utilized for the design of the BVPS-2 reactor containment were used for the evaluation of the containment penetrations.
Additional requirements for containment systems involving penetrations are provided in Technical Specifications 3/4.6.1.1, Primary Containment Integrity; 3/4.6.1.2, Containment Leakage; 3/4.6.1.3, Containment Air Locks; 3/4.6.3.1, Containment Isolation Valves and 5.2.3, Page 2 of 20
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Containment Penetrations. These Technical Specifications set operability conditions and design provisions for containment systems, including penetrations, which must be maintained in suppon of safe plant operation.
The cited design criteria and licensing commitments were reviewed and utilized by the BVPS-2 Containment Penetration Review Team in the performance of the containment penetration evaluations. Additional positions developed in support of the methodology to detennine design and regulatory compliance are included as Attachment 7.5 to this report.
4.0 BVPS-2 Containment Pene' ration Review Category Analysis Due to design similarities and plant configuration, the BVPS-2 containment penetrations were grouped into the following ten (10) review categories.
Review Total Category ;
Review Category Description Number of Number Penetrations
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l 1 Penetrations with Relief Valves as Thermal Overpressure Protection 24 i 2 Penetrations with Gas Medium . 20 3 Penetrations Maintained Drained 7 '
4 Penetrations Associated with Reactor Vessel Level Instrumentation System 6 5 Penetrations with Check Valves to Relief Valves 15 6 Penetrations with Check Valves and Downstream Isolation Valves 4 7 Penetrations with Open Ended Pipe Inside Containment 13 8 Spare Penetrations 27 9 Penetrations with Relief Valve / Check Valve to Spectacle Flange 6 10 Penetrations with Insulation Inside Containment Acting as Thermal Barrier 6 Individual penetration review sheets, which document the approach taken to establish design and licensing compliance, are included as Attachment 7.2 to this repon and are summarized as i
followsin this section.
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4.1 Review Category 1: Penetrations with Relief Valves as Thermal Overpressure Protection There were a total of twenty-four (24) containment penetrations in Review Category 1, including Penetrations X-1, X-2, X-4, X-5, X-14, X-20, X-21, X-24, X-25, X-27, X-28, X 29, X-38, X-45, X-55d, X-56b, X 56c, X-56d, X-57a, X-73, X-74, X-75, X-97c and X-106.
The penetrations in this review category are protected from overpressurization by thermal relief valves. The relief valve setpoints have been determined to provide adequate thermal reli4 protection.
For penetrations that have relief valves located inside containment, i.e., Penetrations X-1, X-2, X-4 and X-5, a 45 psig back pressure was added to the relief valve setpoint ta account for peak DBA containment pressure. It was concluded that the resulting penetration pressure increase would be enveloped by the Code allowable pressure.
For Penetration X-28, which has a relief valve located inside contamment, the relief valve has a compensating bellows, which eliminates the effect of any back pressure.
Relief valve setpoints for penetrations listed in Review Category 1 were verified to be within the tolerance band permitted by the ASME Code.
It was determined that the BVPS-2 containment penetrations listed in Review Category 1 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
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1 4.2 Review Category 2: Penetrations with Gas Medium
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i There were a total of twenty (20) containment penetrations in Review Category 2, 1
including Penetrations X-11, X-42, X-44, X-48, X-49, X 53, X-55a, X-55c, X 57c, X-59, X 90, X-91, X-92, X-93, X-94, X-97b, X-105a, X-105b,2PHS-PAL 1 and 2PHS-EAL1.
The penetrations in this review category are for systems that contain compressible fluid, i.e., not filled with liquid. Assuming ideal gas law behavior, the pressure will increase by a factor of 1.6 for a 300 degree Fahrenheit temperature rise. The increased pressure, which is a result of the thermal expansion of the fluid, will not exceed the Code allowable pressure, it was determined that the BVPS-2 containment penetrations listed in Resiew l Category 2 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
i 4.3 Review Category 3: Penetrations Maintained Drained There were a total of seven (7) penetrations in Review Category 3, including Penetrations X-65, X-99, X-101,X 103, X-104, X-116 and X 117.
