ML030780083
| ML030780083 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/29/2002 |
| From: | Schmidt E, Schroeder P Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0094 SCR 2002-0458 | |
| Download: ML030780083 (7) | |
Text
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 1 Title of Proposed Activity- AFW minimum flow requirement change to AOP, EOP, CSP, ECA, SEP, 01-62 A/B procedures Associated Reference(s) #: Removal of internals from-AF-1 17 and upgrade open function of AFW pumps minirecire vlaves to safety -related (MR 02-029); SCR 2002-005-01 EOPIARP actions for AFW mini-recirc requirement ; 2002-0055, P-38A/B mini recirc flow orifice replacment (MR 99-029 *A, *B);
Flowserve Corporation Pump Division letter dated March 2, 20012; CAP 29908; CAP 29952 Prepared by- Eric A. Schmidt / John P. Schroeder ,*( _ e /0 . d2 Name (Print) '4ir Reviewed by: __ _ __ _ __ -/A__
_4___ __ _ Date: 0 -A =
Nam'-P-rint) Signature PART I (50.59/72.48) - DESCRIBE THE PROPOSED ACTIVITY AND SEARCH THE PLANT AND ISFSI LICENSING BASIS (Resource Manual 5.3.1)
NOTE: The "NMC 10 CFR 50.59 Resource Manual" (Resource Manual) and NEI 96-07, Appendix B, Guidelines for 10 CFR 72.48 Implementation should be used for guidance to determine the proper responses for 10 CFR 50.59 and 10 CFR 72.48 screenings.
1.1 Describe the proposed activity and the scope of the activity being covered by this screening. (The 10 CFR 50.59/72.48 review of other portions of the proposed activity may be documented via the applicability and pre-screening process requirements inNP 5.1.8.) Appropriate descriptive material maybe attached.
This screening supports procedural uprgrades to address the Auxiliary Feedwater (AFW) System issue as identified in CAP, 29908 and CAP 29952. Procedural guidance for operation of AFW System will be changed such that the operator must ensure that discharge flow for P-38 A/B must be greater than 50 gpm and 1/2 P-29 discharge flow must be greater than 75 gprn. If pump flow cannot be maintained within these requirements, the pump must be secured.
1.2 Search the PBNP Current Licensing Basis (CLB) as follows: Final Safety Analysis Report (FSAR), FSAR Change Requests (FCRs) with assigned numbers, the Fire Protection Evaluation Report (FPER), the CLB (Regulatory) Commitment Database, the Technical Specifications, the Technical Specifications Bases, and the Technical Requirements Manual. Search the ISFSI licensing basis as follows: VSC-24 Safety Analysis Report, the VSC-24 Certificate of Compliance, the CLB (Regulatory)
Commitment Database, and the VSC-24 10 CFR 72.212 Site Evaluation Report Describe the pertinent design function(s),
performance requirements, and methods of evaluation for both the plant and for the cask/ISFSI as appropriate. Identify where the pertinent information is described in the above documents (by document section number and title). (Resource.
Manual 5.3.1 and NEI 96-07, App. B, B.2)
FSAR 10.2 Auxiliary Feedwater System (AF) - The AFW system shall automatically start and deliver adequate AFW flow to maintain adequate steam generator levels during accidents which may result in main steam safety valve opening, such as: Loss of normal feedwater (LONF) and Loss of all AC power to the station auxiliaries (LOAC). AFW system shall also deliver sufficient flow to the steam generators supporting rapid cooldown during such accidents as: steam generator tube rupture (SGTR) and Imain steam line break (MSLB).
Each pump has an AOV controlled recirculation line back to the condensate storage tanks to ensure minimum flow to prevent hydraulic instabilities and dissipate pump heat.
"TS3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3.4 Manual AFW Flow Control During Plant Shutdown Manual control of steam generator water level using the AF pumps to remove reactor decay and sensible heat.
