ML20211J298
| ML20211J298 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/18/1997 |
| From: | Strauss G BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20211J295 | List: |
| References | |
| PROC-970918, NUDOCS 9710080061 | |
| Download: ML20211J298 (241) | |
Text
{{#Wiki_filter:. _ . - _ _ . . - _ - . . _ - - . _ - - - - . - - _ - . - - - _ - - - ATTACIIMENT (1) 4 i i PUMP AND VALVE INSERVICE TESTING PROGRAM Tinuo TEN-YEAR INTERVAL FOR CALVERT CLYFFS NUCLEAR POWER PLANT UNITS 1 AND 2 REVISION 1 i 9710000061 971001 PDR ADOCK 05000317 P PDR Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant October 1,1997
- _ _.m. _ _ .
4 t PUMP AND VALVE INSERVICE TESTING PROGRAM THIRD TEN-YEAR INTERVAL FOR i ' CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 Implementation DAte: January 15,1998 , Commercial Service Date Unit 1: May 8,1975 Unit 2: April 1,1977 (Docket Nos, 50-317 & 50-318).
- BALTIMORE GAS AND ELECTRIC COMPANY-
- Original Prepared by: A. R. Jacobstein. ThermTech Services. Inc. Date: 3/29/97 Independent Review: G. S. Strauss Date:- 4/16/97 l - Approved
, By: P. E. Katz Date: 4/30/97 Revision 1 ' Prepared by: ,M c.A 5nxuss Date: 9//B,/97 Independent-fk// ) fik1n>/ lh
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Review: Kuaer L - Date: f/Mk7 Date: By/
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i
- List of Effective Pages Page Revision Page Revision Page Revision Page Revision i 1 C-16 1 D-34 1 E-8 1 ii - 1 C-17 1- D-35 1 E-9 1 iii 1 C-18 1 D-36 1 E-10 1 iv 1 D-37 1 E-11 1 1 1 D-38 1 E-12 1
_2 1 D-1 1 D 39 1 E-13 1 3 1 D-2 1 D-40 1 E-14 1 4 1 D-3 1 . D-41 1 E 1 5 1 D-4 1 D-42 1 E-16 1 6 1 D-5 1 D-43 1 E-17 1 7 1 D-6 1 D-44 1 E-18 1 8 1 D-7 1 D-45 1 E-19 1 9 1 D-8 1 D-46 1 E-20 1 10 1 D-9 1 D-47 1 E-21 1 11 1 D-10 1 D-48 1 13 - 2 2 1 12 1 D Il 1 D-49 1 E-23 1 D-12 1 D-50 1 E-24 1 A-1 1 D-13 1 D-51 1 E-25 1 A-2 1 D-14 1 D-52 1 E-26 1 A-3 1 D-15 1 D-53 1 E-27 1 A-4 1 D-16 1 D-54 1 E-28 1 B-1 1 D-17 1 D-55 1 E-29 1 B-2 1 D-18 1 D-56 1 E-30 1 B-3 1 D-19 1 D-57 1 E-31 1 C-1 1 D-20 1 D-58 1 E-32 1 C-2 1 D-21 1 D-59 1 E-33 1 C-3 '1 D-22 1 D-60 1 E-34 1 C-4 1 D-23 1 D-61 1 E-35 1 C-5 1 D-24 1 D-62 1 E-36 1 C-6 1 D-25 1 D-63 1 E-37 1 C-7 1 D-26 1 E-38 1 C-8 1 D-27 1 E-1 1 E-39 1 C-9 1 D-28 1 E-2 1 E-40 1 C-10 1 D-29 1 E-3 1 E-41 1 C-11 1 D-30 1 E-4 1 E-42 1 C-12 1 D-31 1 E-5 I .E-43 1 C-13 1 D-32 1 E-6 1 E-44 1 C-14 1 D-33 1 E-7 1 E-45 1 i
List of Effective Pages Page,j Revision Page Revision Page Revision Page Revision E-4 a l ~ 1 G-2 1 G-40 1 E-4 [~ l G-3 1 G-41 1 i E48 1 G4 1 G42 1 E-49 1 G-5 1 - H-1 1-1 E-50 1 G-6 1 H-2 1 E 51 1 G-7 1 H-3 1 E-52 1 G-8 1 H-4 1 E-53 1 G9 1 H-5 1 E-54 1- G-10 1 H-6 1 E-55 1 G-11 1 H-7 1 E-56 1 G-12 1 H-8 1 ' ) E-57 G-13 1 1 H-9 1 F-1 1 G-14 i H-10 1 F-2 1 G 15 1 H ll 1 F-3 1 G-16 1 H-12 1
- F-4 1 G 17 1 F-5 1 G-18 1 F-6 1 G-19 1 F-7 1 G-20 1 F-8 1 G-21 1 F-9 1 G-22 1 F-10 1 G-23 1
, F-11 1 G-24 1 ~ F-12 1 G-25 1 _F-13 1 G-26 1 F-14 1 G-27 1 F F-15 1 G-28 1 F-16 1 G-29 1 F-17 1 G-30 1 F-18 1 G-31 1 F 1 G-32 1 F-20 1 G-33 1 F-21 1 G 34 1 F-22 1 G-35 1 F-23 1 G-36 1 F-24 1 G-3 7 - 1 G-38 1 G-1 1 G-39 1 ii ! l l
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1 1 Table of Contents Pane l Li st of Effect ive Pag es . .. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . { Table o f Co nt ent s : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . j Reco rd of R esi sions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . .
- 1.0 I nt rod u ctio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......I .......................
2.0 Reference Docu t r.ent s . . . . . .. . . ... . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0 P rogram Developmem . . . . . . . . . . . . . . .. . r. .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.1 Initial Program Scope . .. . . . . .. .. .. . . . .. . . .. . .. . . . . .. . .. . . . . . . . . . . .. . . . . . . . . . . . ... . . . . . . 4 3.2 Program Updat e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . , 5 j' 3.3 Progra m S cope Philo sop hy . . .. . . . . . . . ... .. .. .. . . . . . .. . .. . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . 5 3.4 - - Augmented Testing Program for Non-Code Class Pumps and Valves. 7 . 4.0 - Inservice Testing Program For Pumps ..................... ......... ......................... 8
- 4.1 Code Compliance ................... .................................................8 4.2 Allowable Ranges of Test Quantities .................... .... .................... . 8 4.3 Test ing I nte
- val s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 8 4.4 Pu mp P rogram Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . ' 9 4.5 Relief Requests for Pump Testing ........ .. .......................... .. ...... ..., 9 4.6 - I nst ru ment accu ra cy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 5.0 Insenice Testing Program For Valves .............................. .......... ..... ,, ... 9
- 5.1- Co d e Co mpliance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . 9 5.2 Stroke Time Acceptance Criteria ....,........................................9
- 5.3 C heck Valve Testing . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . .. . . . . , 9 5.4 Testing Int ervals . .. ... . . . . .. . . . . . . . . . . . . . . . . .. . .. . . . . . . .. . . . . . . . . . , . . . . . 10 5.5 ~ Valve Program Tables . . . . . . . . . . . . . .. . .. .. . . . . . . ... .. . . . ... . . . . ... . . . .. .. . .. .. .. . . . I 1 5.6 - D e ferred Testing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1 5.7 . Relief Requests For Valve Testing ...........,..........................,..12 5.8 Active and Passive Valves ... . .. ........ .. .. ........ .. ..... . ....... .... ... ... .- 12 Appendices A Inservice Testing Plan -_ Unit 1 - Pumps B Insenice Testing Plan - Unit 2 - Pumps C- -Relief Requests - Pumps
-D Insenice Testing Plan - Unit 1 - Valves E_ Insenice Testing Plan - Unit 2 - Valves -
F Relief Requests -_ Valves G Cold Shutdown Testing Justifications - Valves H Refueling Outage Testing Justifications - Valves til
RECORD OF REVISIONS REVISION DESCRIPTION OF REVISION DATE NUMBER REASON FOR THE CHANGE RLVISED Original N/A N/A 1 a. Revised Cold Shutdown 9/18/97 Justification CSJ-44 (pg. G-38).
- b. Added ReliefRequest VR-13 &
revised affected Unit 1 & 2 valve tables (pgs. F-23, F-24, F25, D-43, E-39).
- c. Withdrew ReliefRequest VR-04 &
revised affected Unit 1 & 2 valve tables ' (pgs. F-5, D-40, E-36)
- d. Withdrew ReliefRequest PR-07 &
revised affected Unit 1 & 2 pump tables. (pgs. C-13, A-3, B-3)
- e. Re-paginated, iv
INSERVICE TESTING (IST) PROGRAM PLAN CALVERT CLIFFS NUCLEAR POWER PLANT
1.0 INTRODUCTION
This document outlines the Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2, IST Program for the third 10-year interval based on the requirements of Section XI of the Americt a. Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,1989 Edition. Subsections IWP and IWV refer to implementing the requirements of ASMPJANSI OM-6 and OM-10, respectively. Herefore, per Reference 2.1, this revision of the Calvert Cliffs Nuclear Power Plant IST Program is l based on the applicable requirements set forth in ASMPJANSI OM-1987 " Operation and Maintenance of Nuclear Power Plants" including ASMPJANSI OMa-1988 l Addenda. This revision of the CCNPP ASME Inservice Testing (IST) Pmgram will be in effect through the end of the third 120-month (10-year) interval unless changed and re-issued for reasons other than the mutine update required at the start of the fourth interval per 10 CFR 50.55a(0, ne third inspection interval begins on January 15,1998, and ends on January 14,2008. r 1
2.0 REFERENCE DOCUMENTS This Program Plan was developed per the requirements and guidance provided by the following documents: 2.1 Title 10, Code of Federal Regulations, Part 50.55a 2.2 NRC Regulatory Guides - Division 1 2.3 Standard Review Plan 3.9.6, "Ine:vice Testing of Pumps and Valves 2.4 Updated Final Safety Analysis Report, Calvert Cliffs Nuclear Power Plant, Rev.19 2.5 Calvert Cliffs Nuclear Power Plant Technical Specifications throughUnit 1 Amendment 220 & Unit 2 Amendment 196. l 2.6 ASME Boiler and Pressure Vessel Code, Section XI,1989 Edition 2.7 NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" 2,8 ASME/ ANSI OM-1987 " Operation and Maintenance of Nuclear Power Plants" i including ASMFJANSI OMa-1988 Addenda. I l- 2.9 NUDEG-1482, Guidelines for Inservice Testing at Nuclear Power Plants - 2
3.0' PROGRAM DEVELOPMENT ASME B&PV Code, Section XI (hereby referred to as 'the Code') requires that the owner of each nuclear power plant prepare and submit a " plan" for testing and ' inspection of systems and components under thejurisdiction of the Code and in compliance with Title 10, Part 50 of the Code of Federal Regulations (Para. 50.55.a). With respect to the elements of that plan related to the testing of pumps and valves, Section XI, Subsections IWP and IWV direct each licensee to comply with the ; applicable portions of ASME/ ANSI OM-6 and OM 10. The regulation directs that ! pump and valve testing should be performed in accordance with ASME/ ANSI OM - 1987 including OMa-1988 Addenda. Spe.cifically, Part 1 of OM-1987 and Paragraphs 1.1 of OMa-1988 Addenda, Parts 6 and 10, establish the Program scope with the ! provision that the rules apply only to ISI Classes 1,2, and 3 as stated by Title 10, Part 50 of the Code of Federal Regulations (Para. 50.55.a)). l- In accordance with ASMFJANSI OM-1987 with OMa 1988 Addenda, the following ! are required to be inaluded in the testing Program: Class 1.2 ci , m trifunal and oositive dienlarament oumps that are provided with an emergency power source and required to perform a specif.c function in
- 1) Shutting down the reactor to the cold shutdown condition;
- 2) Maintaining the cold shutdown condition; or
- 3) Mitigating the consequences of an accident.
Class 1.2 and 3xlive or nassive valves (and their actuatine and nosition indicatine systems) which are required to perform a specific function in
- 1) Shutting down the reactor to the cold shutdown condition;
- 2) Maintaining the cold shutdown condition; or
- 3) Mitigating the consequences of an accident.
Class 1.2 and 3 oressure relief devices that protect systems or portions of systems which perform a required function in
- 1) Shutting down the reactor to the cold shutdown condition;
- 2) Maintaining the cold shutdown condition; or .
- 3) Mitigating the conseqaences of an accident.
3
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e j l
- 3.0 PROGRAM DEVELOPMENT (Continued)
- In addition to the general Code mquirements outlined above, there are other
) interpretations and positions that have come about as a result of past regulatory and
' licensee actions including NUREG-1482. Other than these, theit is no specific
- guidance for developing the IST Program scope of testing.
1 i " Note that the CCNPP safety analysis'specifically requires the units to reach a safe-shutdown condition defined as hot standby and not the cold shutdown condition as required by the Code. Per NUREG-1482 pumps and valves in such plants needed only to reach cold shutdown need not be included in the Inservice Testing Program. . However, in some instances, BG&E has decided to include cold shutdown-related
; components in the Program for completeness even though complir.nce with Code
. requirements may not be required.-
- In light of the foregoing, a set of rules was established by which the scope of the i CCNPP ASME Section XI IST Program is determined including comronents that are to j- be included and the extent and type of testing required for each component. Based on
! these rules, the philosophy and assumptions used in determining the test requirements for selected pumps and valves were documented. t
- 3.1- Initia- Program Scope In the course of developing the Program scope, each of the significant safety
[ systems (included within the ISI-class boundaries) were evaluated with respect i to the function of each component and the need for its operability as it relates to j' the scope of Section XI. Supporting documents used include, l - Updated Final Safety Analysis Report (UFSAR); i - Technical Specifications; Past program correspondence; I - Operating Procedures (Normal, Emergency and Off-Normal); and Plant System Descriptions.
!=
3 The sequence followed during the development effort was as follows:
- 1) Each of the plant systems was subjected to an overview to determine any-
, potential active safety function as described in the scope statement.
l Those systems with no safety functions were then excluded from further consideration. Plant documents as well as operating staff inputs were utilized in this phase. i >
)
4 4 4
, , - 3 m e -
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3.1 Initial Program Scope (Continued).
- 2) For the remaining systems, flow diagnms were studied and any co;nponent that could possibly have an active or passive safety function 1 (other than simply maintaining the pressure boundary) were identified =
for further evaluation.
- 3) The function of each component identified in 2, above, was determined.
This included classifying valves and their functions as passive or active. Testing requirements were then derived based on the component function (s) and the applicable avle(s), l
- 4) Documents were reviewed and specific or implied component .
operational requirements were compared to the infonnation derived in 3,- above.
. 5) The results of Steps I through 4, above, were reviewed by several knowledgeable members of the plant staff and evaluated for accuracy and consistency. Based on this review, the fm* al program scope was derived and the IST Program Plan developed.
3.2 Progam Update During the third 10-year interval,- it is expected that the scope of the Program will
- occasionally be modified in response to activities including, but not limited to,
- 1) Plant design changes;
- 2) Changes in operating conditions (e.g. normal valve lineup);
- 3) Changes in accident mitigating procedures ~ philosophy; or
- 4) Regulatory demands, As a result, the IST Program will be revised to ensure continued compliance with the Code requirements relating to the scope of the test program, as necessary.
The supervisor responsible for maintaining the IST Program is provided input from Engineering regarding plant modifications that are designated by Engineering to have a potential IST/ISI impact. - Additionally, other pertinent changes such as a significant
- change in plant operating or accident mitigation philosophy that might have a direct
' impact on the IST Program are also reviewed. Should a change require a Program revision, the IST Coordinator implements the change to the Program Plan and the appropriate test procedure (s) in a timely manner.
3,3 . Program Scope Philosophy The final scope of the Third Ten YearIntervalIST Program was determined based on an exhaustive' search and comprehensive evaluation of numerous design-basis and 5-
3.3 - - Program Scope Philosophy (Continued) licensing-basis documents which included, in part, the CCNPP UFSAR and Technical Specifications, various engineering and Q List evaluations, various CCNPP Operating Procedures and Instmetions, various CCNPP Abnormal and Emergency Operating Pmcedures, and numerous related NRC Generic Letters, Safety Evaluation Reports,
- and other current and historial docketed pieces of BGE-NRC correspondence The purpose of this effon was to identify and evaluate the safety function (s) of all potential candidate pumps and valves. The major criteria for including pumps and valves in the IST Program may be generalized / summarized as follows:
l 1. Pumps and valves credited in CCNPP UFSAR Chapter 14 Accident Analyses for accomplishing, or supporting, one or more of the Critical Safety Functions: Reactivity Control, RCS Prmsure & Inventory Control, RCS Heat Removal, Containment Isolation & Environment, Radiation Control, and Vital Auxiliaries.
- 2. Selected pumps and valves which provide " operational flexibility", i.ei components which are not specifically credited but may be substituted for '
7 components which are credited as accomplishing or supporting the Critical Safety Functions, Selected pumps and valves which support implementing selected "altemate success paths" (which are not credited) for accomplishing necessary safety functions, (However, uncontrolled scope growth would dilute Progmm effectivene',s if
- additional testing did not provide additional safety benefits.To avoid this, CCNPP considered factors such as (1) tie number of other " success paths" and
- which ones were already included in the IST Program, (2) the scope of other preventive maintenance or testing programs, (3) available equipment redundancy versus applicable single' failure requirements, e.g. multiple failure scenarios an: generally not included in the IST Program scope. Additionally, there are several ways CCNPP can progress from the licensed safe shutdown y
condition to the cold shutdown condition. However, since CCNPP is licensed for a safe, vice cold, shutdown condition, not all these camponents are necessarily classified safety-related and/or ASME Code Class 1, 2, or 3.) 4. Pumps and valves for which specific commitments have been made regarding inclusion in the IST Program, 5. Pumps and valves whose inclusion in the IST Program is specifically required by CCNPP Technical Specifications, 6
-J
3.3 Pmgram Scope Philosophy (Continued)
- 6. Selected pumps and valves whose assumed performance is considered critical in applicable, pettinent, engineering evaluations / calculations,
- 7. Pressure relief devices which meet the above criteria themselves, or protect systems / portions of systems which meet the above criteria.