Adequate thermal reliefprotection is provided with the penetrations in this resiew 1
category being maintained drained. With the penetration drained and isolated, refill of the containment penetration is not a concem. Administrative controls are in place to adequately maintain these conditions for each penetration in Review Category 3.
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- For Penetration X-65, containment isolation is provided by a blind flange and "O" rings on the containment end. Isolation of the fuel transfer tube is prosided by the blind flange and "O" rings on the containment end and a closed gate valve at the spent fuel pool end. Should leakage occur through the gate valve, overpressure protection is provided by the fact that this valve is not leak tight. For all other penetrations listed in Review Categon 3, a leak path would be required through the boundary valve and containment isolation valve or through one containment isolation valve to allow water to leak in and displace the air. Complete air displacement from the penetration is not credible due to the low flow rate and piping configuration. A leak path through the containment isolation valve will trap a volume of air in the containment penetration and intemal piping. This scenario would provide a compressible air volume in the penetration during a thermal event.
Assuming ideal gas law behavior, the pressure will increase by a factor of 1.6 for a 300 degree Fahrenheit temperature rise. With the containment penetration drained at ambient pressure, the resulting pressure will be less than design pressure.
It was detennined that the BVPS-2 containment penetrations listed in Review Category 3 are adequately designed and are in compliance with the applicable design codes andlicensing commitments.
4.4 Review Category 4: Penetrations Associated with the Reactor Vessel Level Instrumentation System (RVLIS)
There were a total of six (6) contamment penetrations in Review Category 4, including Penetrations X-119a, X-119b, X-119c, X-119d, X-119e and X-119f.
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In the event of a Loss of Coolant Accident (LOCA) with sufficient heat addition to the
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capillary tubing or inside containment high volume sensor to cause the contained fluid
. temperature inside the RVLIS capillary tubing to increase beyond the saturation point, overpressurization of the tubing and hydraulic isolator located outside of containment will be prevented by failure of the high volume sensor bellows.
Containment isolation is provided by the hydraulic isolator and associated capillary tubing located outside containment. NUREG / CR-2628 indicates that the hydraulic i isolator serves as the air isolation valve on the reactor containment building and provides a barrier to the release of containment atmosphere as utilized in the RVLIS application. Each of the six (6) RVLIS penetrations has its own hydraulic isolator and high volume sensor bellows.
It was detennined that the BVPS-2 containment penetrations listed in Review Category 4 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
4.5 Review Category 5: Penetrations with Check Valves to Relief Valves There were a total of fifteen (15) penetrations in Review Category 5, including Penetrations X-15, X-19, X-35, X-36, X-37, X-46, X-60, X-61, X-62, X-76, X-77, X-78, X-79, X-80 and X-83.
The penetrations in this review category are protected from overpressurization by check valves with no downstream isolation valves, i.e., a check valve opens due to upstream pressure and relieves through a relief valve. The reliefpath is through a relief valve to one of the following: Prr.ssurizer Relief Tank, Containment Atmosphere or Outside Containment Atmosphere.
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For penetrations that have relief valves located inside containment, i.e., Penetrations )
l X-15 and X-19, the relief valves have compensating bellows, which eliminate the effect .
of any back pressure.
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For penetrations that have a reliefpath to relief valves located inside containment, i.e., j Penetrations X-35, X-36, X-37 and X-46, a 45 psig back pressure was added to the relief valve setpoint to account for peak DBA containment pressure. It was concluded that the resulting penetration pressure would be enveloped by the piping design pressure.
For penetrations that have a relief path to safety valves located inside containment, i.e.,
Penetrations X-60, X-61 and X-62, a 45 psig back pressure was added to the safety valve setpoint to account for peak DBA containment pressure. It was concluded that the resulting penetration pressure would be enveloped by the piping hydro test presswe. ,
The relief valve and safety valve setpoints associated with penetrations listed in Review Category 5 have been verified to be within the tolerance band permitted by the ASME Code.
It was determined that the BVPS-2 containment penetrations listed in Review Category 5 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
I 4.6 Review Category 6: Penetrations with Check Valves and Downstream Isolation Valves i
There were a total of four (4) penetrations in Review Category 6, includmg i Penetrations X-7, X-17, X 34 and X-113.