FPER 6.6.4 Auxiliary Feedwater System The Auxiliary Feedwater Pumps are provided with a mini-recirc line to ensure a minimum amount of flow is established to keep the pumps from dead heading. I1"it)
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Point Beach Nuclear Plant SCR 2002-0458
. 10 CFR 50.59/72.48 SCREENING (NEW RULE) verify SCR number on all pages Page 2 FSAR 10.2 Auxiliary Feedwater System (AF)
TS 3.7.5 Auxiliary Feedwater (AFW) System "TSBases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.33.4 Manual AFW Flow Control During Plant Shutdown FPER 6.6.4 Auxiliary Feedwater System Specifications require a 1.3 Does the proposed activity involve a change to any Technical Specification? Changes to Technical License Amendment Request (Resource Manual Section 5.3.1.2).
Technical Specification Change: [] Yes 0D No If a Technical Specification change is required, explain what the change should be and why it is required.
any VSC-24 cask 1.4 Does the proposed activity involve a change to the terms, conditions or specifications incorporated in Certificate of Compliance (CoC)? Changes to a VSC-24 cask Certificate of Compliance require a CoC amendment request.
El Yes 0 No If a storage cask Certificate of Compliance change is required, explain what the change should be and why it is required.
-10 CFR 50.59 SCREENING Manual 5.3.2)
PART H (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGNFUNCTION (Resource Compare the proposed activity to the relevant CLB descriptions, and answer the following questions:
YES NO QUESTION 0 El ~Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited in the Safety Analyses?
El 0] Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses?
0] El Does the proposed activity involve SSCs whose failure could initiate a transient (e.g., reactor trip, loss of feedwater, etc.) or accident, OR whose failure could impact SSC(s) credited in the Safety Analyses?
0] El Does the proposed activity involve CLB-described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications?
El Z Does the activity involve a method of evaluation described in the FSAR?
El 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
El 0] Does the activity exceed or potentially affect a design basis limitfor afission product barrier(DBLFPB)?
(NOTE: If THIS questions is answered YES, a 10 CFR 50.59 Evaluation is required.)
the If the answers to ALL of these questions are NO, mark Part III as not applicable, document the 10 CFR 50.59 screening in conclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening Questions.
of evaluation(s) or DBLFPB(s)
If any of the above questions are marked YES, identify below the specific design function(s), method involved.
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I AA Reference, NP 5 18
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 3 MR-02-029 upgraded the open function of the AFW pumps mini-recirc AOV to safety-related. The safety-related boundary includes the recirc orifice and all associated upstream components and piping. It is postulated that a failure of the piping downstream of the recirc orifice will not have any adverse affects on the AFW system. The availability of the recirculation flowpath provides an additional flowpath to support minimum flow requirements. This procedure change will improve the reliability of the AFW pumps by not relying upon the recirc flow path for operability as it has been concluded that the restrictions in the recirc orifice may not be adequate for use. Whereas current guidance mandates that the operator verify the position of the recirc AOV and the status of the Instrument Air system, these procedural changes will only require the operator to monitor pump discharge flow.
PART 111 (50.59) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (Resource Manual 5.3.3)
If ALL the questions in Part HI are answered NO then Part m is El NOT APPLICABLE.
Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 50.59 Evaluation is required; EXCEPT where noted in Part 11.3.
111.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO, QUESTION El 0] Does the activity adversely affect the designfunction of an SSC credited in safety analyses?
El 0 Does the activity adversely affect the method of performing or controlling the designfunction of an SSC credited in the safety analyses?
If any answer is YES, a 10 CFR 50.59 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion as necessary):
Minimum flow requirements will be maintained within recommendations from the vendor by monitoring pump discharge flow and securing the pump as required. Starting and stopping of the AFW pumps has been previously evaluated in 50.59 Evaluation 2002-005, which addressed procedural changes to reduce the potential of pump damage as a result of the loss of the recirculation flow path.
11.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are 0 NOT APPLICABLE.)
YES NO QUESTION
[] El Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB?
El [E Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in the CLB?
If any answer is YES a 10 CFR 50.59 Evaluation is required. If both answers are NO. describe the basis for the conclusion (attach additional discussion, as necessary).
111.3 TESTS OR EXPERIMENTS If the activity is not a test or experiment, the questions in I1.3.a and III.3.b are Z NOT APPLICABLE.
- a. Answer these two questions first:
YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB?
El nl Are the SSCs affected by the proposed test or experiment isolated from the facility?