3.4 Augmented Testing Program for Non-Code Class Pumps and Valves l The reviews performed to prepare the Third Ten-Year Interval IST Program identified L some safety-related, non-Code Class valves which perform significant safety functions. l - Per NUREG-1482, Section 2.2 and Appendix G, non-Code Class pumps and valves aie
- RQt required to be included in the IST Program. However, even though these non-Code Class valves do not fall within the required scope of the IST Program, some perform significant safety functions which would otherwise fall within the scope of the Code and, therefore, require some type of testing commensurate with their importance to safety.
NUREG-1482 Section 2.2 and Appendix G states tilat testing of such non-Code Clan pumps and valves can be consolidated with the IST Program (without actually including them ir the scope of the IST Program) to the maximum extent desired and/or practical for convenience and that " deviations" from the Code for such components do not require an approved relief request. CCNPP considered several options for testing these selected non-Code Class valves. Because of the similarity most of these non-Code Ces valves have to some of the Code Class valves in the IST Program (such as configuration and function), CCNPP detetmined that consolidating their testing with the IST Program, as discussed in NUREG-1482, maximized the benefits and minimized the costs. Such consolidation was done for CCNPP's convenience. While these non-Code Class valves will be tested commensurate with their safety function (s), this does not necessarily mean such testing will conform to the Code. The' NUREG discussion also intcates it is desired that such situations be clearly _
- identified to avoid confusion and the appearance of a failure to properly implement Code requirements. To minimize confusion, however, CCNPP also concluded it was best to integrate these valves into the Valve Tables so that all related testing could be grouped and tracked considering any similar Code and non-Code Class valves. This
- was done in this manner solely for CCNPP convenience in order to minimize confusion -
and improve efficiency while implementing _this " Augmented Testing Program" alongside the IST Program. Each affected valve is clearly marked as "NC" (meaning non-Code Class) in the Valve Tables. Furthermore, to minimize confusion, CCNPP chose to include " cold shutdown / refueling justifications" and " relief requests" for these non-Code valves to maintain consistency and clearly identify the basis for any
" deviations" from the Code, llowever, these arc included in the IST Program Plan 7
3.4 - Augmented Testing Program for Non Code Class Pumps and Valves (Continued) only to avoid the appearance that CCNPP is not performing all required IST testing for the applicable Code Class pumps and valves. 4.0 - INSERVICE TESTING PROGRAM FOR PUMPS 4.1 Code Compliance
'Ihe IST Program for pumps meets the requirements of Reference 2.8, Part 6 and any applicable interpretations or clarifications of existing requiretrents provided by References 2.7 and 23. Paragraph and table references in this section refer to specific paragraphs and tables in Reference 2.8. Where these requirements have been detennined to be impractical, conformance would cause unreasonable hardship without any corapensating increase in safety, or an alternative test provides an acceptable level of quality ud safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR -
50.55a(f)(5)(ii0 and, References 2.7 and 2.9.(See Appendix C) 4.2 Allowable Ranges of Test Quantities The allowable ranges for test parameters as specified in Reference 2.8, Part 6, Table 3 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief requests. 4.3 Testing Intervals The test frequency for pumps included in the Program will be as set forth in Reference 2.8, Part 6, Section 5, and Reference 2.9, Paragraph 5.1.1, and related relief requests. An allowable extension, not to exceed +25 percent of the surveillance interval, may be applied to a test schedule as allowed by the Calvert Cliffs Nuclear Power Plant Technical Specifications to provide for operational Cexibility.
- The frequencies used for scheduling pump tests are defined as:
-Quarterly - 92 days -
Refueling - 730 days Cold Shutdown - Per the applicable Relief Request consistent with the cold shutdown testing requirements for valves of Referenc( '.8, ' Part 10, Paragraphs 4.2.1.2 (f), (g), & (h) and 4.3.2.2 (f), (g), & (h), and Reference 2.9, Sections 3.1,1, 3.1.1.1 & 3.1.1.2. % hen all cold shutdown testing will not be completed, priorities for testing will be established per approved CCNPP procedures. 8
4.4 Pump Program Tables Appendices A and B list those pumps included in the IST Prognm with references to parameters to be measured and applicable requests for relief. 4.5 Relief Requests for Pump Testing-Relief requests PR-01 through PR-10 are submitted per 10CFR50.55a where appropriate and are included in Appendix C. l 4.6 Instmment Accuracy - Instruments will meet the requirements specificciin Reference 2.8, Part 6, Paragraph 4.6 and amplified in Reference 2.9, Section 5, except where specific
- relief is granted.
=5.0 INSERVICE TESTING PROGRAM FOR VALVES 5.1 Code Compliance This IST Program for valves meets the requirements of Reference 2.8, Paits 1 and 10 and any applicable interpretations or clarifications of existing requirements provided by References 2.7 and 2.9. Pamgraph and table references in this section refe4 to specific paragraphs and tables in Reference 2.8. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality _-
and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(f)(5)(iii) and Reference 2.7. (See Appendix F) 5.2 Stroke Time Acceptance Criteria
- When mquired, the acceptance criteria for the stroke times of power-operated valves will be as set forth in References 2.7 and 2.8.
5.3 ~ Check Valve Testing Full-stroke exercising of check valves to the open position using system flow will be via a test in which the predicted full accident condition flowrate (allowing for analytical and instrument uncertainties) through the valve is measured / verified or full stroke of the disk is verified by appropriate non-intmsive methods or ot_her positive means. Any deviation to this requirement will satisfy the requirements of Reference 2.7, Position 1 or as set forth in ( requests for relief. 9
5.3 Check Valve Testing (Continued) Under !,ome circumstances, closure testing of a check valve may be performed by verifying that a valve is closed without pre-exercising to the open position.
. Ihis is acceptable if the valve (1) performs only a closed safety function, (2) is normally closed, and (3) the closed position can be monitored during normal plaa operation, Funhermore, if verification of closure is practical on a quanerly basis and verification following opening is possible_ on an extended frequency (cold shutdown or efueling), then this combination is also acceptable. (Refenence NUREG-1482, Appendix A, QuTJon Group 24)
When active check valves cannot be full stroke exeteised quarterly, they are part-stroke exercised to the maximum extent practicali Pan stroking may take l' many forms. The following are typical examples of pan-stroke exercising:
- a. Exercising a check valve partially open by passing flow thinugh it at less than the required accident flowrate, b,
Exercising a check valve panially open by creating a pressure 1 increase / surge upstream of the check valve and verifying the pressure increase / surge is transmitted downstream of the check valve.
- c. Exercising a check valve closelne-driven horizontal centrifugal DISC PRESS Test parameter - discharge pressure DIFF. PRESS Test parameter - pump differential pressure FLOWRATE Test parameter - flowrate SPEED Test parameter - pump rotational speed VIBRATION Test parameter - pump vibration NOTE The respective table indicates by a "YES" or "NO" that the specific parameter.-
is measured, evaluated, and recorded per the applicable Code requirement. If a "NO" is indicated or the parameter is measured in a manner not strictly specified by the Code, the associated relief request number (PR-XX) is noted in the same column. "NA" indicates that tne specific parameter is not applicable to this pump.
CALVERT CLIFFS NUCLEAR POWER PLANT - UNIT I INSERVICE usnNG PLAN - PUMPS Page A-2 TEST PARAMETERS PUMP NAME PUMP NO. DWG NO. COOR TYPE DISC. PRESS DIFF. PRESS FLOWRATE SPEED VIBRATION INTERVAL Auxiliary Feedwater 11 60-583-E C-10 THC N/A YES YES/PR-02 YES YES Qtr/CSD Auxiliary Feedwater 12 60-583-E F-10 THC N/A YES YES/PR-02 YES YES Qtr/CSD Auxiliary Feedwater 13 60-583-E H-9 MHC N/A YES YES/PR-03 N/A YES Qtr/CSD Boric Acid 11 60-730-E-1 G-9 MHC N/A YES YES N/A YES Qtr Caric Acid 12 60-730-E-1 H-11 MHC N/A YES YES N/A YES Qtr Component Cooling i1 60-710-E-1 E-5 MHC N/A YES YES N/A YES Qtr Component Cooling 12 60-710-E-1 G-5 MHC N/A YES YES N/A YES Qtr Component Cooling 13 60-710-E-1 H-5 MHC N/A YES YES N/A YES Qtr Containment Spray 11 60-731-E-3 B-9 MHC N/A YES YES/PR-06 N/A YES Qtr/CSD Containment Spray 12 60-731-E-3 F-9 MHC N/A YES YES/PR-06 N/A YES Qtr/CSD I A-EDG Fuel Oil Trans. I1 62-437-E D-4 MHC NA YES YES N/A YES Qtr I A-EDG Fuel Oil Trans. 12 62-437-E D-4 MHC NA YES YES N/A YES Qtr
CALVERT CIlFFS NUCLEAR POWER PLANT - UNIT I INSERVICE TESTING PLAN - PUMPS Page A-3 TEST PARAMETERS PUMP NAME PUMP NO. DWG NO. COOR. TYPE DISC. PRESS DIFF. PRESS FLOWRATE SPEED VIBRATION INTERVAL j High Pressure injection i1 60-731-E-1, D-7 MHC N/A .YES . YES/PR-03 N/A YES Qtr/CSD High Pressure injection ~12 60-731-E-1 E-7 MHC N/A YES YES/PR-04 N/A YES Qtr/CSD High Pressure Injection 13 60-731-E-1 G-7 MHC N/A YES YES/PR-04 N/A YES Qtr/CSD Low Pressure injection iI 60-731-E-1 ' B-7 MHC N/A YES YES/PR-01 N/A. YES Qtr/CSD Low Pressure Injection 12 60-731-E-1 H-7 MHC N/A YES YES/PR-01 N/A YES Qtr/CSD Rx. Coolant Charging i1 60-731-E-2 . F-7 RPD YES NO YES ' YES YES/PR-05 Qtr Rx. Coolant Charging 12 60-731-E-2 G-7 RPD YES NO YES YES YES/PR-05 Qtr Rx. Coolant Charging 13 60-731-E-2 H-7 RPD YES NO YES YES YES/PR-05 Qtr Saltwater Cooling i1 60-708-E-2 C-10 VDC N/A YES/PR-08 YES/PR-08 NO YES/PR-09 Qtr Saltwater Cooling 12 60-708-E-2 C-8 VDC N/ A YES/P".-08 YES/PR-08 NO YES/PR-09 Qtr Saltwater Cooling 13 60-708-E-2 C-5 VDC N/ A YES/PR-08 YES/PR-08 NO YES/PR-09 Qtr L._________________ - - - - - -
l CALVERT CUFFS NUCLEAR POWER PLANT . UNIT 1 INSERVICE TESTING PLAN - PUMPS Page A-4 TEST PARAMETERS PUMP NAME PUMP NO. DWG NO. COOR. TYPE DISC. PRESS DIFF. PRESS FLOWRATE SPEED VidRA1KM4 INTERVAL Service Water 11 60-706-E-2. E-2 MHC N/A .YES YES NO YES. Qtr ' Service Water 12 60-7%E-2 F-2 MHC- N/A YES YES NO YES Qtr " Service Water 13 60-706-E-2 G-2 MHC N/A YES YES NO YES , Qtr . e ___.___a -_._
- Page B-1 LEGEND FOR PUMP TABIRt
]
PUMP NAME Generic name/ function of the pump. PUMP NO.- Numerical designator ind:cated on the aspective flow diagram. DWG NO. Corresponds to the flow diagram or drawing COORD Drawing coordinates of the pump on the flow diagram TYPE Type of pump as fol'pws: MHC Motor-driven horizontal centrifugal RPD Reciprocating positive displacement MVC Motor-Driven vertical line shaft centrifugal l THC. TuMne-driven horizontal centrifugal DISC.' PRESS Test parameter - discharge pressure DIFF. PRESS Test parameter - pump diffemntial pressum FLOWRATE Test parameter - flowrate SPEED Test parameter - pump rotational speed VIBRATION Test parameter - pump vibratlon NOTE The respective table indicates by a "YES" or "NO" that the specific parameter is measured, evaluated, and recorded per the applicable Code requirement. If a "NO" is indicated or the parameter is measured in a manner not strictly specified by the Code, the associated relief mquest number (PR-XX) is noted in the same column. "NA" indicates that the specific parameter is not applicable to this pump.
CALVERT CLIFFS NUCLEAR POWER PLANT - UNIT 2 INSERVICETESTING PLAN- PUMPS Page B-2 TEST PARAMETERS PUMP NAME PUMP NO. DWG NO. _C_QQR m TYPE DISC. PRESS DIFF. PRESS FLOWRATE SPEED VIBRATION INTERVAL Auxiliary Feedwater 21 62-583-E C-10 THC N/A YES ' YES/PR-02 YES YES' Qtr/CSD Auxiliary Feedwater 22 62-583-E F-10 THC N/A YES YES/PR-02 YES YES Qtr/CSD ' Auxiliary Feedwater 23 62-583-E H-9 MHC N/A YES YES/PR-03 N/A YES Qtr/CSD ' Boric Acid 21 62-730-E-1 G-9 MHC N/A YES YES N/A YES Qtr Boric Acid 22 62-730-E-1 H-il MHC N/A YES YES N/A YES Qtr Component Cooling 21 62-710-E-1 I-5 MHC N/A YES YES N/A YES Qtr Component Cooling 22 62-710-E-1 G-5 MHC N/A YES YES N/A YES Qtr Component Cooling 23 62-710-E-1 E-5 MHC N/A YES YES N/A YES Qtr - Containment Spray 21 62-731-E-3 B-9 MHC N/A YES YES/PR-06 N/A YES Qtr/CSD Containment Spray 22 62-731-E-3 F-9 MHC N/A YES YES/PR-06 N/A YES Qtr/CSD High Pressure injection 21 62-731-E-1 D-7 MHC N/A YES .YES/PR-04 N/A YES Qtr/CSD High Pressure Injection 22 62-731-E-1 E-7 MHC N/A YES YES/PR44 N/A YES Qtr/CSD High Pressure Injection 23 62-731-E-1 G-7 MHC N/A YES YES/PR-04 N/A YES Qtr/CSD
--,.--.__---,-r--, , - - - - - - - - - - - , - - - - - - - - - - - - - - - - -
A'- CALVERT CUFFS NUCLEAR POWER PLANT - UNIT 2 INSERVICE TESTING PLAN - PUMPS Page B-3
]
TEST PARAMETERS PUMP NAME PUMP NO.- DWG NO. COOR. TYPE DISC. PRESS DIFF. PRESS FLOWRATE SPEED VIBRATION DUERVAL Low Prnsure Injection 2! 62-731-E-1 C-7 MHC. 'N/A YES ' YES/PR-01 N/A YES Qtr/CSD' Low Pressure Injection 22 62-731-E-1 H-7 ' MHC ' N/A YES YES/PR-01 N/A YES- ,Qtr/CSD , Rx. Coolant Charging . 21 62-731-E-2 F-7 RPD. YES NO YES YES YES/PR-05 Qtr Rx. Coolant Charging 22 62-731-E-2 G-7 RPD YES NO YES 'YES YES/PR-05 Qtr Rx. Coolant Charging 23 62-731-E-2 H-7 .RPD YES NO .YES 'YES YES/PR Qtr Saltwater Cooling 21 62-708-E-2 C-5 VDC N/A YES/PR48 YES/PR-08 ' NO YES/PR-09 Qtr ' Saltwater Cooling 22 62-708-E-2 C-8 VDC. N/A YES/PR-08 . YES/PR-08 NO YES/PR-09 . Qtr . Saltwrder Cooling 23- 62-708-E-2 C-10 VDC N/A YES/PR-08 YES/PR-08 NO YES/PR-09 ' Qtr Service Water 21 62-706-E-2 E-2 MHC N/A YES .YES NO YES ..Qtr Service Water 22 62-706-E-2 F-2 .MHC N/A YES YES NO YES V Service Water 23 62-706-E-2 H-2 MHC N/A YES YES NO YES Qtr
Page C-1 RELIEF REQUEST NO. PR-01
- COMPONENTS' Lew Pressure Safety Injection (LPSI) Pumps PART 6 REOUIREMENT:.
Where system resistance cannot be varied, flowrate and pressure shall be determined and compared to their respective reference value. (Part 6, Para. 5.2(c)) BASIS FOR BRT M:
- During quarterly testing of the LPSI pumps, flow is routed through a minimum flow recirculation line returning boated water to the refueling water tank (RWT). This recirculation flowpath is capable of passing a flowrate appmximately 1 percent of that at the pump design operating point. A flow instrument is installed on this recirculation
. piping; however, there is concern regarding the practice of thmttling under minimum flow conditions with the potential for causing pump damage. In addition, hydraulic pump test data at or near a pump's shutoff head provides little infonnation as to the mechanical condition of a pump.-
NRC Generic Letter 89-04, Position 9, (Reference 2.7) allows climination of minimum flow test line flowrate measurements providing inservice tests are performed during cold shutdowns or refueling under full or substantial flow conditions where pump
' flowrate is recordcd and evaluated. The proposed alternate testing is consistent with the philosophy and the intent cf Position 9.
These pumps are standby pumps and little degradation is expected with respect to hydraulic performance during operational periods when the pumps anc idle. Thus, tie alternate testing will provide adequate monitoring of these pumps with respect to the applicable Code requirements to ensure continued operability and availability for accident mitigation.