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The penetrations in this review category are protected from overpressurization by check valves with downstream isolation valves, i.e., a check valve is the inside containment isolation valve and acts as the pressure relieving device. A high pressure condition between the check valve and the outside isolation valve will cause the check valve to open and re.lieve the pressure to the Reactor Coolant System. Each relief path from the check valves to the RCS contains a (NSA - Locked Throttled) isolation valve.
Verification of each valve's throttled position was identified as a short term corrective action, which will be completed to confirm the results of this analysis.
The Reactor Coolant System pressure is limited by safety valves. The safety valve setpoint has been determined to provide adequate thermal relief protection. It was concluded that if a 45 psig back pressure is added to the safety valve setpoint, to account for peak DBA containment pressure, the resulting containment penetration pressure increase would be enveloped by the piping design pressure. The safety valve setpoints associated with penetrations listed in Review Category 6 were verified to be within the tolerance band permitted by the ASME Code.
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It was determined that the BVPS-2 containment penetrations listed in Review '
Category 6 are adequately designed and are in compliance with the applicable de.dgn codes and licensing commitments, as documented in Attachment 7.5 to this report.
4.7 Review Category 7: Penetrations with Open Ended Pipe Inside Containment There were a total of thirteen (13) penetrations in Review Category 7, including Penetrations X-43, X-55b, X-57b, X-66, X-67, X-68, X-69, X-87, X-88, X 97a, X-105c, X-105d and X-118e.
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F The penetrations in this review category are protected from overpressurization by relieving the pressure to the containment atmosphere or to the containment sump.
These penetrations have an open ended pipe inside containment.
It was determined that the BVPS-2 contamment penetrations listed in Review Category 7 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
4.8 Review Category 8: Spare Penetrations There were a total of twenty-seven (27) penetrations in Review Category 8, including Penetrations X-6, X o, X-13, X-16, X-22, X-23, X-30, X-31, X-32, X-33, X-47, X-50, X-51, X-52, X-89, X-%, X-98, X-100, X-108, X-110a, X-110b, X-110c, X-110d, X 118a,X-118b,X-118e and X-118d.
The penetrations in this review category are spare penetrations and are not connected to any other plant system. These penetrations do not contain any fluid and are sealed at the inside contamment end, as verified by plant walkdowns. The penetrations have been rated for use with an anticipated system design pressure and temperature. In their current configuration, each spare penetration is designed to withstand the pressure and temperature analogous to those utilized for the design of the reactor containment structure.
It was determined that the BVPS-2 containment penetrations listed in Review Category 8 are adequately designed and are in compliance with the applicable design codes andlicensing commitments.
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4.9 Review Category 9: Penetrations with Relief Valve / Check Valve to Spectacle Flange There were a total of six (6) penetrations in Review Category 9, including Penetrations X-63, X-64, X-70, X-71, X-114 and X-115.
The penetrations in this review category are protected from overpressurization by their corresponding check valves opening and relieving pressure through a spectacle flange to the Quench Spray Header / Rings or Recirculation Spray Header / Rings. Each group of Spray Header / Rings contains open nozzles, which would allow relief to the containment atmosphere. Valve bonnet pressure reliefis also provided for the outside
- ontainment isolation Motor Operated Valves (MOVs), which either relieves to the Safeguards Building atmosphere or returns to the downstream piping and relieves i through the spectacle flange to the Recirculation Spray Header / Rings. Action has been taken to verify that the spectacle flange downstream of each check valve is in the flow position prior to entry into Mode 4. !
' It was determined that the BVPS-2 containment penetrations listed in Review i Category 9 are adequately designed and are in compliance with the applicable design codes and licensing commitments, as documented in Attachment 7.5 to this report. ]
4.10 Review Category 10: Penetrations with Insulation Inside Contamment Acting as Thermal Barrier There were a total of six (6) penetrations in Review Category 10, including Penetrations X 39, X-40, X-41, X-56a, X-57d and X-97d.