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Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59172.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 4 is YES, then If the answer to BOTH questions in V.3.a is NO continue to mI.3.b. If the answer to EITHER question describe the basis.
given in IfI.3.a above.
- b. Answer these additional questions ONLY for tests or experiments which do NOT meet the criteria If the answer to either question in II.3.a is YES, then these three questions are [] NOT APPLICABLE.
YES NO QUESTION El El Does the activity utilize or control an SSC in a manner that is outside the reference bounds bf the design bases as described in the CLB?
E] E] Does the activity utilize or control an SSC in a manner that is inconsistent with the analyses or descriptions in the CLB?
......... ..... .. Does tectiyity place theqfacility in a condition notprevýiý sly evaluated or that could affect the, capability of an SSC to perform its intended functions?
NO, desci'be the If any answer in IL3.b is YES, a 10 CFR 50.59 Evaluation is required. If the answers in 1I1.3.b are basis for the conclusion (attach additional discussion as necessary):
Part IV - 10 CFR 50.59 SCREENING CONCLUSION (Resource Manual 53.4).
Check all that apply.
A 10 CFR 50.59 Evaluation is [D required or 0 NOT required.
initiate an FSAR Change A Point Beach FSAR change is [E required or Z NOT required. If an FSAR change is required, then Request (FCR) per NP 5.2.6.
A Regulatory Commitment (CLB Commitment Database) change is E] required or 0] NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.
Specification Bases is A Technical Specification Bases change is El required or 0 NOT required. If a change to the Technical required, then initiate a Technical Specification Bases change per NP 5.2.15.
A Technical Requirements Manual change is E] required or 0 NOT required. If a change to the Technical Requirements Manual is required, then initiate a Technical Requirements Manual change per NP 5.2.15.
- 10 CFR 72.48 SCREENING to determine the NOTE: NEI 96-07. Appendix B, Guidelines for 10 CFR 72.48 Implementation should be used for guidance proper responses for 72.48 screenings.
PART V (72.48) - 10 CFR V2.48 INITIAL SCREENING QUESTIONS the proposed activity.
Part V determines if a full 10 CFR 72.48 screening is required to be completed (Parts VI and VII) for YES NO QUESTION the cask transfer/transport El ED Does the proposed activity involve IN ANY MANNER the dry fuel storage cask(s),
as follows: Multi-Assembly Sealed Basket equipment, any ISFSI facility SSC(s), or any ISFSI facility monitoring Concrete Cask (VCC), Ventilated Storage (MSB), MSB Transfer Cask (MTC), MTC Lifting Yoke, Ventilated Facility, ISFSI Storage Pad Data/Communication Links, Cask (VSC), VSC Transporter (VCST), ISFSI Storage Pad or PPCS/ISFSI Continuous Temperature Monitoring System?
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Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 5 El 0] Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System?
ElI 0 Does the proposed activity involve IN ANY MANNER SSC(s) needed for plant operation which are also used to support cask loading/unloading activities, as follows: Spent Fuel Pool (SFP), SFP Cooling and Filtration (SF),
Primary Auxiliary Building Ventilation System (VNPAB), Drumming Area Ventilation System (VNDRM),
RE-1 05 (SFP Low Range Monitor), RE-135 (SFP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bridge, Truck Access Area, or Decon Area?
El 0 Does the proposed activity involve a change to Point Beach CLB design criteria for external events such as earthquakes, tornadoes, high winds, flooding, etc.?
ED 0 Does the activity involve plant heavy load requirements or procedures for areas of the plant used to support cask loading/unloading activities?
El 0D Does the activity involve any potential for fire or explosion where casks are loaded, unloaded, transported or stored?
If ANY of the Part V questions are answered YES, then a full 10 CFR 72.48 screening is required and answers to the questions in Part VI and Part VII are to be provided. If ALL the questions in Part V are answered NO then check Parts VI and VII as not applicable. Complete Part VIII to document the conclusion that no 10 CFR 72.48 evaluation is required.
PART VI (72.48) - DETERMINE IF THE CHANGE INVOLVES A ISFSI LICENSING BASIS DESIGN FUNCTION (If ALL the questions in Part V are NO then Part VI is El NOT APPLICABLE.)