' ALTERNATE TESTING:
During quarterly testing of the LPSI pumps, a fixed-resistance test circuit will be used and pump differential pressure, vibration, and flowrate will be measured. Pump differential pressure and vibration measurements will be compared to their respective reference values per Part 6, Para. 5.2(c) while flowrate will only be verified to be greater than the minimum flow requirement. e
PageC-3 RELIEF REQUFJiT NO. PR 01 (cont.) ALTERNATH TESTING (cont.h During testing performed at cold shutdown or refueling, pump differential pressure, flowrate, and vibration will be recorded and evaluated as per Part 6 Para. 5.2(b). Testing during cold shutdowns will le scheduled / performed as follows:
- 1. Fo, a :d shutdown periods occurring at intervals of less than 3 months -
testing is not toquired unless 3 rr.onths have passed since the last cold shutdown tr.ct. l 2.. For cold . 'utdown periods occurring at intervals of 3 months or longer - l cach shutdown, to the mrximum extent pmetical. The above statements regarding cold shutdown testing are subject to the following:
- 1. Cold Sht.tdown Testing will commence within 48 hours of ente.bg the applicable Mode reqdred for testing and continue, to the maximum extent practical, until testing of all pumps and valves designated for cold f
shutdown testing during the outage is complete or the unit is otherwise ready to retum to power.
- 2. Where plant conditions or other circumstances arise that preclude testing of 1. pump, a unit will not be retained in a lower Mode or Mode 3 for the sole purpose of completing testing nor will the plant be reduced to a lower Mode solely for the purpose of completing testing.
- 3. For those cases where purnps can be tested during power ascension and v r<te the Technical Speellication requirements for the pumps or system determine when the pump is rtquired to be operable, tests may be performed during power ascension without regard to the 48 hour starting time,
- 4. For extended outages, testing need not be commenced within 48 hours provided all required testing is completed prior to startup.
l l Page C 3 1 1
- RElJEF REQUEST No. PR 02 I
i
- COMPONENTS
Steam Driven Auxiliary Feedwater (AFW) Pumps 11,12,21, and 22 l PART 6 REQUIREMENT: i i _ ! Where system resistance cannot be varied, nowrate and pressure shall be determined l l and compared to their respective reference value. (Part 6, Para. 5.2(c)) ' l BASIS FOR RELIEF: i l Full or substantial flow testing of these pumps is not practical during plant operation at i
- power due to the potential for thermal shock of the steam generator nozzles or
i intemals. Thus, during quarterly testing of the AFW pumps, How is routed through a
- minimum now recirculation line retuming condensate to the condensate storage tank
! and the respective pump suction line. This recirculation flowpath is capable of passing i [ a Dowrate somewhat less than 10 percent of tint at the pump design operating point. A l i flow instrument is installed on this recirculation piping; however, there is concern ! regarding the pmetice of throttling under minimum now conditions with the potential ! for causing pump damage. ~ In addition, hydraulic pump test data at or near a pump's j shutoff head provides little information as to the mechanical condition of a pump. 4 During cold shutdown conditions steam may or may not be available for turbine , opention depending on the cirrumstances of the cold shutdown. It is not desirable to l use auxiliary steam for this purpose. - t , NRC Generic Letter 89_-04, Position 9, (Peference 2.7) allows elimination of minimum ' t
- now test line flowrate measurements providing inservice tests are performJ during L
cold shutdowns or afueling under full or substantial Dow conditions where pump j flowrate is recorded and evaluated. The proposed alternate testing is consistent with ] _ the philosophy and the intent of Position 9.- These pumps are standby pumps and little degndation is expected with respect to ? hydraulle performance during operational periods when the pumps are idle. Thus, the alternate testing will provide adequate monitoring of these pumps with respect to the ; applicable Code requirements to ensure continued operability and availability for accident mitigation. 1. Y t
- =-
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- 3' g -w g - ww eve ww---et-9 -a.--qvmwo ----m wg pr m w4ey+,ip- m
Page C-4 RELIEF REQUEST NO. PR 02 (cont.) ALTERNATE TESTING: During quarterly testing of the AFW pumps, a fixed diance test circuit will be used and pump differential pressure, vibration, and flowrate will be measured. Pump differential pressure and vibration measurements will be compared to their respective reference values per Part 6, Paragraph 5.2(c) while flowrate wl!! only be verified to be greater than the minimum flow requirement. During testing performed at cold t.hutdown or refueling, pump differential pressure. l flowrate, and vibration will be recordcJ and evaluated as per Part 6, Para. 5.2(b). Testing during cold shutdowns will ta scheduled / performed as follows:
- 1. For cold shutdown periods occurring at intervals of less than 3 months -
testing is not required unless 3 months have passed since the last cold shutdown test.
- 2. , For cold shutdown periods occurring at intervals of 3 months or longer -
each shutdown, to the maximum extent practical. The above statements regarding cold shutdown testing are subject to the following:
- 1. Cold Shutdown Testing will commence within 48 hours of entering the applicable Mode required for testing and continue, to the maximum extent practical, until testing of all pumps and valves designated for cold shutdown testing during the outage is complete or the unit is otherwise ready to retum to power.
- 2. Where plant conditions or other circumstances arise that pnsclude testing of a pump, a unit will not be retained in a lower Mode or Mode 3 for the sole purpose of completing testing nor will the plant be reduced to a lower Mode solely for the pu: pose of completing testing.
- 3. For those cases where pumps can be tested ouring power ascension and where the Technical Specification requirements for the pumps or system determine when the pump is required w be operable, tests may be perfonned during power ascension without regard to the 48 hour stanting time.
- 4. For extended outages, testing need not be commenced within 48 hours provided all required testing is completed prior to startup.
-:: - - = = - =i=
Page C-5 RELIEF REQUEST NO. PR-03 COMPONENTS: Motor Driven Auxiliary Feedwater (AFW) Pumps 13 and 23 PART 6 REOUIREMENT1 Where system resistance cannot be varied, flowrute and pressure shall be determined and compared to their respective reference value. (Part 6, Para. 5.2(c)) l BASIS FOR RRr1RF:
- Full or substantial flow testing of these pumps is not practical during plant opemtion at power due to the potential for thermal shock of the steam generator nozzles or '
intemals. 'Ihus, during quarterly testing of the AFW pumps, flow is routed through a minimum flow recirculation line returning condensate to the condensate storage tank and the respective pump suction line. This recirculation flowpath is capable of passing a flowrate somewhat less than 10 percent of that at the pump design operating point. A Dow instrument is installed in this recirculation piping; however, there is concern regarding the practice of throttling under minimum flow conditions with the potential for causing pump damage. In addition, nydraulle pump test data at or near a pump's shutoff head provides little information as to the mechanical condition of a pump. NRC Generic Letter 89-04, Position 9, (Reference 2.7) allows elimination of minimum Dow test line flowrate measurements providing inservice tests are performed during cold shutdowns or refueling under full or substantial flow conditions where pump Dowrate is recorded and evaluated. The proposed alternate testing is consistent with the philosophy and the intent of Position 9. These pumps are standby pumps and little degradation is expected with respect to hydmulle performance during operational periods when the pumps are idle. Thus, the alternate testing will provide adequate monitoring of these pumps with respect to the applicable Code requirements to ensure continued operability and availability for accident mitigation. ALTERNATE TESTING: During quarterly testing of the AFW Pumps 13 and 23 a fixed-resistance test circuit will be used and pump differential pressure, vibration, and flowrate will be N
Page C 6 RELIEF REQUEST NO. PR-03 (cont.) ALTERNATE TESTING (cont.): measured. Pump differential pressure and vibration measurements will be companxl to their respective reference values per Paragraph 5.2(c) while flowrate will be only-
._ verified to be greater than the minimum flow requirement.
During testing perfonned at cold shutdown or refueling, pump differential pressure, flowrate, and vibration will be recortled and evaluated as per Part 6, Para. 5.2(b). Testing during cold shutdowns will be scheduled / performed as follows: l 1. For cold shutdown periods occurring at intervals of less than 3 months - l testing is not required unless 3 months have passed since the last cold { shutdown test. 2.. For cold shutdown periods occurring at intervals of 3 months or longer - each shutdown, to the maximum extent practical. The above statements regarding cold shutdown testing sre subject to the following:
- 1. Cold Shutdown Testing will commence within 48 hours of entering the applicable Mode required for testing and continue, to the maximum extent practical, until testing of all pumps and valves designated for cold shutdown testing during the outage is complete or the unit is otherwise ready to return to power,
- 2. Where plant conditions or other circumstances arise that preclude testing of a pump, a unit will not be retained in a lower Mode or Mode 3 for the sole purpose of completing testing nor will the plant be reduced to a lower Mode solely for the purpose of completing testing.
- 3. For those cases where pumps can be testcd during power ascension and .
where the Technical Specification requirements for the pumps or system determine when the pump is required to be operable, tests may be performed during power ascension without regard to the 48 hour starting time.
- 4. For extended outages, testing need not be commenced within 48 hours provided all required testing is completed prior to startup.
~~ . , ~ . - . - . . _ _ - --- - - - - _ . _ - - - . - - - - - - _- -
Page C-7 RELIEF REQUFET NO, PR 04 4 COMPONENTjSi Illgh Pressure Safety Injection (IIPSI) Pumps PART 6 REOUIREMENT: Where system resistance cannot be varied, Howrate and pressure shall be determined and comparal to their respective reference value. (Part 6, Para. 5.2(c)) BASIS FOR RF11FF: During quarterly testing of the IIPSI Pumps, the pumps cannot develop sunicient discharge pressure to overcome RCS pressure and allow flow thmugh the safety injection line. Thus, during quarterly testing of the IIPSI pumps, flow is muted thmugh a minimum flow recirculation line returning boric acid solution to the refueling water tanks. This l recirculation flowpath is capable of passing a flowrate somewhat less than 10 percent of that at the pump design operating point. A flow instru:nent is installed on this recirculation piping; however, there is concern regarding the practice of thmttling under minimum flow conditions with the potential for causing pump damage. In addition, hydraulic pump test data at or near a pump's shutoff head provides little infonnation as to the mechanical condition of a pump. During cold shutdown corklitions, full flow operation of the HPS! pumps to the RCS is restricted to preclude RCS system pressure transients due to mass addition that could result in exceeding the pressure-temperature limits specified in the Technical Specifications (L'IDP), unless the RCS is de-pressurized and the pressurizer manway is removed. However, under certain circumstances it is possible to line-up tie IISPI pumps so that they take their suction fmm the RCS to preclude mass addition and a resulting pressure transient. NRC Generic Letter 89-04, Position 9, allows elimination of minimum flow test line flowrate measurements providing inservice tests are perfonned during cold shutdowns or refueling under full or substantial flow conditions where pump flowrate is recorded and evaluated. The propsed attemate testing is consistent with the philosophy and the intent of Position 9.
- - . - - - . - - . ~ . - - - . - - . - . - - - - . . - - - .
l l l l Page C 8 [ ] - 4 ! REIJEF REQUEST NO. PR 04 (cont.) i .
- ALTERNATE TESENG: i l <
i Dudng quarterly testing of the HPSI pumps a fixed resistance test circuit will be used i { and pump differential pressure, vibration, and nowrate will be measured. Pump i differential pressure and vibration measurements will be compared to their nespeedve reference values per Paragraph 5.2(c) while nowrate will only be verified to be greater , i than the minimum now reguliement. ! t During testing performed at cold shutd'o wn or refueling, pump differential pressure, d Howrate, and vibration will be recorded ahd evaluated as per Part 6, Para. 5.2(b), [ Testing during cold shutdowns will be scheduled / performed as follows:
- 1. For cold shutdown perbds occurring at intervals of less than 3 months - t l testing is not required unless 3 months have passed since the last cold ;
2 shutdown test. !
- 2. , For cold shutdown periods occurring at intervals of 3 months or longer -
5-each shutdown, to the maximum extent practical. r i The above statements regarding cold shutdown testing are subject to the following: i
- 1. Cold Shutdown Testing will commence within 48 hours of entering the l >
i applicable Mode required for testing and continue, to the maximum extent practical, until testing of all pumps and valves designated for cold shutdown testing during the outage is complete or the unit is otherwise - ) ready to retum to power. ; i i j 2. Where plant conditions on other circumstances arise that preclude testing j of a pump, a unit will not be retained in a lower Mode or Mode 3 for the sole purpose of completing testing nor will the plant be reduced to a !
- i. lower Mode solely for the purpose of completing testing.
} 3. For those cases where pumps can be tested during power ascension and where the Technical Specification requirements for the pumps or system determine when the pump is required to be operable, tests may be i performed during power ascension without regard to the 48 hour starting ; ! __ time, t
- 4. For extended outages, testing need not be commenced within 48 hours
[ provided all required testing is completed prior to startup, i i 1
. . . _ - , , , , , .__;.. . _ , , , _ _ _ , _ , . . _ , .._,_.,,._,___m, - , _ _ _ _ . . . _ , , . , _ , _ . . , _ , _ _ , , _ _ . , , , _ _ _ _ . , _ , , , _ . _ , _ . . _ . , -
Page C 9 RELIEF REQUEJiT NO. PR 05 COMPONENTS: Reactor Coolant Charging Pumps PART 6 REOUIREMENT: The frequency response range of the vibration measuring transducers and their readout system shall be from one third minimum pump shaft rotational speed to at least 1000
- Hz. (Paragraph 4.6.1.6)
BASIS FOR RRr1RP: __ De rotational shaft speed of the charging pumps is 209 rpm relating to a rotational frequency of approximately 3.48 Hz. In order to satisfy the requirements of Paragraph 4.6.1.6, a vibration measurement system capable of measuring vibration to a lower limiting frequency of 1.16 Hz. would be required. The instruments currently being used at Calvert Cliffs have a lower frequency limit for reliable, accurate measurement of 4 Hz. This instrumentation is " state-of the art" industrial grade, high quality equipment. Satisfying the Code requirements with respect to frequency response would require the unnecessary procurement of new and more sophisticated equipment beyond that intended by the Code. Monitoring lower frequencies (less than rotational speed) is performed primarily for the purpose of detecting oil whirl or whip in journal bearings. The Calvert Cliffs charging pumps main bearings use oil-mist lubricated roller bearings that are not susceptible to the oil whip or whirl phenomena. Other conditions that could result in low frequency vibration (less than shaft speed) are included in the general category of mechanical " rub" which is not considered to be-significant from the aspect of pump degradation. Thus, it can be deduced that the instrumentation currently in use is adequate for determining pump degradation that may manifest itself in increased vibration, in addition to the ASMB pump testing, Calvert Cliffs also has implemented a " Rotating Machinery Vibration Monitoring Program" that includes periodic vibration monitoring of the charging pumps. This program is inclusive and encompasses a wider range of vibration analyses at several critical pump and motor locations,
Page C 10 RELIEF REQUEST NO. PR 05 (cont.) BASIS FOR BR11RF (contJ; ne data derived fmm this expanded pmgmm along with the IST vibration data will pmvide a high degree of assurance that significant pump degradation will not go undiscovered. ALTERNATE TESTING: ne instruments used for measuring vibration on the scactor charging water pumps will have a frequency response range that extehds to a lower limiting frequency of 4 Hz. or less, ne charging pumps will be included in the CCNPP " Rotating Machinery Vibration Monitoring Prognm" that includes periodic vibration monitoring and analysis of each pump.
l 1 Page C Il i RELIEF REQUEST NO. PR 06 COMPONENTS-Containment Spray Pumps PART 6 REOUIREMRNT: Where system resistance cannot be varied, 00wrate and pressure shall be detennined and compared to their respective reference value. (Part 6, Para. 5.2(c))
- BASIS FOR RRr 1RF:
1 During quarterly testing of the containment spray pumps, now is routed thmugh a minimum flow recirculation line returning borated water to the refueling water tank (RWT) to avoid pumping water through the spray headers and spraying down , containment with borated water, nis recirculation Dowpath is capable of passing a Dowrate appmximately 3 percent of that at the purnp design operating point. A Dow instrument is installed on this recirculation piping; however, there is concem regarding the practice of throttling under minimum now conditions with the potential for causing pump damage. In addition, hydraulic pump test data at or near a pump's shutoff head provides little infonnation as to the mechanical condition of a pump. NRC Generic letter 89-04, Position 9, (Referene 2.7) allows climination of minimum How test line Dowrate measurements providing inservice tests are performed during cold shutdowns or refueling under full or substantial now conditions where pump flowrate is reconied and evaluated. The proposed attemate testing is consistent with the philosophy and the intent of Position 9.
- Perfonning full Dow testing of a CS pump requires substituting it for the running LSPI pump in the shutdown cooling (SDC) line up. However, nonnat SDC flow is '
appmximately 3000 gpm and a CS pump pmvides only appmximately 1500 gpm. Therefore, this test can only be safely perfonned after enough time has elapsed since shutdown to allow the decay heat rate to substantially diminish. These pumps are standby pumps and little degradation is expected with respect to .c hydraulic performance during operational periods when the pumps are idle. Bus, the altemate testing will pmvide adequate monitoring of these pumps with respect to the applicable Code requirements to ensure continued operability and availability for accident mitigation.
i 5 Page C 12 I
; RELIEF REQUEST NO. PR 06 (cont.)
j j ALTERNATE TESTING: t During quarterly testing of the containment spmy pumps, a fixed resistance test circuit
!' will be used and pump differential pressure, vibration, and flowrate will be measured.