An engineering analysis has determined that the piping insulation for the penetrations in this category is adequate to prevent the overpressurization of this piping due to thermal i Page 11 of 20 -
heating. The analysis detennined that a delta temperature rise of 3 degrees Fahrenheit, for Penetrations X 39, X-40 and X-41, and 23 degrees Fahrenheit, for Penetrations X-56a, X-57d and X-97d, is expected in the fluid contained in the blowdown penetration piping during a DBA. This temperature rise in the fluid contained in the piping will not result in exceeding the Code allowable pressure. The insulation assumptions used in this analysis were verified by plant walkdowns.
It was determined that the BVPS-2 containment penetrations listed in Review Category 10 are adequately designed and are in compliance with the applicable design codes and licensing commitments.
5.0 Conclusions The adequacy of the DBA thermal overpressure protection for one-hundred twenty-eight (128)
BVPS-2 containment penetrations has been confumed by the BVPS-2 Containment Penetration
~e Review Team, as summarized in this repon and documented on the individual penetration review sheets, which are provided as Attachment 7.2 to this report. It was also determined that
.. the containment penetrations are adequately designed and are in compliance with the applicable design codes and licensing commitments. Shon tenn corrective actions have been evaluated and are summanzed in the BVPS-2 Penetrations List of Action items, which is included in this repon as Attachment 7.3. These are to be verified as complete prior to entry into Mode 4 for startup from the BVPS-2 Sixth Refueling Outage. Long term corrective actions have also been evaluated and are included in this report as Attachment 7.4. The long term corrective actions will be tracked via the Commitment Action Tracking System (CATS).
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6.0 References Isometric Drawings:
10080-2806.257-920-012 10080-2806.259-920-107 10080-2806.260-920-528 10080-2806.258-920-004 10080-2806.259-920-173 10080-2806.260-920-529 10080-2806.258-920-005 10080-2806.259-920-273 10080-2806.260-920-532 10080-2806.258-920-080 10080-2806.259-920-274 10080-2806.260-920-543
'10080-2806.258-920-082 10080-2806.259-920-275 10080-2806.260-920-553 10080-2806.258-920-151 10080-2806.259-920-292 10080-2806.260-920-600 10080-2806.258-920-152 10080-2806.259-920-375 10080-2806.260-920-662 10080-2806.258 920-153 10080-2806.259-920-407 10080-2806.260-920-702-10080-2806.258-920-266 10080-2806.259-920-533 10080-2806.260-920-703 10080-2806.258-920-301 10080-2806.259-920-561 10080-2806.260-920-704 10080-2806.258-920-308 10080-2806.259-920-662 10080-2806.260-920-706 10080-2806.258-920-356 10080-2806.259-920-699 10080-2806.260-920-708
,10080-2806.258-920-405 10080-2806.259-920-718 10080-2806.260-920-843 10080-2806.258-920-451 10080-2806.259-920-757 10080-2806.260-920-887
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10080-2806.258-920-485 10080-2806.259-920-845 10080-2806.260-920-989 '
10080-2806.258-920-573 10080-2806.259-920-916- 10080-2806.260-920-991 10080-2806.258-920-637 10080-2806.259-920-927 10080-2806.261-920-486 10080-2806.258-920-780 10080-2806.259-920-966 10080-2806.262-920-591
~10080-2806.258-920-881 10080-2806.260-920-073 10080-2806.262-920-599 l 10080-2806.259-920-054 10080-2806.260-920-478 10080-2806.262-920-600 l
10080-2806.259-920-056 10080-2806.260-920-523 10080-2806.262-920-778 10080-2806.259-920-087 _10080-2806.260-920-524 10080-2806.263-920-959 j 10080-2806.259-920-088 ~ 10080-2806.260-920-525 10080-2806.263-920-960 !