Compare the proposed activity to the relevant portions of the ISFSI licensing basis and answer the following questions:
YES NO QUESTION El 0] Does the proposed activity involve cask/ISFSI Safety Analyses or plant/cask/ISFSI structures, systems and components (SSCs) credited in the Safety Analyses?
El 0 Does the proposed activity involve plant, cask or ISFSI SSCs that support SSC(s) credited in the Safety Analyses?
El 0 Does the proposed activity involve plant, cask or ISFSI SSCs whose function is relied upon for prevention of a radioactive release, OR whose failure could impact SSC(s) credited in the Safety Analyses?
El Z Does the proposed activity involve cask/ISFSI described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, CoC conditions, or orders?
El [] Does the activity involve a method ofevaluation described in the ISFSI licensing basis?
El 2 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
El 0] Does the activity exceed or potentially affect a cask design basis limit for afissionproduct barrier(DBLFPB)?
(NOTE: If THIS questions is answered YES a 10 CFR 72.48 Evaluation is required.)
If the answers to ALL of these questions are NO, mark Parts VII as not applicable, and document the 10 CFR 72.48 screening in the conclusion section (Part VIIIT.
If any of the above questions are marked YES, identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.
PART VII (72.48) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (NEI 96-07, Appendix B, Section B.4.2.1)
(IfALL the questions in Part V or Part VI are answered NO then Part VII is 0 NOT APPLICABLE.)
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Point Beachý Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all page Page 6 Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 72.48 Evaluation is required; EXCEPT where noted in Part VII.3.
VII.1 Changes to the Facility or Procedures YES NO QUESTION E] El Does the activity adversely affect the designfunction of a plant, cask, or ISFSI SSC credited in safety analyses?
E] E] Does the activity adversely affect the method of performing or controlling the designfunction of a plant, cask, or ISFSI SSC credited in the safety analyses?
If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion, as necessary):
VI.2 Changes to a Method of Evaluation (If the activity does not involve a method of evaluation, these questions are E] NOT APPLICABLE.)
YES NO QUESTION 0 13 Does the activity use a revised or different method of evaluation for performing safety analyses than that described in a cask SAR?
El E] Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in a cask SAR?
If any answer is YES a 10 CFR 72.48 Evaluation is required. If both answers are NO. describe the basis for the conclusion (attach additional discussion, as necessary):
V.113 Tests or Experiments (If the activity is not a test or experiment, the questions in VII.3.a and VII.3.b are E] NOT APPLICABLE.)
- a. Answer these two questions first:
YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis?
El El Are the SSCs affected by the proposed test or experiment isolated from the cask(s) or ISFSI facility?
k If the answer to both questions is NO, continue to VII.3.b. If the answer to EITHER question is YES, then briefly describe the basis.
- b. Answer these additional questions ONLY for tests or experiments which do not meet the criteria given in VII.3.a above.
If the answer to either question in VII.3.a is YES, then these three questions are El NOT APPLICABLE:
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Point Beach Nuclear Piant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 7 YES NO QUESTION El 1l Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in the ISFSI licensing basis?
El [E Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descriptions in the ISFSI licensing basis?
[I El Does the activity place the cask or ISFSI facility in a condition not previously evaluated or that could affect the capability of a plant, cask, or ISFSI SSC to perform its intended functions?
If any answer in VII.3.b is YES, a 10 CFR 72.48 Evaluation is required. If the answers are all NO describe the basis for the conclusion (attach additional discussion as necessary):
PART VII-L DOCU- ENT-iIE'CONCI(USiOTqOF Ti"E 16"CIG72:48 SCfEEXING .. ."-
Check all that apply.
A 10 CFR 72.48 Evaluation is [] required or Z NOT required. Obtain a screening number and provide the original to Records Management regardless of the conclusion of the 50.59 or 72.48 screening.
A VSC-24 cask Safety Analysis Report change is El required or ED NOT required. If a VSC-24 cask SAR change is required, then contact the Point Beach Dry Fuel Storage group supervisor.
A Regulatory Commitment (CLB Commitment Database) change is E] required or Z NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.
A change to the VSC-24 10 CFR 72.212 Site Evaluation Report is El required or 0 NOT required. If a VSC-24 10 CFR 72.212 Site Evaluation Report change is required, then contact the Point Beach Dry Fuel Storage group supervisor.
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