Pump differential pressure and vibration measurements will be compared to their respective reference values per Paragraph 5.2(c) while flowrate will only be vedfici to be greater than the minimum flow requirement. , During testing performed at cold shutdown or refueling, pump differential pressure, flowrate, and vibration will be recorded and evaluated as per Part 6, Para. 5.2(b). ' 4 . I Testing during cold shutdowns will be scheduled /perfonned as follows: ] 1. For cold shutdown periods occurring at inteivals of less than 3 months - l testing is not required unless 3 months have passed since the last cold i
- shutdown test. -
j 2.. For cold shutdown periods occurring at intervals of 3 months or longer - cach shutdown, to the maximum extent practical. 1. 4 The above statements regarding cold shutdown testing are subject to the following: i i 1. Cold Shutdown Testing will commence within 48 hours of entering the l' applicable Mode required for testing and continue, to the maximum extent practical, until testing of all pumps and valves designated for cold j shutdown testing during the outage is complete or the unit is otherwise i ready to return to power, i 2. I Where plant conditions or other circumstances arise that preclude testing l of i pump, a unit will not be retained in a lower Mode or Mode 3 for the ' i sole purpose of completing testing nor will the plant be reduced to a j lower Moda solely for the purpose of completing testing, j 3. For those cases where pumps can be tested during power ascension and where the Technical Specification requirements for the pumps or system detennine when the pump is required to be operable, tests may be _ performed during power ascension without regard to the 48 hour starting time. 4-
; 4. For extended outages, testing need not be commenced within 48 hours
- provided all required testing is completed prior to startup, i ,
1
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Page C 13 REI.IEF REQUEST NO. PR 07 COMPONEtES2 Reactor Coolant Charging Pumps WITIIDRAWN l
l-Page C 14 RELIEF REQUEST NO. PR 08 COMPONENTS: Saltwater Cooling Pumps PART 6 REOUIREMENT: Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared to the limits given in Table 3a and corrective action taken is specified in para. 6.1. (Paragraph 5.2(d)) The limits presented in Table 3 for vertical line shaft pumps are as follows: Diff. Pressure Acceptable Range 0.95 to 1.10 dP, Alert Range 0.93 to <.95 dP, Required Action Range <0.93 dP, and > 1.10 dP, and Flowrate Acceptable Range 0.95 to 1.10Q, Alert Range 0.93 to < .95Q, Required Action Range <0.93 Q, and > 1.10 Q, On vertical line shaft pumps, measurements (vibration) shall be taken on the upper motor bearing housing 10 three onhogonal directions, one of which is the axial direction. (Paragraph 4.6.4(b)) BASIS FOR RRIIEF: These pumps neet the strict definition of a vertical line shaft pump stated in NUREG-1482, Paragraph 5.9 where such a pump is described as "a vertically suspended pump, where the pump driver and pumping element are connected by a line shaft within an enclosing column which contains the pump bearings, making pump bearing vibration measurements impracticable" with the exception of the impracticality of mt:asuring pump vibration. These pumps are mounted in a dry pit located at the intake structure with pump orientation such that they take suction through the intrke stmeture floor with the drive motor mounted on an elevated platform above the pump and connected to the pump via a verileal shaft. This design allows pump operation in the event of flooding. l
Page C-15 RELIEF REQUEST NO. PR-08 (cont.) BASIS FOR NRr rEF (conL); NUREG 1482 states that the basis for the more restrictive hydraulle acceptance criteria for vertical line shaft pumps is due to " inherent deficiencies in vibration resting." In this case there are no restrictions to perfonning vibration measurements as assumed by j the Code for normal pump configuration (non vertical line shaft pumps). Thus, with
- the ability to adequately monitor pump vibration, it is not necessary to apply the more L restrictive hydraulle acceptance criteria. Clearly, the more restrictive limits are not i required in this case to meet the Code requirement of assessing pump operational
{ readiness. - I ALTERNATE TESTING' b j During toutine inservice testing of these pumps vibration measurements will be taken as ! required for centrifugal pumps per Part 6, Paragraph 4.6.4(a). I Pressure, flow rate, and vibration (displacement or velocity) will be determined and 3 compared with corresponding reference values. All deviations from the reference 4 values will be compared to the limits given in Table 3a for centrifugal pumps (see , below) and corrective action taken as specified in para. 6.1. (Paragraph 5.2(d)) l The limits presented in Table 3a for centrifugal pumps are as follows: Diff. Pressure Acceptable Range 0.90 to 1.10 dP, Required Action Range <0.90 dP, and > 1.10 dP, and ! i4owrate Acceptable Range 0.90 to 1.10 Q, Required Action Range <0.90 Q, and > 1.10 Q, i g i a
Page C 16 RELIEF REQUEST NO. PR-09 COMPONPNTS: l Salt Water Cooling Pumps - PART 6 REOUIREMENE The free scy response range of the vibration incasuring transducers and their readout ; system shall be from one third minimum pump shaft rotational speed to at least 1000 Hz. (Paragraph 4.6.1.6) , BASIS FOR RMI TEF: - The speed of the saltwater cooling (SW) pumps is approximately 585 rpm relating to a mtational frequency of 9.75 Hz. In order to satisfy the requirements of Paragraph 4.6.1.6, a vibration measurement system capable of measuring vibration to a lower limiting frequency of 3.25 Hz, would be required. l l The instruments currently being used at Calvert Cliffs have a lower frequency limit of l 4 Hz. This instrumentation is " state-of the-art" industrial grade, high quality equipment. Satisfying the Code requirements with respect to frequency response would require the unnecessary procurement of new and more sophisticated equipment beyond that intended by the Code.- t Monitoring lower frequencies (less than rotational speed) is pe formed primarily fof the i purpose of detecting oil whirl in the pump journal bearings. Other conditions that - could result in low frequency vibration (less than shaft speed) are included in the general category of mechanical " rub" which is not considered to be significant from the aspect of pump degradation. These pumps are provided with grease lubricated roller bearings that are not susceptible to oil related vibration problems, f Vibration measurements taken on these pumps with instruments capable of monitoring - frequencies to 4 Hz. Will satisfy the intent of the Code - that of reading vibration at frequencies "Just" less than one-half the rotating frequency. In addition to the ASMB pump testing, Calvert Cliffs also has implemented a " Rotating Machinery Vibration Monitoring Program" that includes periodic vibration m'onitoring of the saltwater pumps. This program is inclusive and encompasses a wider range of vibration analyses at several critical pump and motor locations.
Page C-17 RELIEF REQUEST NO. PR-09 (cont.) l ALTERNATE TESTING' l l The instruments used for measuring vibration on the salt water cooling pumps will have a frequency response range that extends to a lower limiting frequency of 4 Hz, or less. l The saltwater pumps will be included in the CCNPP " Rotating Machinery Vibration Monitoring Pmgnm" that includes periodic vibration monitoring and analysis of each pump. c 9 l f n
Page C 18 RELIEF REQUEST NO. PR 10 COMPONENTS: Various - This is a generic request for relief. PART 6 REOUIREMENT: l l Pressure, flow rate, and vibmtion (displacement or velocity) shall be dete! mined and
- - compared with corresponding reference values. All deviations from the reference ;
) ' values shall be compared to the limits tilven in Table 3 and corrective action taken as 1 specified in para. 6.1. (Paragraph 5.2(d)) l BASIS FOR RELIEF: , During the printing process for Addenda OMa 1988, Figure 1 (referenced in footnote (2) of Table 3, was unintentionally omitted from the text. This was corrected in Addenda OMb-1989 (although it was still not labeled as Figure 1). This figure allows the optional application of displacement units for pumps with speeds greater than 600 rpm and velocity units for pumps with speeds less than 600 rpm. In addition to the ASME pump testing, Calvert Cliffs also has implemented a " Rotating Machinery Vibution Monitoring Program" that includes periodic vibmtion monitoring of all pumps. This program is inclusive and encompasses a wider range of vibration analyses at several critical pump and motor locations. ALTERNATE TESTING: As an option, Note (2) of Table 3 can be used for determining pump vibration acceptance criteria in conjunction with Figure 1 (Table 3a) of Addenda OMb 1989.
Page D 1 LEGEND FOR VALVB TABIM The " Valve Tables"In this IST Program Plan are arranged by System and Unit. The Valve Tables provide the following information for each valve included in the IST Program: , i
- 1. Valve Number: The standard CCNPP Equipment identification Number (EIN).
- 2. ASME Class: ISI Code Class 1,2,3, or NC (non Code Class: See Section 3.4).
- 3. Valve Category: A, B, C, or AC per OM-10.
- 4. O&M Coord.: Alphanumeric location o( valve on the applicable CCNPP Operations &
Maintenance (O&M) Drawing identified in the upper right hand comer of each page.
- 5. Valve Size: Self-explanatory
- 6. Valve Type: Self explanatcry. Abbreviations provided on each page.
- 7. Actuator Type: Self explanatory. Abbreviations provided on each page.
- 8. Position Indication: Self explanatory. Abbreviations provided ors each page.
- 9. Normal Position (s): A valve's normal position includes any position it may be in to accomplish approved evolutions commonly performed during normal operation, unless use of such a line-up is specifically iestricted (such as requiring the system / train to be declared inoperable while in the line-up).
- 10. Safety Position (s): A valve's safety position includes any position it may be required to either be in or achieve to accomplish its safety function (s) throught the course of an accident response.
- 11. Active / Passive: Indicate:: whether the valve is active or passive to accomplish the glven safety function (s).
- 12. Required Tests / Frequencies: Indicates the specific tests required and their assigned frequency. Each column represents a different test requirement and the e$ry in that column for a specific valve indicates the frequency at which the test is pr.rormed for that valve. Abbreviations provided on each page.
- 13. Testing Frequency Justification (CSJ/RFJ): Indicates the associated Justification Number. An evaluation is provided for all valves which are tested only during cold shutdown periods and refueling outages.
14 Rollef Request (Rel. Req.): Indicates any associated relief request.
- 15. Remarks: Self explanatory.
Baltimsre 00s & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program . Valves Page D-i System OM Number (s) BGE Drawing Number (s) Page Area Radiation Monitoring OM 098 Sh.1 60738 Sh.1 D. 3 Auxiliary Feedwater OM-Ob9 Sh.1 60717 Sh.1 D. 4 OM-800 60583 D- 5 Chemical & Volume Control OM-073 Sh.1 60730 Sh.1 D7 OM-073 Sh. 2 60730 Sh. 2 D. 9 OM-073 Sh. 3 60730 Sh. 3 D.11 l Component Cooling OM-051 Sh.1 60710 Sh.1 D 12 ! OM 051 Sh. 2 60710 Sh. 2 D- 13 OM-066 Sh.1 60724 Sh.1 D.15 i OM 066 Sh. 2 60724 Sh. 2 D.16 OM-463 Sh.1 60744 Sh.1 D-17 Condensate Storage (Common) OM-059 Sh.1 60717 Sh.1 D.18 Containment OM 065 Sh. 2 60723 Sh. 2 D.19 Containment Ventilation OM 065 Sh.1 60723 Sh.1 D. 7.0 OM 065 Sh. 2 60723 Sh. 2 D. 21 Demineralize'J Water OM-072 Sh.1 60729 Sh.1 D.22 Extraction Steam OM 077 Sh. 3 60734 Sh. 3 D. 23 Feedwater OM 039 Sh. 4 60702 Sh. 4 D 24 Fire Protection OM-056 Sh. 2 60714 Sh. 2 D.25 Gas Analyzing OM 463 Sh.1 60744 Sh.1 D 26 OM-463 Sh. 2 60744 Sh. 2 D.27 Instrument Air OM-053 Sh.1 60712 Sh.1 D.26 OM-053 Sh,3 60712 Sh. 3 D-29 OM-053 Sh. 5 60712 Sh. 5 D.30 Liquid Waste OM-077 Sh.1 60734 Sh.1 D. 31 , Main Steam OM 035 Sh.1 60700 Sh.1 D.32 OM-800 60583 D. 34 Nitrogen OM-068 60726 D- 35 Plant Air OM-479 Sh. 2 60746 Sh. 2 D. 36 Plant Drains OM-076 Sh.1 60733 Sh.1 D- 37 OM 076 Sh. 4 60733 Sh. 4 D. 38 Plant Wator OM-479 Sh. 3 60746 Sh. 3 D 39 Primary / Post Accident Sampling OM-06u Sh.1 60724 Sh.1 D.40 OM-C,$6 Sh. 3 60724 Sh. 3 D.41 Reactor Coolant OM-066 Sh.1 60724 Sh.1 D 42 OM-072 Sh.1 60729 Sh.1 D.43 Safety injection / Containment Spray OM-074 Sh.1 60731 Sh.1 D 44 OM-074 Sh. 2 60731 Sh. 2 D 47 OM-074 Sh. 3 60731 Sh. 3 D.50 Saltwater OM-049 Sh. 2 607C8 Sh. 2 D.52 Service Water OM-046 Sh. 2 60706 Sh. 2 0 54 OM-069 Sh. 2 60727 Sh. 2 D 56 OM-464 60761 D- 57 Spent Fuel Pool Coolino OM-058 60718
' D 58 Steam Generator Blowdown OM-464 60761 D- 59 Waste Gas OM-078 Sh.1 60735 Sh.1 D.60 1 A EDG Starting Air DG M-8 Sh.1 62467 Sh.1 D- 61 DG-M-8 Sh. 2 62467 Sh. 2 D.62 1 A EDG Fuel Oil Storage & Transfer DG-M 13 62437 D- 63
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Baltimore Gas & Electric, Calved Cliffs Nucicar Power Plant Unit 1, IST Program - Valves Page D-7 Unit 1 System Name: Chemical & Volume Control O&M Number: OM-073 Sh_1 BGE Dwg Numbec 60730 Sh.1 l Required Tests / Frequencies l t I y : i e 4 3
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I Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D.9 Unit 1 System Name: Chemical & Volume Control O&M Number: OM-073 Sh.2 BGE Dwn Number: 60730 Sh. 2 I l Rcquired Tests / Frequencses [ ' E E I d d E
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Type Type Position (s) CKV/HV Full-Strcke/ Exercise Open FSEO Quarterty Q BA - Ball A - Air C - Closed CKV/HV Fu!I-Strob> Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Fuli-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time C!osed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J ' LJ
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Baltimore Gas & Electric, Calvert Cliffs Nucl ear Power Plant Unit 1, IST Progrem - Valves Page D-12 Unit 1 System Name: Component Cooling O&M Number: OM-051 Sh.1 BGE Dwg Number: G0710 Sh.1 l Required Tests / Frequencies l e I y i e d 3 a 0 "g i l l i e e G ? + i E k
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1. IST Program - Val' es Page D-13 Unit 1 System Name: Component Cooling O&M Number OM-051 Sh. 2 BGE Dwg Number: 60710 Sh. 2 l Required Tests / Frequencies l
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-14 Unit 1 System Name: Component Cooling O&M Number: OM-051 Sh. 2 BGE Dwg Number: 60710 Sh. 2 Required Tests / Frequencies l 5 E E d E E
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l Baltimore Gas & Electric, Calvert Cliffs Nucle r Power Plant Unit 1, IST Program - Valves Page D-15 Unit 1 System Name: Component Cooling O&M Number: OM-066 Sh.1 BGE Dwg Number: 60724 Sh.1 l Required Tests / Frequencies ; e I j E Y d d i e 0 a 5 2 % F-i e e G + e W U E C F- -s ~ D E O O O O
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C O AO S 1-CC-6471-RV 3 C E3 .75 R - - C O AO S 1-CC-6472-RV 3 C E4 .75 R - - C O AO S ! b
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Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly - Q l BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Coki Shutdown C ! BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R ! C - Check S - Solenoid T - Throttled (Open) POV Fuli-Stroke Time Closed FSTC 2-Year 2 ! GA - Gate H - Hand Fai!-Safe FS Sampling S ! G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi i AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J - LJ i
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-t6 Unit 1 & 2 System Name: Component Cooling ' O&M Number: OM-066 Sh. 2 BGE Dwg Number: 60724 Sh. 2 (Common) Required Tests / Frequencies l I t I E d E
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C O AO S 0-CC-6503-RV 3 C E9 .50 R - - C O AO S 0-CC-6530-RV 3 C E9 .50 R - - C O AO S 0-CC-6533-RV 3 C F10 .50 R - - C O AO S Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - GIobe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
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Baltimore Gas & Electric Calvert Cliffs Nuclear Power Plant Unit 1. IST Program - Valves Page D-19 Unit 1 System Name: Containment O&M Number: OM-065 Sh. 2 BGE Dwg Number: 60723 Sh. 2 ;
. Required Tests / Frequencies l
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$ $h$$h 1-CPI-5313A-SV NC B 4EEE # EEEEE E 5 ii- Ei $ 3 $4 E fRemarks C3 .75 G S X O O PO 2 1-CPI-5313B-SV NC B B3 .75 G S X O O PO 2 1-CPI-5313C-SV NC B D3 .75 G S X O O PO 2 1-CPI-5313D-SV NC B C3 .75 G S X O O PO 2 1-ILRT-1 NC A A7 .75 G - - C C PC J CIV 1-ILRT-2 NC A B7 .75 G - -
C C PC J CIV Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke /Erercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - GIobe Active / Passive Part-Stroke PS Per App.J J R - Safety / Relief AO - Active Open Disassembly / laspection DI PO - Passive Open Position Indication Pl AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ
1 Baltimore Gas & Eledric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-20 Unit 1 System Name: Containment Ventilation O&M Number: OM-065 Sh.1 BGE Dwg Number- 60723 Sh.1 l Required Tests / Frequencies l 5 I j : i e e i
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" Effectice Until Completion of ESP 94-205 *And any cold shutdown period during which p containment purge is established.
