ML19290E554
| ML19290E554 | |
| Person / Time | |
|---|---|
| Site: | 05000495 |
| Issue date: | 03/17/1980 |
| From: | STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| Shared Package | |
| ML19290E552 | List: |
| References | |
| NUDOCS 8003140201 | |
| Download: ML19290E554 (8) | |
Text
.
SWESSAR-P1 AMENDMENT 42 March 17, 1980 PWR REFERENCE NUCLEAR POWER PLANT SAFETY ANALYSIS REPORT ASSEMBLY INSTRUCTIONS Remove Insert Insertion Location Assembly Instructions Front of Vol. 1 S6W Letter Front of Vol. 1 Notarized Statement Front of Vol. 1 3C-a 3C-a 3C-1/2 3C-1/2 3C-15/16 3C-15/16 3C-21/22 3C-21/22 8003140 Md/
SWESSAR-P1 APPENDIX 3C EXTENSION REVIEW MATTERS FOR PRELIMINARY DESIGN APPROVALS LIST OF EFFECTIVE PAGES Page, Table (T) Amendment or Fiqure (F) No.
3C-a 42 3C-i 40 3C-1 and 2 42 3C-3 thru 14 40 3C-15 42 3C-16 40 3C-17 41 3C-18 thru 21 40 3C-22 42 3C-23 thru 25 40 3C-a Amendment 42 3/17/80
SWESSAR-P1 APPENDIX 3C EXTENSION REVIEW MATTERS FOR PRELIMINARY DESIGN APPkOVALS The following items (1) are not within the SWESSAR-P1 scope (Utility-Applicant or NSSS scope-35 items) .
Category I: Items 3, S, 9, 15, 16, 17, 20, 24, 26, 28, 34, 38, 42 39, 40, 44, 45, 49, 50, 51, 54, and 55 Category II: Items 6, 18, and 19 Category III: Items 1, 3, 4, 5, 7, 9, and 11 Category IV-C: Items 4, 7, 8, and 11 The following items have NRC implementation dates prior to the NRC cutoff date for SNESSAR/BSAR-205 which is September 1976.
Since the applicable items are generic to SSW design (white pages) , the NRC review and conclusion relative to SWESSAR/BSAR-205 are applicable (44 items).(2)
Category I: Items 6, 14, 21, and 22 Category II: Items 1, 2, 8, 16, and 17 Category III: Item 6 Category IV-A: Items 1 through 6 Category IV-B: Items 1 through 23 Category IV-C: Items 2, 3, 13, 18, and 19 The following items are duplicated or the response is already in SWESSAR-P1 even though the implementation date is after September 1976 ( 10 items) . ( 2 )
Category I: Items 7, 13, and 42 Category II: Items 5, 15, and 20
(*)The NRC letters of January 24, 1979 (Enclosure 1 to W.J.L.
Kennedy's letter of May 3, 1979 to Roger Boyd) listing Categories I, II, III, and IV matters identifies the item numbers. These items were numbered by SSW in some cases.
Category I and III matters approved since September 1, 1978 were telecopied to SSW by the NRC on February 20, 1980 and were numbered by SSW to follow sequentially the items in the 42 January 24, 1979 letters.
(2 )Reterence SSW letter RPS-375 dated August 16, 1979 3C-1 Amendment 42 3/17/80
SWESSAR-P1 Category IV-C: Items 1, 5, 14, and 17 The remaining items listed below are addressed in Sections 3C.1 through 3C.4 even though they are not considered signiricant safety issues. These. items are applicable to the SWh.SSAR-P1 design and the NRC 1mplementation date is after September 1976, the cutoff date for SWESSAR/BSAR-205 (46 items) .
Category I: Items 1, 2, 4, 5, 10, 11, 12, 18, 19, 23, 25, 27, 29, 30, 31, 32, 33, 35, 36, 37, 41, 43, 46, 47, 48, 52, and 53 Category II: Items 3, 4, 7, 9, 10, 11, 12, 13, and 14 Category III: Items 2, 8, 10, and 12 l42 Category IV<C: Items 6, 9, 10, 12, 15, and 16 0
3C-2 Amendment 42 3/17/80
SWESSAR-P1 Item 48 - RG B.19, Rev 0 (3/14/78) Occupational Radiation Dose Assessment at LWRs - Design State Man-Rem Estimates
Response
Estimates of occupational radiation doses for selected normal operational activities are described in Section 12.1.6. Routine and special maintenance, instrument calibration, fuel handling and inservice inspection are not included.