10080 2806.259-920-089 10080-2806.260-920-526 10080 2806.263-920-963 j 10080-2806.259-920-092 10080-2806.260-920-527 10080-2806.263-920-973 l Page 13 of 20
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,H Isometric Drawings:
10080-RK-317A-2 ' 10080-RK-328L-5 10080-RK-333J-6
- 10080-RK-317A-3 10080-RK-328L-10 10080-RK-333L-1 10080-RK-317B-1 10080-RK-333C-1 10080-RK-333L-6 10080-RK-317C-3 10080-RK-333F-1 10080-RK-333M 1 10080-RK-317C 10080-RK-333F-6 10080-RK-333M-6 10080-RK-317C-5 10080-RK-333G-6 10080-RK-333N-1 10080-RK-321A-1 10080-RK-333H 1 10080-RK-333N-6 10080-RK-321C-1 10080-RK-333H-6 10080-RK-333AD-1 10080-RK-321D-1 10080-RK-333J-1 Design Drawings:
10080-RP-121 A 10080-RV-1J 10080-RV-8A 10080-RP-121B 10080-RV-lK 10080-RV-8B 10080-RV-1A 10080-RV-1L 10080-RV-1H 10080-RV-IS Vendor Drawings:
10080-2006.280-091-032 10080-2006.440-067-033 10080-2007.650-719-161 10080-2006.320-064-032 10080-2006.440-067-041 10080-2007.650-719-232 10080-2006.320-64A-066 ' 10080-2006.450-76A-075 10080-2007.650-719-238 10080-2006.320-064-038 10080-2006.450-82A-084 10080-2007.730-001-039 10080-2006.360-075-022 10080-2007.506-756-004 10080-2007.880-001-003
'10080-2006.380-091-033 10080-2007.650-651-117 10080-2007.880-001-005 10080-2006.390-069-056 10080-2007.650-651-118 10080-2010.290-192-003 10080-2006.390-069-097 10080-2007.650-679-181 10080-2858.711-000-001 10080-2006.420-020-006 10080-2007.650-719-125 10080-2858.711-000-002 10080-2006.420-020-007 10080-2007.650-719-132 Page 14 of 20
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l Vendor Technical Manual:
10080-2702.102-001-201
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Flow Diagrams:
10080-RB-85D 10080-RM-75A 10080-RM-87A 10080-RB-91C 10080-RM-75B 10080-RM-87B 10080-RB 910 10080-RM-76A 10080-RM-88A 10080-RM-41 A 10080-RM-77B 10080-RM-89A 10080-RM-45A 10080-RM-79A 10080-RM-99E 10080-RM-45B 10080-RM-79C 10080-RM-99F 10080-RM-47F 10080-RM-79D 10080-RM-100A 10080-RM-61B 10080-RM-82A 10080-RM-110A 10080-RM-61D 10080-RM-85A j 10080-RM-71B 10080-RM-85B Valve Operating Number Diagrams (VONDs):
10080-RM-406-1 10080-RM-413-1 10080-RM-425-1 10080-RM-406-2 10080-RM-413-2 10080-RM'-429-4 10080-RM-4071 A 10080-RM-414A-1 10080-RM-433-1A 10080-RM-407-3 10080-RM-414A-2 10080-RM-433-1D l i
10080-RM-409-1 10080-RM-414C-2 10080-RM-434-1B 1 10080-RM-410-1 10080-RM-415-2 10080-RM-434-3 i 10080-RM-411-1 10080-RM-420-1 10080-RM-444C-2 l 10080-RM-411-2 10080-RM-421-1 10080-RM-446-1 l
10080-RM-412-1 10080-RM-424-2A 10080-RM-447-1 10080-RM-412-2 10080-RM-424-3 I
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VOND Change Notices (VCNs):
VCN 2 96-179 VCN 2-96-182 VCN-2-96-185 VCN 2-96-180 VCN 2-96-183 VCN 2-96181 VCN 2-96-184 Operating Manual (OM) and Procedures:
20M-Chapter 47, Containment j 20M-47.3.D, Containment Integrity Check List 20ST-47.2, Containment Integrity Verification 20ST-47.3A, Containment Penetration and ASME Section XI Valve Test l
Test Procedure: -
2BVT 1.60.5,IST Safety and Relief Valve Tracking Engineering Memorandum (EM):
l EM 112519, Overpressure Protection of Containment Penetrations l
Technical Evaluation Report (TER):
TER 10322, Removal of Blind Section of Spectacle Flange on Downstream of Valves Design Specifications:
2BVS-65, Reactor Containment Liner and Mat Embedments i
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2BVS-939, Piping Engineering and Design 10 CFR 50.59 Safety Evaluation Reports:
Add RVLIS to Containment Penetration Table and UFSAR Fire Protection Water System Containment Penetrations Page 16 of 20 L
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Updated Final Safety Analysis Report (UFSAR):
Section 3.1, Conformance With U.S. NRC General Design Criteria Section 5.1, Reactor Coolant System And Connected Systems Summary Description Section 6.2.4, Containment isolation System Section 6.3, Emergency Core Cooling System Section 10.3, Main Steam Supply System Table 6.2-60, Containment Isolation Features 4 Section 3.8.1, Concre:e Containment l Section 5.1.2, Piping and Instrumentation Diagram j Section 5.4.7, Residual Heat Removal System Section 6.2.2, Containment Heat Removal System Section 6.2.5, Combustible Gas Control System Section 9.1.3, Spent Fuel Pool Cooling and Cleanup System Section 9.2.1, Station Service Water System Section 9.2.2, Cooling Systems for Reactor Auxiliaries Section 9.3.1, Compressed Air Systems .