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Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Strokelr'.xercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active'Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Ba!!imore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-21 Unit 1 System Name: Containment Ventiation O&M Number: OM-065 Sh. 2 BGE Dwg Number: 60723 Sh. 2 l Required Tests / Frequencies l e E E E N 4 n E E b s b d E E $ E E 5 5 & I E - s 7 9 C 2 i E I 8 e R E 4 5 1-HP-104
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-24 Unit 1 System Name: Feedwater O&M Number: OM-039 Sh. 4 BGE Dwg Number: 60702 Sh.4 Required Tests / Frequencies l
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-26 Unit 1 System Name: Gas Analyzing O&M Number: OM463 Sh.1 BGE Dwg Number: 60744 Sh.1 Required Tests / Frequencies l I e g E Y i i 3
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Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarte 1y Q , BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C ! BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S-Solenoid T-Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S " G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI " PO - Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ ' l
Baltimora Gas & Electric. Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-27 Unit i System Name: Gas Analyzing O&M Number: OM-463 Sh. 2 BGE Dwg Number: 60744 Sh. 2 l Required Tests / Frequencies l U $
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B:ltimore G:s & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Prog.rm - Valves Page D-28 Unit 1 - System Name: Instrument Air O&M Number: OM-053 Sh.1 BGE Dwg Number: 60712 Sh.1 l Required Tests / Frequencies l 2 S y Y s e i 5 0 s 2 h h $ E E 5 & 5 I E - s$* 7 9 $ 2 i l $ SM R R 4 5 S 1-IA-337 E $5 NCi AC B11
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O/C O/C AO/AC Q R J RFJ-02 CtV 1-IA-2085-CV NC B B10 3 G A - O C AC C C 2 CSJ-24 __ L - l t Valve Actuator Normal / Safety Requised Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke /Exerci e Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ __-__-___--------4
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1. IST Program - Valves Page D-29 Unit 1 System Name: Instrument Air O&M Number: OM-053 Sh. 3 BGE Dwg Number: 60712 Sh. 3 l Required Tests / Frequencies l t
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l: i e e i e 1 0 g B w u z i wi -s e eb R ? e e g c y y o n o n , y b $ $ E'E o. it $ 3 3 Remarks 1-IA-650 NC C F3 2 C - - O/C C AC R RFJ-3 : 1 1-IA-721 NC C G10 .75 C - - O/C O/C AO/AC R R RFJ-4 1-IA-722 NC C G10 .75 C - - O/C O/C AO/AC R R RFJ-4 1-IA-1333 NC C H10 .50 C - - O/C C AC R RFJ-5 ; 1-IA-1338 NC C H10 .50 C - - O/C C AC R RFJ-5 1-IA-2080-MOV NC A F2 2 GA M - O O/C AO/AC C C 2 ' J CSJ-25 CIV 1-IA-5200-RV NC C H11 .25 R - - C O AO S 1-IA-5201-RV NC C G9 .25 R - - C O AO S E Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly O BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J
'R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ i
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Pfard Unit 1, IST Program - Valves Page D-30 l Unit 1 System Name: Instrument Air O&M Number: OM-053 Sh. 5 BGE Dwg Number: 60712 Sh. 5 l Required Tests / Frequencies l
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1-IA-2058-RV NC C E7 1 R - - C O A'O S 1-IA-4070-RV NC C D6 .75 R - - C O AO S 1-IA-4070A-RV NC C C9 .75 R - - C O AO S 1-IA-4071-RV NC C C5 .75 R - - C O AO S 1-1A-4071 A-RV NC C C4 .75 R - - C O AO S 1-IA-6301A-RV NC C G2 .75 R - - C O AO S 1-IA-6301 B-RV NC C G10 .751 R - - C O AO S f Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stmke/ Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Sht tdown C BU - 3utterfly M - Motor O - Open POV Full-Strake Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S 3 - Globe Active / Passive Part-Stroke PS Per App.J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 1.J
l 4 Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-31 Unit 1 System Name: Liquid Waste O&M Number: OM-077 Sh.1 BGE Dwg Number: 60734 Sh.1 ; l 1 l Required Tests / Frequencies l ] 3 I y E $ e d 3 5 I b # u 5 h $ $ 8 E 9 s 7 9 5 2 E E {5 5 3 S S S R 5 4 i 5 y 1-RCW-4260-CV NC A Eh8 $ $$$$ $ $ E EE E E E 5E$33 0 E , Remarks t ES 2 GA A X O/C C AC Q Q 2 J CIV t I i Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterfy Q BA - Ball A - Air C - Closed CKV/HV Fu!I-Stroke / Exercise Closed FSEC Cold Shutdowre C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gale H - Hand Fail-Safe FS Sampling S G - Globe Active /Passise Part-Stroke PS Per App J J R - Safcty/ Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication P! AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ l
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1. !ST Program - Valves Page D-32 Unit 1 System Name: Main Steam O&M Number: OM-035 Sh.1 BGE Dwg Number: 60700 Sh.1 Required Tests / Frequencies l e I E I N d J E E
$ a 8 e 8. 8. -3 $ E E 2 &
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C O AO S ~ 1-MS-4004-RV 2 B B5 6 R - - C O AO S 1-MS-4005-RV 2 B B5 6 R - - C O AO S 1-MS-4006-RV 2 B B5 6 R - - C O AO S 1-MS-4007-RV 2 8 84 6 R - - C O AO S Valve Actuator Normal / Safety Required Tests Required Frega Type Type Position (s) CKV/HV Full-Strol,e/ Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke! Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R-C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Pcr App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Positior'. 2ndication PI AC - Active Closed Setpoint Testing SP PC - Passit e Closed Leak Testing iK LI RT per App. J Li
l Baltimore Gas & Electric. Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-33 . Unit 1 System Name: Main Steram O&M Nun.ber: OM-035 Sh.1 BGE Dwg Number: 60700 Sh.1 ! l Required Tests / Frequencies l y i s e i i
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C C PC J CIV _ 0-N2-389 NC AC H6 1 C - - C C PC J CIV N2-392 NC AC 16 1 C - - C C PC J CIV Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refuelitig R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO- Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plan' Unit 1. IST Program - Valves Page D-36 Unit 1 System Name: Plant Air O&M Number: OM-479 Sh. 2 BGE Dwg Number: 60746 Sh. 2 l Required Tests / Frequenches
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Baltimore Gas & Electric. Calvert Cliffs Nuclear Power Plant Unit '. IST Fiugam - Valves Page D-38 Unit i System Name: Plant Drains O&M Mumber: OM-076 Sh. 4 BGE Dwg Number: 60733 Sh. 4 l Required Tests s Frequencies e I y : I e d i a e 2 0 s 5 in 2 U
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Type Type Position (s) CKV/HV Fuff-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke > Exercise Close<1 FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe F3 Sampling S G - Globe Active / Passive Par'-Ctroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection Di PO - Passive Open Position Indication PI AC - Adive Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ
l Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-39 Unit 1 System Name: Plant Water O&M Number: OM-479 Sh. 3 BGE Dwg Number: 60746 Sh. 3 l Required Tests / Frequencies l _
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Baltimore Gas & Eledric, Calvert Cliffs Nudear Power Plant Unit 1. IST Program - Valves Page D-45 Unit 1 System Name: Safety injedion/ Containment Spray OEM Number: OM-074 Sh.1 BGE Dwg Number: 60731 Sh.1 l Required Tests / Frequencses l
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1-SI-247 1 - C O/C AO/AC Ri R Q. 2 VR-03 PlV 1-SI-306-CV 2 B E13 12 G A- X O O PO , 2 1-SI-399-MOV 2 B 17 2 GA M XiC O/C AO/AC OjQ 2 1-SI-455 2 A- A10 2i G' H -iC C PC e i iJ CIV Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterfy Q BA - Ball A - Air C- Closed CKV/HV Fuli-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Fu!I-Stroke Time Open FSTO Refuermg R C - Check S - Scienoid T- Throttled (Opt n) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampfmg S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly /Inspectron DI PO - Passive Open Position Indication Pi Attemative
- AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Baltimore Gas & Sectric Calvert Cliffs Nuclear Power Plant Unit 1. IST Program - Valves Page D-48 Unit 1 System Name: Safety injection / Containment Spray O&M Number: OM-074 Sh. 2 BGE Dwg Number: 60731 Sh2 l Required Tests / Frequericses l l e I E d*d I
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d S I I - s - C i E I S S S R 4 5 1-St-463 E O 2 A A9 { 2 EhME$ E N EEEEE'EoEI33 $ E Remarks i o GA H ' C C PC l 1 l lJ . CIV ! 1-SI-612-CV NC A' B5 ' 1 GA A X O/C C AC j Q Q l2l tJ CIV t 1-St-613-CV 2 B C2 1 G A X C C PC l2 i 1-St-614-MOV 2 B D3 12 G M. X O O PO l2 1-SI-615-MOV 2 B E2 6 G M X C O/C AO/AC Q Q. 2 ! 1-SI-618-CV 2 B DS 1 G A X' O/C C AC O Q 2 l 1-SI-622-CV ,NC A FS 1 GA A Xi O/C C AC Q Q 2 i J CIV 1-SI-623-CV 2 B F2 1 G A X C C PC 2 1-SI-624-MOV 2 B H3 12 G M X. O O PO 2 1-St-625-MOV 2 B H2 6- G M X C O/C AO/AC Q' Q 2 1-SI-628-CV l2 B G5 1 G A X O/C C AC Q Q 2 1-SI-632-CV NC A 88 1 GA A X O/C. C AC Q Q ' 2 J . CIV 1-SI-633-CV 2 B C11 1 G A X C C PC 2 1-SI-634-MOV 2 B D9 12 G M X O O PO 2 1-SI-635-MOV 2 8. E10 6 G M X C O/C AO/AC ! O Q. 2 , 1-SI-638-CV 2 B DB 1 G- A X- O/C C AC O Q 2 n 1-St-642-CV NC A F8 1 GA A X O/C C AC Q- Q 2 J ' CIV 1-SI-643-CV 2 B F11 1 G Al X C C PC 2 1-St-644-MOV 2 B H9 12 G MI X O O PO l ' 2 Valve Actuator Normal / Safety Requered Tests Requered Freqs. Type Type Position (s) CKV/HV Full-Stroke /Exerase Open FSEO Quarterfy Q l BA - Ball A - Air C- Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C ' BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T-Throttled (Open) POV Fuli-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J i R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J ~ Li
Baltimore Gas & Electric. Calvert Cliffs Nudear Power Plant Unit 1. IST Program -Valves Page IM9 Unit 1 System Name: Safety injection / Containment Spray O&M Number: OM-074 Sh. 2 BGE Dwg Number: 6051 Sh2 l Requered Tests 1 Frequencies ] E l t : i e a
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O/C C AC C 4CSJ-42; 1-SI-492 2 C F4 1 C - - O/C C AC C lCSJ-42; i 1-SI-493 2 C B8: 1 C - - O/C C AC C- lCSJ-42] 1-SI-494 2 C FB 1 C - - O/C C AC C H 'CSJ-42; 4 i l 1-SI-211-RV 2 C AS 1 R - - C O AO S 1-SI-221-RV 2 C ES 1 R - - C O AO S 1-SI-231-RV 2 C A10 1 R - - C O AO S
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O/C O/C AO/AC Q Q-1-SW-111 3 C C6 24 C - - O/C O,C AO/AC Q Q 1-SW-5149-CV 3 8 B8 24 BU AlX C O/O AO!PC C 2 CSJ-44 1-SW-5150-CV 3 8 E7 30 BU A X O O/C AC/PO Q l 2 1-SW-5152-CV , B G7 30 BU A X O O PO 2 1-SW-5153-CV 3 8 F11 30 BU A X O O/C PO/AC Q 2 1-SW-5155-CV i 3 8 H9; 30 BU A X C O/C AO/PC C 2 CSJ-45 1 1-SW-5156-CV 3 D G5 30 BU A X C O/C AO/PC C 2 CSJ-45! 1-SW-5160-CV 3 8 ES 24 BU A X O O/C AO/AC Q Q Q 2L l 1-SW-5162-CV 3 8 G4 24 BU A X O: O/C AO/AC Q Q Q 2
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[ 1-SW-5163-CV 3 B 16 12 BU A X O O/C AO/AC Q Q Q 2 l 1-SW-5165-CV 3 8 G6 18 BU A X C O/C AO/PC C 2 CSJ-44 1-SW-5166-CV 3 8 F6 18 BU A X C .O/C AO/PC C 2 CSJ-45l 1-SW-5170-CV 3' B F3 8 BU A X C O/C AO/AC Q Q 'Q 2 1-SW-5171-CV 3 8 G3 8 BU A X C O/C AO/AC Q Q -Q 2! 1-SW-5173-CV 3 B D4 8 BU A X C O AO Q Q 2 1-SW-5174-CV 3 8 H2 8 BU A X O O/C PO/AC Q 2 1-SW-5175-CV 3 8 H2 8 BU A X O O/C PO/AC- Q 2 I r Valve Actuator Normal / Safety Requered Tests Requered Freqs. Type Type Position (s) CKV/HV Fun-Stroke /Exerose Open FSEO Quarterty Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke /Exerose Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S-Solenoid T-Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS PerApp. J J R - Safety /Re!ief AO - Active Open DisassemblyIinspection DI PO - Passive O' pen Position indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J ' LI
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-53 Unit 1 System Name: Saitwater O&M Number: OM-049 Sh. 2 BGE Dwg Number: 60708 Sh. 2 l l Required Tests / Frequencies [ > g ; ' I y E I 4 4 3 3 0 s o8 2 h i i E E E 5 + 2
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1-SW-5178-CV 3 B F2 8' BU A X C O/C AO/PC C 2 CSJ-45i i 1-SW-5206-CV - 3 B 16 12 BU A X T O/C AO/AC Q Q Q 2 1-SW-5208-CV 3 8 !4 12 BU A Xi T O/C AO/AC Q Q Q 2 1-SW-5210-CV 3 B F9 24 BU A X T O/C AO/AC Q Q Q 2 1-SW-5212-CV 3 8 H10 24 BU A X T O!C AO/AC Q Q Q 2 __1-SW-C05-RV 3 C E2 .75 R - - C O AO S _ t-SW-5206-RV 3 G G5- 1.5 R - - C O AO S 1-SW-5207-RV 3 C D2 .75 R - - C O AO S 1-SW-5208-RV 3 C HS 1.5 R - - C O AO S 1-SW-5210-RV 3 C F8 1.5 R - - C O AO 3 1-SW-5212-RV 3 C HS 1.5 R - - C O AO S 1 l L i i l l Valve Actuator Normal / Safety Required Tests Requered Freqs-Type Type Position (s) CKV/HV Fu!I-Stroke /Exercrse Open FSEO Quarterty O BA - Bal: A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C , BU - Butterfly M - Motor O - Open POV Fu!!-Stroke Time Open FSTO Refuermg R I C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 i GA - Gate H - Hand Fail-Safe FS Sampling S l G - Globe Active / Passive Part-Stroke PS Per App. J J ; R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LI i i
i Baltimore Gas & Eledric Calvert Cliffs Nuclear Power Plant Unit 1, IST Program - Valves Page D-54 Unit 1 System Name: Eervice Water O&M Number- OM-046 Sh. 2 BGE Dwg Number: 60706 Sh. 2 l Required Tests / Frequencies l e I y : I e d 3 1 0 a 8 2 5 k e 2 i E e W D -
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1-SRW-1590-CV 3 B H6 8 BU A X C O AO Q Q 2 1-SRW-1592-CV 3 B F9 8 BU A X O T/O AO/AC Q .QlQ 2 l 1-SRW-1593-CV 3 Bi G11 8 BU A 1 X' . C O AO i ! 'Q: IQ: 1 2 l Valve Actuator Normal / Safety Required Tests Requwed Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterty Q ! BA - Ball A - Air C - Closed CKV/HV FuSStroke!Exercrse Closed FSEC Cok! Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueting R [ C - Check S - Solenoid T- Throttled (Open) POV Fu4 Stroke Time Closed FSTC 2-Year 2 I GA - Gate H - Hand Fail-Safe FS Samprmg S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Adive Open Disassembly / Inspecion DI ! PO - Passrve Open Position Indication PI AC- Adive Closed Setpo nt Testing SP , PC - Passive Closed t_eak Testmg LK LLRT per App. J -LJ ;
Baltimore Gas a Electric, Calvert Cliffs Nudear Power Plant Unit 1. 'ST Program - Valves Page D-55 Unit 1 System Name: Service Water O&M Number: OM-046 Sh. 2 BGE Dwg Numtxer: 60706 Sh. 2 l Requered Tests / Frequencies l
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i l Page B-1 i LEGEND FOR VALVB TABLES The " Valve Tables"in this IST Program Plan are arranged by System and Unit. The Valve Tables provide the following information for each valve included in the IST Program:
- 1. Valve Number: The standard CCNPP Equipment identification Number (EIN).
- 2. ASME Class: ISl Code Class 1,2,3, or NC (non-Code Class: See Section 3.4).
- 3. Valve Category: A, B, C or AC per OM-10.
- 4. O&M Coord.: Alphanumeric location of valve on the applicable CCNPP Operations &
Maintenance (O&M) Drawing identified in the upper right hand comer of each page.
- 5. Valve Size: Self explanatory
- 6. Valve Type: Self explanatory. Abbretistions provided on each page.
- 7. Actuator Type: Self explanatory. Abbrev 8ations provided cn each page.
- 8. Position Indication: Self explanatory. Abbreviations provided on each page.
- 9. Normal Position (s): A valve's normal position includes any position it may be in to accomplish approved evolutions commonly performed during normal operation, unless use of such a line-up is specifically restricted (such as requiring the system / train to be declared inoperable while in the line up).
10, Safety Position (s): A valve's safety position includes any position it may be required to either be in or achieve to accomplish its safety function (s) throught the course of an accident response.
- 11. Active / Passive: Indicates whether the valve is active or passive to accomplish the given safety function (s).