Item 52 - RG 1.XX (RS 035-2), Auditing ot Quality Assurance Programs
Response
Regulatory Guide 1.144, Revision 0, dated January 1979, reflects the latest NRC guidance for auditing of quality assurance programs for nuclear power plants. The position for Regulatory Guide 1.144 is given in Appendix VII of SSW Topical Report 42 SWSQAP 1-74A. Appendix VII of the topical report addresses ANSI N45.2.12, Draft 3, Revision 4, dated February 22, 1974; however, the same degree of compliance applies to ANSI N45.2.12-1977 and Regulatory Guide 1.144, Revision O.
Item 53 - ETSB 11-4, Design Guidance for Radiological Effluent Monitoring Instrumentation Installed in Light Water Cooled Nuclear Power Reactors
Response
The design or radiological effluent monitoring instrumentation complies with ETSB 11-4.
3C-15 Amendment 42 3/17/80
SWESSAR-P1 3C.2 REGULATORY REQUIREMENTS REVIEW COMMITTEE (RRRC)
CATEGORY II Item 3 - RG 1.59, Rev 2 (8/77) Design Basis Floods for Nuclear Power Plants
Response
The design complies with the regulatory positions of RG 1.59, Rev 2, with the following exception: For a site on a water body of more complex Geometry, such as semi-enclosed bay, the S&W two-dimensional model described in SSW Topical Report SWECO 7501-P-A (and the nonproprietary version ShECO-7501-NP-A) , entitled "Two Dimensional Coastal Storm Surge Model," will be used.
Item 4 - RG 1.63, Rev 1 (3/22/77) , Electrical Penetration Assemblies in Containment Structures for Water-Coo .d Nuclear Power Plants
Response
The criteria used in the design, construction, installation, and testing of electrical penetrations cotyly with RG 1.63, Rev 1, dated May 1977 with the following clarifications:
- 1. The single failure provision of Rg 1.63 shall apply to both Class IE and Class Non-IE overcurrent protection devices.
- 2. An acceptable method of compliance with the " Single Failure Criterion" of RG 1.63 may be the use of redundant or backup circuit breakers.
- 3. While satisfying the " Single Failure Criterion" in IEEE 279-1971, Section 4.2, the overcurrent protection devices are not required to comply with other criteria listed in IEEE 279-1971.
Item 7 - RG 1.97, Rev 1 (1/28/77) , Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Daring and Following an Accident.
Response
The criteria used in the design of the Post-Accident Monitoring System comply with RG 1.97, Rev 1 dated August 1977, with the following exceptions:
3C-16 Amendment 40 7/10/79
SWESSAR-P1
- 11. Footnote 4 on page 1.130-4 should be deleted in its entirety.
- 12. Footnote 5 on page 1.130-4 should be deleted in its entirety.
3C-21 Amendment 40 7/10/79
SWESSAR-P1 -
3C.3 REGULATORY REQUIREMENTS REVIEW COMMITTEE (RRRC)
CATEGORY III Item 2 - RG 1.68.2, Rev 1 (5/16/78) Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants
Response
The design complies with the remote shutdown capability of RG 1.68.2, with the following exception:
The regulatory position implies the requirement for transfer switches. Separately rused parallel controls may be utilized in the design rather then a transfer service.
The responsibility of the initial startup test program is within the scope of the Utility-Applicant.
Item 8 -
RG 1.137, Rev 0 (9/27/77) Fuel Oil Systems for Standby Diesel Generators
Response
The cesign of fuel oil systems for standby diesel generators complies with RG 1.137 dated January 1978.
Item 10 - RG 1.141, Rev 0 (1/31/78) Containment Isolation Provisions for Fluid Syatems
Response
The design complies with RG 1.141, Rev 0 dated April 1978, w2 *h the tollowing exception:
Regulatory Position C.3 parameters sensed (i.e. , types of isolation signals) for the initiation of containment isolation are as specified by the NSSS vendor.
Item 12 - Anticipated Transients Without Scram ( A'1MS)
Response 42 BOP moditications will compl.' with the final NRC resolution of ATWS.
O 3C-22 Amendment 42 3/17/80