Section 9.3.2, Process and Post Accident Sampling System Section 9.3.2.3, Post Accident Sampling System Section 9.3.3, Equipment and Floor Drainage System Section 9.3.4, Chemical And Volume Control System Section 9.4.7.3, Containment Purge Air System Section 9.5.1, Fire Protection System Section 9.5.9, Reactor Plant Gas Supply System I Section 9.5.10, Containment Vacuum System Section 10.4.7, Condensate and Feedwater System Section 10.4.8, Steam Generator Blowdown System ;
Section 10.4.9, Auxiliary Feedwater System Page 17 of 20
Technical Specifications including Limiting Conditions for Operation (LCOs), Surveillance Requirements and Bases:
3.6.1.1, Containment Integrity 3.6.1.2, Containment Leakage 3.6.1.3, Containment Air Locks 3.6.3.1, Containment Isolation Valves 3.7.1.1, Turbine Cycle - Safety Valves 5.2.2, Containment Design Pressure and Temperature 5.2.3, Containment Penetrations 6.17, Containment Leakage Rate Testing Program Table 3.6-1, Containment Penetrations (maintained at the back of the BVPS-2 Technical Specifications)
Design Analyses:
10080-N-749, Temperature Rise due to DBA in Containment of S/G Blowdown Piping 10080-SP-2CHS-05, Compilation of Setpoints for the CHS System 10080-2QSS* 12-0-C, Overpressure Protection for 2QSS*MOV101 A, B lD080-2RSS* 12-0-C, Thermal Relief Valves Which Protect the Valve Bonnetsof Gate Valves 2RSS*MOV156A, B, C, D 10080-211-N-285, Overpressure Protection Analysis for Gaseous Systems Penetrations 10080-DLC(P)-895-XD, Stress Evaluation for Sample Tubing Following a DBA 10080-NS(B)-262, Containment Liner Unsleeved Penetration Design Temperature Review I
Overpressure Protection Analyses: i OPA-1, Main Steam System, Feedwater System, Auxiliary Feedwater System and Steam Ocnerator Blowdown System '
OPA-4, Quench Spray System OPA4, Containment Penetrations Page 18 of 20
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Vendor Correspondence to DLC:
Memorandum concerning Masoneilan 20,000 and 40,000 series Globe Valves dated September 5,1996 DLC Correspondence:
DLC Telecon between SPED and NED personnel dated September 5,1996 Quality Control Report (QCR):
QCR Number 1340, dated September 5,1996, Inspection of Steam Generator Blowdown Piping Licensing Event Report (LER):
LER 96-009-00, Containment Penetrations Not in Accordance with the Design Basis Stone and Webster Engineering Corporation (SWEC) Beaver Valley Manual (BVM):
2BVM-178, Design Criteria for Containment Liner Penetratiora '
Miscellaneous
References:
NUREG / CR-2628, Inadequate Core Cooling Instrumentation Using Differential Pressure For Reactor Vessel Level Measurement, dated March 1,1982 The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III - Division 1,1971 Edition with Addenda through Winter 1972 Article NC-7000, Protection Against Overpressure Page 19 of 20
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