- 12. Required Tosts/ Frequencies: Indicates the specific tests required and their assigned frequency. Each column represents a different test requirement and the entry in that column for a specific valve indicates the frequency at which the test is performed for that valve. Abbreviations provided on each page.
- 13. Testing Frequency Justification (CSJ/RFJ): Indicates the associated Justification Number. An evaluation is provided for all valves which are tested only during cold shutdown periods and refueling outages.
- 14. Relief Request (Rel. Req.): Indicates any associated relief request.
- 15. Remarks: Self explanatory.
Baltimore C:s & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program . Valves Page E.2 system OM Number (s) BOE Drawing Number (s) Page Area Radiation Monitoring { OM-098 Sh.1 60736 Sh.1 E. 3 Auxiliary Feedwater OM 059 Sh.1 60717 Sh.1 E. 4 ' OM-801 62563 E. 5 Chemical & Volume Co itrol OM-461 Sh.1 62730 Sh.1 E. 7 OM-461 Sh. 2 62730 Sh. 2 E. 9 OM-461 Sh. 3 62730 Sh. 3 E.11 i Component Cooling OM 452 Sh.1 62710 Sh.'1 E.12 ! l OM-452 Sh. 2 62710 Sh. 2 E.13 OM 066 Sh.1 60724 Sh.1 E.15 Containment OM-065 Sh. 2 60723 Sh. 2 E.16 Containment Ventilation OM-065 Sh.1 60723 Ch.1 E.17 OM-065 Sh. 2 60723 Sh. 2 E.18 Domineralized Water OM-460 Sh.1 62729 Sh.1 E.19 Extraction Steam OM-077 Sh. 3 60734 Sh. 3 E 'O Feedwater OM-040 Sh. 4 62702 Sh. 4 21 Fire Protection OM-056 Sh. 2 60714 Sh. 2 't: 22 Gas Analyzing OM-463 Sh.1 60744 Sh,1 E.23 OM-463 Sh. 2 60744 Sh. 2 E.24 Instrument Air OM 454 Sh. 3 62712 Sh. 3 E. .*5 l lquid Waste OM-077 Sh.1 60734 Sh.1 E 27 Main Steam OM-036 Sh.1 62700 Sh.1 E. 26 OM-001 62583 E.30 Nitrogen OM-068 60726 E. 31 Plant Air OM-479 Sh. 2 60746 Sh. 2 E.32 Plant Drains Of 4 076 Sh. 2 60733 Sh. 2 E.33 OM-076 Sh. 4 60733 Sh. 4 E. 34 Plant Water OM-479 Sh. 3 60746 Sh. 3 E.35 Primary / Post Accident Sampling OM 066 Sh.1 60724 Sh.1 E. 36 OM-066 Sh. 3 60724 Sh. 3 E.37 Reactor Coolant OM 066 Sh.1 60724 Sh.1 E.38 OM-460 Sh.1 62729 Sh.1 E.39 Safety injection / Containment Spray OM 462 Sh.1 62731 Sh.1 E.40 OM 462 Sh. 2 62731 Sh. 2 E.43 OM 462 Sh. 3 62731 Sh. 3 E.46 Saltwater OM450 Sh. 2 62708 Sh. 2 E.48 Service Water OM-047 Sh. 2 62706 Sh. 2 E.50 OM-069 Sh.1 60727 Sh.1 E.52 OM-069 Sh. 3 60727 Sh. 3 E.53 OM-465 62749 E. 54 Spent Fuel Pool Coolino OM 058 60716 E.55
,St,eam Generator Blowdown OM 465 62749 E. 56 Mste Gas OM-078 Sh.1 60735 Sh.1 E. 57
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-6 Unit 2 System Name: Auxiliary Feedwater O&M Number: OM-801 BGE Dwg Number: 62583 Required TeMil 'nequencies
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2-AFW-4512-CV 3 8 G3 3 G A X O T AO Q Q 2 i 2-AFW-4520-CV 3 B C5 6 G A E O O/C AO/AC Q Q Q 2 2-AFW-4521-CV 3 8 C4 6 G A X O O/C AO/AC Q Q Q 2 l 2-AFW-4522-CV 3 B D4 6 G A X O O/C AO/AC Q Q Q 2 2-AFW-4523-CV 3 B D3 6 G A X O O/C AO/AC Q Q Q 2 2-AFW-4525-CV 3 8 D2 4 G A X O T AO Q Q 2 7 2-AFW-4530-CV 3 8 G5 6 G A X O O/C AO/AC Q Q. Q 2 ; 2-AFW-4531-CV 3 B G4 6 G A X O O/C AO/AC Q Q Q 2 2-AFW-4532-CV 3 B F4 6,G A X O O/C AO/AC Q Q Q 2 2-AFW-4533-CV 3 B F2 6. G A X O O/C AO/AC Q Q Q 2 ! 2-AFW-4535-CV 3 B F2 4 G A X O T AO O Q 2 2-AFW-4550-CV 3 8 H7 6 G A X C O/C AO/PC Q 2 Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterfy Q = BA - Ball A - Air C - Closed CKV/HV Full-Skoke/ Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Strok6 Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App.J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpaint Testing SP t PC - Passive Closd Leak Testing LK L LLRT per App. J Li
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-7 Unit 2 System Name: Chemical & Volume Control O&M Number: OM-461 Sh.1 BGE Dwg Number: 62730 Sh.1 l Required Tests / Frequencies l
% I y : I e d i
=
5 o 8 , a t e 2 : 2 + E E5 f $
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8 5 E Remarks 2-CVC-162 2 C F2 4 C - - O/C C AC C CSJ-06 2-CVC-217 2 C G8 3 C - - O/C O/C AO/AC Q Q 2-CVC-222 2 C. H10 3 C - - O/C O/C AO/AO Q Q 2-CVC-228 2 C H3 3 C - - C O/C AO/AC C C Q CSJ-07 2-CVC-235 2 C F5 3 C - - O/C O AO C CSJ-08 2-CVC-251 2 C DS 3 C - - O/C C AC C CSJ-08A 2-CVC-257 2 C F3 3 C - - O/C O/C AO/AC C C CSJ-09 2-CVC-501-MOV 2 B F2 4 GA M X O C AC C. 2 CSJ-10 2-CVC-504-MOV 2 B F3 3 GA M X C O/C AO/AC C C 2 'CSJ-11 2-CVC-508-MOV 2 B H12 3 GA M X C O AO Q 2 ~ 2-CVC-509-MOV 2 B G8 3 GA M X C O AO O 2 2-CVC-510-CV 2 B ES 1.5 GA A X O C AC Q Q 2 2-CVC-511-CV 2 B E12 1.5 GA A X O C AC Q Q 2 2-CVC-512-CV NC B D4 3 G A X O/C C AC Q Q 2 2-CVC-514-MOV 2 B F6 3 GA M X C O AO Q 2 Vrive Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown O BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-8 Unit 2 System Name: Chemical & Volume Control O&M Number: OM-461 Sh.1 BGE Dwg Number: 62730 Sh.1 ' Required Tests / Frequencies l E = I 4 . 2 z ii 2
=- E HE Y E. k $ +
2 e W 2 u - E # n* ; e C g:: b
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$h 4 $ $ 5 M E EE E E E 5 E I 3 "j $ E Remarks
.75 R - -
C O AO S , 2-CVC-132-RV 2 C G8 .75 R - - C O AO S 2-CVC-133-RV 2 C F8 .75 R - - C O AO S 2-CVC-141-RV 2 C G12 .75 R - - C O AO S j 2-CVC-149-RV 2 C F12 .75 R - - C O AO S ; 2-CVC-150-RV 2 C F12 .75 R - - C O AO S 2-CVC-157-RV 2 C F6 .75 R - - C O AO S
- 2-CVC-160-RV 2 C F7 .75 R - -
C O AO S 2-CVC-171-RV 2 C E7 .75 R - - C O AO S. l L Valve Actuator Normal / Safety . Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC' Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hcnd -t Fail-Safe FS Sampling S l G - Globe A:tive/ Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI ; PO - Passive Open Position Indication P1 AC - Active Closed Setpoint Testing SP t PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ
B ltimore Gas & Electric Calver1 Cliffs Nuclear.~awer Plant Unit 2, IST Program - Valves Page E-9 Unit 2 System Name: Chemical & Volume Control O&M Number: OM-461 Sh. 2 BGE Dwg Number: 62730 Sh. 2 Required Tests / Frequencies U I E d d E l?; I e 8 s 8 E l i e e & + 1 E - z 7 9 3 2 i f I S S S R $ s 2-CVC-165 a$$ 2 C 5 $ # 2e # # E2 2 E E E 5 it %53 8 E Remarks F6 2 C - - O/C O/C AO/AC Q Q 2-CVC-171 2 C G6 2 C - - O/C O/C AO/AC Q Q 2-CVC-177 2 C 16 2 C - - O/C O/C AO/AC Q Q
- 2-CVC-184 2 AC DS 2 C - -
0 O/C AO/AC C C Q J CSJ-12~ CIV 2-CVC-185 1 C C8 2 C - - C O!C AO/AC C C C CSJ-13 ; 2.CvC-186 1 C E8 2 C - - O/C O/C AO/AC C C Q ' CSJ-14 2-CVC-187 1 C E12 2 C - - O/C O/C AO/AC Q C CSJ-14 2-CVC-435 1 AC F11 2 G - - O O/C AO/AC C C Q J CSJ-15 CIV 2-CVC-269-MOV 2 B F3 2 GA M X C O!C AO/AC Q Q 2 2-CVC-505-CV NC A B3 .75 G A X O C AC C C 2 J CSJ-16 CIV ! 2-CVC-506-CV NC A B6 .75 G A X O C AC C C 2 'J CSJ-16 CIV 2-CVC-515-CV 1 A D2 2 G A X O C AC C C 2 J CSJ-17 CIV 2-CVC-516-CV 1 A D4 2 G A X O C AC C C 2 J CSJ-17, CIV ; 2-CVC-517-CV 1 A C9 2 G A X C O/C AO/AC C C C 2 J CSJ-18 CIV 2-CVC-518-CV A E9 l 1 2 G A X O O/C AO/AC Q Q Q 2 J CIV ! 2-CVC-519-CV 1 A E11 2 G A X O O/C AO/AC Q Q Q 2 J CIV i Valve Actuator Normall Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R ! C - Check S - Solenoid T - Throttled (Open) POV Fufi-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC- Active Closed Setpoint Testing SP - PC - Passive Closed Leak Testing LK LLRT per App. J 1.J
Baltimore Gas & E!ectric, Calvert Cliffs Nuclear Power Plant Unit 2. IST Program - Valves Page E-10 Unit 2 System Name: Chemical & Volume Control O&M Number: OM-461 Sh.2 BGE Dwg Number: 62730 Sh. ? Required Tests / Frequencies
% I j E Y g d i
=
$ a o 7 1 1 6 2 8 2 2 g 5 E E E i T f i n i 3 S e R R 5 5
$ E O k M E 2E M E E E E E E5 E I b.] $ 2 Remarks 2-CVC-311-RV 2 C G10.75 R - -
C O AO l S l 2-CVC-315-RV 2 C E8 .75 R - - C O AO S i 2-CVC-318-RV 2 C G8 .75 R - - C O AO S 2-CVC-321-RV 2 C H8 .75 R - - C O AO S 2-CVC-324-RV 2 C H6 .75 R - - C O AO S 2-CVC-325-RV 2 C G6 .75 R - - C O AO S 2-CVC-326-RV 2 C E6 .75 R - - C O AO S Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C ' BU - Butterfly M - Motor O - Open POV Ful!-Stroke Time Open FSTO Refueling R C - Check S-Solenoid T-Throttle-(Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Scie FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-11 Unit 2 System Name: Chemical & Volume Controi ~ O&M Number: OM-461 Sh. 3 BGE Dwg Number: 62730 Sh. 3 Required Tests / Frequencies
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=
5 o a n s E E : 2 # w 0 U 5 & ~
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*l PC J CIV 2-CVC-105 2 A B3 2 GA - -
- i PC J CIV
- Normally, if 2-CVC-103 is OPEN then 2-CVC-105 is CLOSED, and vice versa.
Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pl AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Baltimore Gas & Electric, Calved Cliffs Nuclear Power Plant Unit 2. IST rogram - Valves Page E-12 , Unit 2 System i' me: Component Cooling O&M Number: OM-452 Sh.1 BGE Dwg Number: 62710 Sh.1 ( l Required Tests / Frequencies . l l I U S l 1= : i ; e i 0 a 8 = & & n E E E E & l _! E E Eh$ U . $ h f
$ 5 M EE
$ 3 i f E
I M S S R R E E E E E E 5 E i% 53 8 E Remarks j 2-CC-115 3 C 14 16 C - - O/C O/C AO/AC Q Q
- 2-CC-120 3 C G4 16 C - -
O/C O/C AO/AC Q Q i 2-CC-125 3 C E4 16 C - - O/C O/C AO/AC Q Q i i Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quartedy Q , BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 , GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active! Passive Part-Stroke PS Per App.J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed i eak Testing LK L' RT per App. J -LJ l
- . . - - - - . .. . - -~ .- .
E B ltimore Gas & Electric, Crivert Cliffs Nuclear Power Plint Unit 2, IST Program - Valves ' page E-13 Unit 2 System Name: Component Cooling O&M Number: OM-452 Sh. 2 BGE Dwg Number: 62710 Sh. 2
'l Required Tests / Frequencies l 5 I I
$ 3 i e d 3 a O s E 'Z l l i e e G ? i i E R s M Ci i $ 5 8 8 R R ; 5 2-CC-459 Eh O $ $ # E $ $ $ E E EEEE 5E $$] O E Remarks 3 C D10 10 C - - O C AC Q 2-CC-3823-CV 3 B B7 10 BU A -
T C AC Q Q 2-CC-3824-CV 3 B B6 16 BU A X O/C O AO Q Q 2 2-CC-3825-CV 3 B C7 10 BU A - T C AC Q Q 2-CC-3826-CV 3 B C6 16 BU A X O/C O AO Q Q 2 ~ 2-CC-3828-CV 3 8 H9 16 BU A X C O AO Q Q 2 2-CC-3830-CV 3 8 E9 16 BU A X C O AO Q Q 2 t 2-CC-3832-CV 3 A B2 10 BU A X O C AC C C 2 J CSJ-19 CIV 2-CC-3833-CV 3 A 14 10 BU A X O C AC C C 2 J CSJ-19 CIV 2-CC-3840-CV 3 B BB 10 BU A X O/C C AC Q Q 2 2-CC-3842-CV NC B B9 10 BU A X O/C C AC Q Q 2 - t t I l Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q > BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C ; BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S Solenoid T-Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-14 Unit 2 System Name: Component Cooling O&M Number: OM-452 Sh. 2 BGE Dwg Number: 62710 Sh. 2 Required Tests / Frequencies [ e I i I w d 3 se 0 ,: i W D 2 zik --t O r D-
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$ $ 5 $$ $ # E $ $ # E E' E E E E 5 E I$3 0 E Remarks 2-CC-3823-RV 3 C B7 1 R - -
C O AO S i 2-CC-3825-RV 3 C D7 1 R - - C O AO S 2-CC-3827-RV 3 C H8 1 R - - C O AO S 2-CC-3829-RV 3 C F8 1 R - - C O t.O S 2-CC-3831-RV 3 C B2 1 R - - C O AO S 2-CC-3841-RV NC C D2 1 R - - C O AO S 2-CC-3842-RV NC C E3 1 R - - C O AO S Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App.J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J ~LJ l - _ _ - _ _ _ . -________ _ -_
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-15 Unit 2 System Name: Component Cooling O&M Number: OM-066 Sh.1 BGE Dwg Number: 60724 Sh.1 Required Tests / Frequencies l e S E Y g e 3
$ $ # $ 7 E E E E $ e e W o 2 3
=- > >EY ~~
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.: a E .2 ;: w w s F S E$o N $ #ES E # E E EE E E5 it $ $3 0 E Remarks 2-CC-6450A-RV 3 C G8 .75 R - -
C O AO i S 2-CC-6471-RV 3 C E11 .75 R - - C O AO S 2-CC-6472-RV 3 C E10 .75 R - - C O AO S l s l , Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C ; BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S ! G - Globe Active / Passive Part-Stroke PS Per App. J J , R - Safety / Relief AO - Active Open Disassembly / Inspection DI ' PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK ! LLRT per App. J 1.J
._ -~- ~ . . - . . .- . .. -- .. .
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-16 Unit 2 System Name: Containment O&M Number: OM-065 Sh. 2 BGE Dwg Number: 60723 Sh. 2 l Required Tests / Frequencies l $ I E d E E a O n 8 s e e G ? + i E - s 7 "i . [l - i d E I 8 8 R E 4 5 , y E h$$ ME$ $ # E E EE E E 5E $$3 8 E Remarks 2-CPI-5313A-SV NC B C3 .75 G S X O O PO 2 ' 2-CPI-53138-SV NC B B3 .75 G S X O O PO 2 2-CPI-5313C-SV NC B D3 .75 G S X O O PO 2 2-CPI-5313D-SV NC B C3 .75 G S X O O PO 2 2-ILRT-1 NC A A6 .75 G - - C C PC J CIV 2-!LRT-2 NC A B6 .75 G - - C C PC J CIV i t I i Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKVMV Full-Stroke /Exercisc Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling e. : G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position !ndication PI AC- Active Closed Setpoint Testing SP i PC - Passive Clo;9d LeakTesting LK ! LLRT per App. J -LJ i T I
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-17 'i , Unit 2 System Name: Containment Ventilation O&M Number: CM-065 Sh.1 BGE Dwg Number: 60723 Sh.1 Required Tests / Frequ2ncies l 3 I . i= : Y g e 3
$ a o 7 1 1 6 E E E 2 &
!S E E$
U- $ h k $ 3 d f } S S R S E EE E E E 5 s-2-CPA-1410-CV** NC A B11
$ $ $ # E E 5 # %5 3 0 E Remarks i 8 BU A X C C AC R* R* 2 J CSJ-20l ;CIV: Disabled Mode 1-4 2-CPA-1411-CV** NC A B11 8 BU A X C C AC R* R* 2 J CSJ-20' CIV: Disabled Mode 1-4 i 2-CPA-1412-CV" NC A D11 8 BU A X C C AC R* R* 2 J CSJ-20 CIV:Disabied Mode 1-4 2-CPA-1413-CV" NC A D11 8 BU A X C C AC R* R* 2 J CSJ-20 lCIV; Disabled Mode 1-4 i i
** Effective Until Completion of ESP 94-205 *And any cold shutdown i period during which containment purge ;
is established. 2-CPA-1410-CV~ NC B B11 8 BU A X C C AC R* R* 2 CSJ-20 Cmnt Closure Mode S&6 2-CPA-1412-CV~ NC B D11 8 BU A X C C AC R* R* 2 CSJ-20 Cmnt Closure Mode S&6 '
~ Effective Following Completion of ESP 94-205l Valve Actuator Normal / Safety Required Tests Required Freqs.
Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterfy O BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open - POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling G G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi i AC - Active Closed Setpoint Testing SP t PC - Passive Closed Leak Testing LK LLRT per App. J -LJ
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-18 Unit 2 System Name: Containment Ventilation O&M Number: OM-065 Sh. 2 BGE Dwg Number: 60723 Sh. 2 ' Required Tests / Frequencies e E
$ E i d d 3 i 8 g 8 : l i s e e i +
W U ~~ ? t 2 * > >: d 5' 3 b e ~ i O U O o
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E-s E $ # 2.s 4 # 2EE EE E 5 it % 5 3 0 E Remarks ! 2-HP-104 NC AC F4 4 C - - C C AC R J RFJ-01 CIV 2-HP-6900-MOV NC /. C5 4 GA M X C C AC Q 2 J CIV 2-HP-6901-MOV NC A GS 4 GA M X C C AC Q 2 J CIV 2-HP-6903-MOV NC A FS 4 GA M X' C C AC C 2 J CSJ-21 CIV ! Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ
Baltimore Gas & Electric Calvert Cliffs Nuclear Power Plant Unit 2. IST Program - Valves Page E-19 Unit 2 System Name: Demineralized Water O&M Number: OM-460 Sh.1 BGE Dwg Number: 62/29 Sh.1 i Required Tests / Frequencies l e S y i s e i e e 0 t 8 UJ U =z-
'i
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b G E O U O U E + E: 2 lE - E e g .: m t: ,
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$ kh$b 5 ME$ E M EEE E EEo if.$ 5 '., 8 E Remarks 2-DW-5460-CV NC A B11 2 G AlX O/C Cl AC Q Q 2 J CIV i
l Valve Actuater Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J 'LJ i
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C C EEW b y c t HS aoMiAe nleto r ua t A A h=Oi s t e .c r i dn or o r m C oi a d E D $E $E N vl 8 8 a e PAPAA TOCPN l m e r t CCOOc t - - - oo s 1 1
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Baltimore Gas & Eledre Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-21 Unit 2 System Name: Feedwater O&M Number: OM-040 Sh. 4 BGE Dwg Number: 62702 Sh.4 [-~ Reqbired Tests / Frequencies l 5 I j # g d i a 0 t 8 z & E s e e G ? e i E - 2 7 9 C i d E I S S R E ; $
$ Eh $ NhME$ $ M E E E E EE 5 i[ . 5 3 8 e Remarks 2-FW-130 2 C F6 16 C -
-lOlC AC C CSJ-22 2-FW-133 2 C B6 16 C - -
c C AC C CSJ-22 2-FW-4516-MOV 2 B B7 16 G M X O C AC C 2 CSJ-23 2-FW-4517-MOV 2 B F7 16 G M X O C AC C 2 CSJ-23 I Valve Actuator Normal / Safety Required Tests Requered Freqs. Type Type Position (s) CKV/HV Full-StrokeExercise Open M@." ' Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Fu!i-Stroke / Exercise Closed
. iC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Fu!I-Stroke Time Open .STO Refueling R C - Check S - Solenoid T - Throttled (Open) FOV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App.J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pl AC- Active Closed Setpoint Testing .SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
\ _ _- ______ _ ______ ______________ _
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-22 Unit 2 System Name: Fire Protection O&M Number: OM-056 Sh. 2 BGE Dwg Number: 60714 Sh. 2 l Required Tests / Frequencies l , 3 I y Y g d 3 z
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l ! Valve Actuator Normal / Safety Required Tests Required Freqs. ! Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q ; BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Coid Shutdown C I BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T- Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 ; GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK t LLRT per App. J -1.J
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Piani Unit 2, IST Program - Valves Page E-23 Unit 2 System Name: Gas AnsiyzinD O&M Number: OM-463 Sh.1 BGE Dwg Number: 60744 Sh.1 Required fests / Frequencies l 5 l $
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_. 2-PS-6507D-SV NC A C12 .25 G S X O/C _C AC Q Q 2 J CIV 2-PS-6507E-SV NC A C4 .25 GiS X O/C C AC Q Q 2 J CIV 2-PS-6507F SV NC A C4 .25 G S X O/C C AC Q Q 2 J CIV 2-PS-6531 -SV NC A F6 .25 G S X O/C C AC Q-Q 2 J CIV 2-PS-6540A-SV NC A B3 .25 G S X O/C C AC Q Q 2 J CIV 2-PS-65408-SV NC A B11 .25 G S X O/C C AC Q Q 2 J CIV 2-PS-6540C-SV NC A B12 .25 G S X O/C C AC Q Q 2 J CIV 2-PS-6540D-SV NC A B12 .25 G S X O!C C AC Q Q 2 J OiV 2-PS-6540E-SV NC A B4 .25 G S X O/C C AC O O 2 J CIV 2-PS-6540F-SV NC A B4 .25 G S X O!C C AC Q Q 2 J CIV i I l Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball t - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly wt - Motor O - Open POV Fuil-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke lime Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO- Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J ' LJ i
Baltimore Gas & Electric Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-24 Unit 2 System Name: Gas Analyzing O&M Number: OM-463 Sh.2 BGE Dwg Number: 60744 Sh. 2 Required Tests / Frequencies l t : y Y d d i e 0 g 8 e e & + e UJ U =z i
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Baltimore Gas & Electric, Calveit Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-25 Unit 2 System Name: Instrumen! Air O&M Number: OM-454 Sh. 3 BGE Dwg Number: 62712 Sh. 3 - l Required Tests / Frequencies y : li g s 1
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Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-26 Unit 2 System Name: Instrument Air O&M Number: OM-454 Sh. 3 BGE Dwg Number: 62712 Sh. 3 l l Required Testa / Frequencies l 5 I
$ E N 4 d E
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2-IA-2085-CV NC B C8 38G A X O C AC C C 2 CSJ-24 2-IA-2058-RV NC C F8 1 R - - C O AO S ~~ 2-IA-4070-RV NC C 17 75 R - - C O AO S 2-lA-4070A-RV e r?C C 17 .75 R - - C O AO S 2-lA-4071-RV NC C 19 .75 R - - C O AO S 2-IA-4071A-RV NC C H9 .75 R - - C O AO S 2-IA-5200-RV NC C F9 .25 R - - C O AO S 2-IA-5201-RV NC C E9 .25 R - - C O AO S 2-lA-6301A-RV NC C G9 .75 R - - C O AO S - 2-IA-63b i B-RV NC C G7 .75 R - - C O AO S Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterfy Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Fuli-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication Pi AC- Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
_ _ _ _ _ . -_ . . ~ _ _ . . _ . - . . . . _ _ _ _ _ . _ _ . _ . _ ._.. _ . - Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-27 Unit 2 System Name: Liquid Waste O&M Number: OM-077 Sh.1 BGE Dwg Number: 60734 Sh.1 l Required Tests / Frequencies l y i e e 3 z
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- Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ba!! A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C t BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R t C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S ,
G - Globe Active / Passive Part-Stroke PS Per App J J R - Safety / Relief AO - Active Open Disassembly / inspection DI : PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP ! PC - Passive Closed L eak Testing LK LLRT per App. J ' LJ I
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-28 Unit 2 System Name: Main Steam O&M Number: OM-036 Sh.1 BGE Dwg Number: 62700 Sh.1 Required Testsi Frequencies ]
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_C O AO S 2-MS-3994-RV 2 B F6 6 R - - C O AO _ S-2-MS-3995-RV 2 B FS 6 R - - C O AO S 2-MS-3996-RV 2 B FS 6 R - - C O AO S 2-MS-3997-RV 2 B F4 6 R - - C O AO S 2-MS-3998-RV 2 B F4 6 R - - C O AO S 2-MS-3999-RV 2 B F4 6 R - - C O AO S 2-MS-4000-RV 2 B B6 6 R - - C O AO S 2-MS-4001-RV 2 B B6 6 R - - C O AO S 2-MS-4002-RV 2 B B6 6 R - - C O AO S 2-MS-4003-RV 2 B B5 6 R - - C O AO S 2-MS-4004-RV 2 B B5 6 R - - C O AO S 2-MS-4005-RV 2 B B4 6 R - - C O AO S 2-MS-4006-RV 2 B B4 6 R - - C O AO S 2-MS-4007-RV 2 B B4 6 R - - C O AO S Valve Actuator Normal / Safety Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS. Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspedion DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed . Leak Testing LK LLRT per App. J ' t.J j - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -
Baltimore Gas & Electric, C lvat Cliffs Nuclecr Power Plant Unit 2, IST Program - Valves Page E-29 Unit 2 System Name: Main Steam O&M Number: OM-036 Sh.1 BGE Dwg Number: 62700 Oh.1
] Required Tests / Frequencies l ,
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Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly Q BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Ttr r,ttled (Open) POV !:uli-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe FS Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication P! AC - Active Closed Setpoint Testing SP PC - Passive Closed Leak Testing LK LLRT per App. J LJ
Baltimore Gas & Electr'c, Calvert Cliffs Nuclear Power Plant iJnit 2. IST Program - Valves Page E-30 Unit 2 System Name: Main Steam O&M Number: OM-801 BGE Dwg Number: 62583 l Required Tests / Frequencies l 5 I y i g e i
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2-MS-103 2 C B9 6 C - - C O/C AO/AC C C Ql CSJ-27l 1 MS-106 2 C B8 6 C - - C O/C AO/AC C C Q' CSJ-27l 2-MS-108 2 C 07 6 C - - C O AO C Q CSJ-28i 2-MS-110 2 C B7 t 6 C - - C O AO C Q CSJ-28 2-MS-4070-CV 2 B B9 6 G A C O AO Q Q 2 2-MS-4070A-CV 2 8 89 2 G A C O AO Q Q 2 ; 2-MS-4071-CV 2 B B8 6 G A C O AO Q Q 2 2-MS-4071A-CV 2 B B8 2 G 'A C O AO Q Q 2 I Valve Actuator Normal / Safety Required Tests Required Freqs. Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarterly G BA - Ball A - Air C - Closed CKV/HV Full-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check S - Solenoid T - Throttled (Open) POV Full-Stroke Time Closed FSTC 2-Year 2 GA - Gate H - Hand Fail-Safe F3 Sampling S G - Globe Active / Passive Part-Stroke PS Per App. J J R - Safety / Relief AO - Active Open Disassembly / Inspection DI PO - Passive Open Position Indication PI AC - Active Closed Setpoint Testing SP PC - Passive Closed Lesk Testing LK LLRT per App. J -Li
Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant Unit 2, IST Program - Valves Page E-31 Unit 2 - System Name: Nitmgen O&M Number: OM-068 BGE Dwg Number: 60726 Required Tests / Frequencies e I j i e d 3 - E 5 E e E HE li E E E
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- Type Type Position (s) CKV/HV Full-Stroke / Exercise Open FSEO Quarter 1y Q BA - Ball A - Air C - Closed CKV/HV Fuli-Stroke / Exercise Closed FSEC Cold Shutdown C BU - Butterfly M - Motor O - Open POV Full-Stroke Time Open FSTO Refueling R C - Check !
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1 I Baltimore G:s & Electric, Calvert Cliffs Nuclear Power Plant Unit 2. IST Program - Valves .- Page E-32 Unit 2 System Name: Plant Air O&M Number: OM-479 Sh. 2 BGE Dwg Number: 60746 Sh. 2 Required Tests / Freq'sencies j u e I e > g : e e s =
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Ba!timore Gas & Electric, Calvert Cliffs Nudear Power Plant Unit 2. IST Program - Valves Page E-41 Unit 2 System Name: Safety injectiori / Containment Spray O&M Number: OM-462 Sh.1 BGE Dwg Number: 62731 Sh.1 l Required Tests / Frequencses l U S S E I J J E E $ a 8 e E E M E E E 2 &
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1 Baltimore Gas & Eledric, Calvert Cliffs Nuclear Power Plant Unit 2. IST Program - Valves Page E-44 Unit 2 System Name: Safety injedion/ Containment Spray O&M Nurrber OM-462 Sh. 2 BGE Dwg Number: 62731 Sh.2 l Required Tests / Frequencies l 3 I y : Y 4 4 3
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Baltimore Gas & Eledric. Calvert Cliffs Nuclear Power Plant 'Jnit 2, IST Program - Valves Page E-45 Unit 2 System Name: Safety injedion/ Containment Spray O&M Number: OM462 Sh. 2 BGE Dwg Number: 62731 Sh.2 l Required Tests / Fret 2ncies [
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Page F 1 RELIEF REQUEST NO, VM-01 SYllfihil Various - This is a generic relief request. COhiPONEJiLS; All Class 2 and 3 safety and relief valves used for compressible fluid services other than steam. CAII1G01tY; - C l FUNCTIQM; Provide over pressure protection for vatlous safety related plant systems and components. PART 1 REO_UIREhjUEI; Accumulator Volume. There shall be a minimum accumulator volume below the valve inlet, based on the valve capacity (cu fl) and calculated from the following formula: hiinimum Volume = [ valve capacity (cu fl per see) X time open (sec) /10. (Paragraph 8.1.2.2) BASIS FOR REl.lEF; The accumulator volume requirement is not required for simple determination of the valve set pressure. This was recognized by the Code Committee ano corrected in more recent versions of the Oh! Code. ALTERNATE TESTING; The volume of the accumulator drum and the pressure source flow rate shall be sullicient to determine the valve set pressure. (Ref. AShiE Ohi Code-1990, Ome-1994 Addenda, Paragraph I 8.1.2)
Page F-2 RELIEF REQUEST NO, VR-02 SYSTEht Various - This is a generic relief request. COMPONENISJ All Class 2 and 3 safety and relief valves tested under ambient conditions using a test medium at ambient conditions. l CATEGORY: - FUNCTION: Provide over pressure protection for various safety-related plant systems and components. < PART 1 REOUIREMENT: Temperature Stability. The test method shall be such that the temperature of the valve body shall be known and stabilized before commencing set pressure testing, with no change in measured temperature of more than 10 deg-F (5 deg-C)in 30 minutes. (Paragraph 8.1.3.8) DASIS FOR RELIEF; For testing under normal prevailing ambient conditions with the test medium at approximately the same temperature, the requirement for verifying temperature stability is inappropriate and an ineffective use of resources. There is little or no consequence of any minor changes in ambient temperature. This has been identified by the OM 1 Code Working Group and the ASME Code Committees and is reflected in the latest version of the Code (OM Code-1995) Paragraphs 18.1.2(d) and I 8.1.3(d). ALTJiRNATE TESIlliG; For safety and relief valves tested under ambient conditions using a test medium at ambient conditions, the test temperature will be recorded prior to each test but there will be no verification of thermal equilibrium performed.
Page F.3 REI lEF REQUEST NO. VR 03 SYSTEM: Various - This is a generic relief request. COMPONENTS: All safety and relief valves tested under ambient conditions using a test medium at ambient conditions. CATEGORY: l C l
\
I FUNCTION: Provide over pressure protection for various safety-related plant systems and components. , i PART 1 REOUIREMENT: Test Media " Valves shall be tested with the normal system operating fluid and temperature for which they are designed, Alternative liquids or different temperatures may be used, provided the requirements of para, 8,3 are met." BASIS FOR RELIEF; These valves are nonnally installed on various systems throughout the plant. Based on potential variations in ambient conditions as well as system operating conditions, a discrete design / operating temperature cannot practically be determined for each valve. Obviously, . it is impractical to test the valve at multiple operating conditions, Based on input from valve manufacturers, typically safety valve setpoints vary inversely with the temperature of the valve, Thus it can be deduced that measuring a valve's setpoint at the lowest temperature that a valve is expected to experience when its protection is required will ensure adequate protection at the elevated temperatures. Clearly, this is a conservative application of the Code requirement. The only adverse concern is that of the potential for premature lifting of a valve. Although this is of some limited operational concern, in no case does it pose a significant safety concern.
Page F-4 RELIEF REQ'UEST NO. VR-03 (cont.) ALTERNATE TESTING: Each of these valves will be setpoint tested in accordance with Part I with the excepion that tests will be conducted at ambient shop temperatures with no temperature correlation required.
)
t 4 I l'
Page F-5 RELIEF REQUEST NO. VR-04
' EYSTEM1 Reactor Coolant and Waste Process Sampling (60/62 724-E, Sheet 1)
C011PONENTS: 1 -PS-5464-CV, 1 -PS-5465-CV,1 -PS-5466-C V,1 -PS-5467-CV 2 PS 5464-CV,2 PS-5465-CV,2-PS 5466-CV,2-PS 5467-CV Withdrawn i.
-...--_,_..,.-%... .: ..,E i .- - '-
. Page F-6 RELIEF REQUEST NO. VR-05 SYSTEAt Safety Injection and Containment Spray (60/62-731-E, Sheet 1)
. COMPONENTS:
SI-4146 and 1-SI-4147 l 2-S1-4146 and 2-SI-4147 CATEGORY: - C
- l. ,
r FUNCTION: Open to allow safety injection and containment spray pumps to take suction from the RWT. 'When the systems are switched from injection to recirculation, they close to prevent backflow when the sump and tank isolation valves are both open at the same time. PART 10 REOUIREMENT: Check valves shall be exercised nominally every 3 months, except as provided by Paragraph 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2,5, (Paragraph 4.3.2) As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to determine operability of check valves may be used. (Paragraph 4.3.2.4(c)) BASIS FOR RELIEF: These are simple check valves that have no external means to exercise them. Exercising with system flow is not practical since a test simulating all of the combinations of operating pumps is not feasible. The alternate testing proposed below meets the intent of NRC Generic Letter 89-04, Position 2 for sample inspection programs. 9
Page F-7 RELIEF REQUEST NO. VR-05 (cont.) Backaround Each of these valves has been disassembled and ic=pected in the past and they have not
~
' displayed any indication of degradation that would impede their capability to perform their safety function to open.
ALTERNATE TESTING: l During each reactor refueling outage atleast one of these valves will be disassembled, inspected, and manually exercised on a sequential and rotating schedule. If, in the course
~ of this inspection a valve is found to be inoperable with respect to its function to fully '
open, then the other valve will be inspected during the same outage. During actisities .- associated with valve disassembly and inspection and prior to system closure, appropriate precautions will be applied and inspections performed to ensure internal cleanliness
- standards are maintained and foreign materials are excluded from valve and system internals. These measures may include creating controlled work areas, maintaining a tool and equipment accounting system, installation of covers during non-work periods, and '
final close-out inspections. Following valve re-assembly, the subject valve will be partial-stroked in the open direction. These functional testing activities will ensure that the subject valve has been re-assembled and aligned properly. They are also part-stroked quarterly.
Page F 8 - RELIEF REQUEST NO. VR-06
- SYSTEM:
Safety Injection ar.d Containment Spray (60/62-731-E, Sheets 1&3) COMPONENTS: 1-SI 314,1-SI-319,1-SI-324,1-SI-329,1-SI-432,1-SI-440,1-SI-441,1-SI-444,1-SI-- 452,1-SI-453,1-SI-456 and 1-SI-457, 2-SI-314,2-SI-319,2 SI-324,2-SI-329',2-SI-432,2-SI-440,2-SI-441,2-SI-444,2-SI-452,2-SI-453,2 SI-456 and 2-SI-457, -
. CATEGORY:
B FUNCTION: Provide flowpaths and appropriate lineups for shutdown core cooling. PART 10 REOUIREMENT: l Active Category A and B valves shall be tested nominally every 3 months, except as provided by paras. 4.2.1.2, 4.2.1.5, and 4.2.1.7. BASIS FOR RELIEF: These manual (handwheel-operated) valves are opened or closed as required to establish flowpaths for shutdown core cooling. _ During plant operation, operation of these valves requires significant effort on the part of the plant staff with no commensurate benefit in plant safety. Although this reason justifies test deferral, it does not strictly meet the criteria set forth in Part 10, Paragraph 4.2.1.2 as clarified by NUREG-1482, Paragraph 3.1.1. The requirement to exercise these valves comes from the Code requirement to test all those valves needed to shut down and cool down the reactor plant to cold shutdown. Per the Calvert Cliffs licensing documents, the plants (Units 1&2) are clearly licensed and fdesigned to achieve " safe shutdown vs. cold shutdown where safe shutdown is defined as -- the hot standby condition. In NUREG-1482 (Paragraph 2.2) the NRC agrees that for cases such as this, components that are not required to operate to achieve safe shutdown
- and are only needed to achieve
Page F-9 I RELIEF REQUEST NO. VR-06 (cont.) l BASIS FOR RELIEF (conth cold shutdown need not be included in the IST Program as active valves. This is clearly
. the case for these valves and, as such, testing of these valves is considered to be an l
additional requirement imposed by the plant staff but not required by the regulation (10CFR50.55a). Historically, the performance of these valves with respect to their operability has been satisfactory. Thus, exercising these valves at a cold shutdown interval is reasonable and justified and is adequate to ensure continued oper tional readiness and reliability for these valves. Note also that, recognizing the apparent lack of value in exercising manual valves, the ASME OM-10 working group is currently considering extension of the exercise interval for manual valves to as much as five (5) years. ALTERNATE TESTING: Each of these valves will be exercised to the full-open and closed positions during cold shutdown conditions pursuant to the conditions set forth in Part 10, Paragraphs _4.2.1.2(c), 4.2.1.2(f), and 4.2.1.2(g), They are exercised any time the plant is placed into a Shutdown Cooling Line-up Per plant procedures, any deificiencies encountered when operating these valves will be reported and evaluated per CCNPP's Issue Reporting system.
. .i
______._a..
Page F-10 RELIEF REQUEST NO. VR-07 SYSTEM: ' Safety Injection and Containment Spray (60/62-731-E, Sheet 2) COMPONENTS: 1-SI-215,1-SI-225,1-SI-235 and 1-SI-245 2-SI-215,2-SI-225,2-SI-235 and 2-SI 245 CATEGORY: - A/C 4 FUNCTION: Provide flowpaths from the SI tanks to the RCS cold legs. Upon initiation of safety injection (pump operation), they remain closed to isolate the SI tanks from the safety 4 injection headers to prevent diversion of safety injection flow into the Si tanks and possibly over-pressurization of the tanks. They also serve as pressure isolation valves (PIVs) during normal operation. PART 10 REOUIREMENT: Check valves shall be exercised nominally every 3 months, except as provided by Paragraph 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5. (Paragraph 4.3.2) As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to determine operability ofcheck valves may be used. (Paragraph 4.3.2.4(c)) \ B ASIS FOR RELIEF: These are simple check valves that have no external means to exercise them. Opening them requires forcing water from the safety injection tanks to the reactor coolant system. During normal operation, RCS pressure is higher thm safety injection tank pressure; therefore, opening is not possible. During cold shwdowns periods " dumping" a safety injection tank is also not practical due to the plani conditions and the extensive system preparations (including instrumenting the check valves) required for the evolution. During refueling outages, it is possible to " dump" each safety injection tank to exercise each check valve. However, flow indication is not available and full design flow cannot be achieved due to the slow opening stroke
Page F-11 RELIEF REQUEST NO. VR-07 (cont.) BASIS FOR RELIEF (cont 3: time of the SIT discharge MOV's. Therefore, the ability of each check valve to full-stroke can only be confiwd using non intrusive monitoring techniques. (Due to their service conditions, these check valves cannot remain instrumented.)
Background
= Each of these valves has been disassembled and inspected in the past and they have not displayed any indication of degradation that would impede their capability to perform their safety function to open.- ALTERNATE TESTING: During each refueling outage each of these check valves will be exercised and shown to full stroke using non-intrusive test methods. In the event that a valve does not full-stroke ' or the test results are inconclusive, valve disassembly and inspection per Generic Letter 89-04 Position 2 may be performed rather than re-filling and re-dumping the SIT due to various considerations, including outage schedule. The scope of valve disassembly will - depend on test results and inspection results, but it will not ordinarily include valves for
- which positive satisfactory results were obtained from non-intrusive testing. Additionally,
- since normal operating conditions preclude leaving the valves instrumented, valve
- disassembly / sampling may be used in lieu of full stroking these check valves to minimize personnel radiation exposure when refueling outage conditions warrant or check valve -
maintenance is already planned. During activities associated with valve disassembly and inspection and prior to system closure, appropriate precautions will be appli.ed and inspections performed to ensure -- internal cleanliness standards are maintained and foreign materials are excluded from valve and system internals. These measures may include creating controlled work areas, maintaining a tool and equipment accounting system, installation of covers during non-work periods, and final close-out inspections. These valves are part-stroked following re-assembly, if disassembled._ These functional testing activities will ensure that the subject valve has been re-assembled and aligned properly. The closure of these check valves is confirmed on an ongoing basis as a result of SIT )evel/ pressure monitoring, and they are also part-stroked quarterly.
Page F-12 RELIEF REQUEST NO. VR-08 i SYSTEM: Safety injection and Containment Spray (60/62-731-E, Sheet 2)
- COMPONENTS:
St-217,1-SI-227,1-SI-237 and 1-SI-247 2-SI-217,2-SI-227,2 SI-237 and 2-SI-247 CATEGORY: - A/C-FUNCTIQH; Provide flowpaths from the safety mjection tanks and safety injection pumps to the RCS cold legs. They also serve as pressure isolation valves (PIVs) during normal operation.
-PART 10 REOUIREMENT:
Check valves shall be exercised nominally every 3 months, except as provided by Paragraph 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5, (Paragraph 4.3.2) _ As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to determine operability.of check valves may be used. (Paragraph 4.3.2.4(c)) BASIS FOR RELIEF: These are simple check valves that have no external means to exercise them. Opening them requires forcing water from the safety injection tanks to the reactor coolant ' system. During normal operation, RCS pressure is higher than safety injection tank pressure = therefore opening is not possible. During cold shutdowns periods " dumping" a safety injection tank is also not practical due to the plant conditions and the extensive system preparations required for the evolution. During refueling outages, it is possible to " dump" each safety injection tank to exercise each check valve, However, flow indication is not available and full design flow cannot be achieved due to the slow opening stroke time of the SIT discharge MOV's. Therefore, the ability of each check valve to full-stroke can only be confirmed using non-intrusive monitoring techniques.-
~
Alternatively, these check valves may be full-stroked using the discharge of a low pressure safety injection pump. However, since the check valves have no external position
- indication, verifying their full-stroke open and closed, still requires non-intrusive
Page F-13 RELIEF REQUEST NO. VR-08 (cont.) BASIS FOR RELIEF (cont 3: monitoring techniques, Due to their eervice conditions these valves cannot remain instrumented and it is not considered practical to instrument them during a cold shutdown
- period.
, Backaround Each of these valves has been disassembled and inspected in the past and they have not i displayed any indication of degradation'that would impede their capability to perform their safety function to open. - L ALTERNATE TESTING:
- During each refueling outage each of these check valves will be exercised and shown to full stroke using non-intrusive test methods. In the event that a valve does not full-stroke or the test results are inconclusive, valve disassembly and inspection per Generic Letter 89-04 Position 2 may be performed rather than re-filling and re-dumping the SIT due to various considerations, including outage schedule. The scope of valve disassembly will depend on test results and inspection results, but will not ordinarily include valves for which positive satisfactory results were obtained from non intrusive testing. Additionally, since normal operating conditions preclude leaving the valves instrumented, valve disassembly / sampling may be used in lieu of full-stroking these check valves to minimize personnel radiation exposure when refueling outage conditions warrant or check valve maintenance is already planned.
.During activities associated with valve disassembly and inspection and prior to system closure, appropriate precautions will be applied and inspections performed to ensure internal cleanliness standards are maintained and foreign materials are excluded from valve and system internals. These measures may include creating controlled work areas, maintaining a tool and equipment accounting system, installation of covers during non-work periods, and final close-out inspections.
These valves are part-stroked following re-assembly, if disassembled. These functional testing activities will ensure that the subject valve has been re-assembled and aligned properly.~ The closure of these check valves is confirmed on an ongoing basis by the presence of upstream pressure alarms (the system is configured such that leakage through all other valves bounding the section of piping monitored by each alarm cannot go - - unnoticed) and they are also part-stroked quarterly. Additionally, the ability of these check valves to at least part-stroke open will be verified during any cold shut down period in which LPSI pump full-flow testing is performed.
Page F-14 RELIEF REQUEST NO. VR-09 SYSTEM;
- Safety Injection and Containment Spray (60/62-731-E, Sheet 2) - COMPONENTS:
! l-SI-651-MOV and 1 SI-652-MOV I i SI-651-MOV and 2-SI-652-MOV I - CATEGORY: - A FUNCTION: Open to provide flowpaths for shutdown cooling flow from the reactor coolant system. They are normally closed during plant steaming operation and are designated containment
- isolation valves - leaktested per 10CFR50, Appendix J. . They are also reactor coolant system pressure isolation valves (PlV's). - PART 10 REOUIREMENT:
Category A valves, which are containment isolation valves, shall be tested in accordance with 10CFR50, Appendix J._ Containment isolation valves which also provide a reactor coolant system pressure isolation function shall additionally be tested 'in accordance with
' Paragraph 4.2.2.3. (Paragraph 4.2.2.2)
- Category A valves, which perform a function other than containment isolation, shall be seat leakage tested to verify their leak-tight integrity. (Paragraph 4.2.2.3) -
Frequency. Tests shall be conducted at least once every 2 years. (Paragraph 4.2.2.3(a)) BASIS FOR RELIEF: Leakage testing of these valves for both purposes is done concurrently using the same procedures and the same acceptance criteria. Recently, BGE has opted to convert to
" Option B" of the Appendix J Testing Program whereby valves that have had a history of good performance with respect to their leak tight integrity, may be tested at a frequency less than the two years required by Appendix J and Part 10. The Part 10 requirement to continue to perform seat
A Page F_-15 H RELIEFREQUESTNO VR-09(cont.) BASIS FOR RELIEF (cont.t leakage testing at 2-year intervals for containment isolation valves which also provide a reactor coolant system pressure isolation function would essentially eliminate the benefit of applying Option B to these valves and would subject these valves to unnecessary leak testing even when they meet Option .9 cnMria foe extending the Appendix J testing frequency. (It should be noted that locd leah rate testing these valves requires a reduced RCS inventory condition.) The consequences offailure (gross leakage) of one of these valves is not significant from the aspect of accident severity. There is two valve isolation between the LPCI piping and _ _; the reactor coolant system. Note that these are gate valves that are typically not subicct to catastrophic failure when statically closed. l Based on the past performance of these valves ~ and other issues discussed above, leakage testing of these valves at an extended frequency as permitted by Option B is adequate to ensure the continued operability and reliability of these valves. ALTERNATE TESTINGM i These valves will be leak tested on a schedule in accordance with the requirements of 10CFR$0, Appendix J Option B, as discussed in Regulatory Guide 1,163. No additional leak testing will be performed. i._m
Page F-16 RELIEF REQUEST NO. VR-10 SYSTEM: Safety Injection and Containment Spray (60/62 731-E, Sheet 3) l COMPONENTA: 1-SI-316,1-SI-326,1-SI-330 and 1-SI-340 2-SI-316,2 SI-326,2-SI-330 and 2-SI-340 CATEGORY: 4 A/C FUNCTION: These check valves open to provide flowpaths from the containment spray pumps to the i containment spray headers in containment. They close for containment isolation. PART 10 REOUIREMENT: Check valves shall be exercised nominally every 3 months, except as provided by Paragraph 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5. (Paragraph 4.3.2) As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to determine operability of check valves may be used. (Paragraph 4.3.2.4(c)) BASIS FOR RELIEF; Full-stroke exercising these valves to the open position would require operating each containment spray pump at nominal accident flowrate. Since no recirculation flowpath exists downstream of these valves, the only flowpath available for such a test would result in injecting radioactive-contaminated borated water into the containment spray headers and into the containment building via the spray nozzles.
I1 Page F-17 RELIEF REQUEST NO. VR-10 (cont.)
- BASIS FOR RELIEF (cont 3 Partial stroking of tl:a valves can be achieved by pressurizing the upstream piping with ~ air -
or nitrogen via the air test connection. Performing partial flow exercising by this method during any mode of plant operation (at power or cold shutdown), however, has the potential of creating an airborne contamination personnel hazard in the auxiliary building and containment. The alternate testing proposed below m' e ets the intent ofNRC Generic Letter 89-04, Position 2 for sample inspection programse
Background
Each of these valves has been disassembled and inspected in the past and they have not displayed any indication of degradation that would impede their capability to perform their safety function to open. A.LTERNATE TESTING: During each reactor refueling outage at least one of these valves will be disassembled, inspected, and manually exercised on a sequential and rotating schedule. If, in the course of this inspection a valve is found to be inoperable with respect to its function to fully i open, then the other valves will be inspected during the same outage. During activities associated with valve disassembly and inspection and prior to system closure, appropriate precautions will be applied and inspections performed to ensure internal cleanliness standards are maintained and foreign materials are excluded from valve and system internals. These 'neasures may include creating controlled work areas, maintaining a tool
- and equipment a: counting system, installation of covers during non-work periods, and final close-out inspections.
Following valve re-assembly, the subject valve will be partial-stroked in the open direction and a seat leakage test will be performed. These Fanctiorial testing activities will ensure that the subject valve has been re-assembled and aligned properly. Part-stroking of these
' check valves is included in the cold shutdown testing program.
Page F-18 RELIEF REQUEST NO. VR 11 SYSTEM: Safety Injection and Containment Spray (60/62-731-E, Sheet 3) i COMPONENTS: 1-SI-4148 and 1-SI-4149 ' i 2-SI-4148 and 2-SI-4149
; CATEGORY: .
A/C-FUNCTION: These check valves open to provide flowpaths from the containment sumps to the containment spray and safety injection pumps during post accident recirculation cooling. When the systems are switched from injection to recirculation, they close to prevent backflow into the sump when the sump and tank isolation valves are both open at the same time. PART 10 REOUIREMENT: Check valves shall be exercised nominally every 3 months, except as provided by Paragraph 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5. (Paragraph 4.3.2)_. As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to determine operability of check valves may be used. (Paragraph 4.3.2.4(c)) BASIS FOR RELIEF; These are simple check valve-s that have no external means to exercise them. Exercising with system flow is not practical since there is no water inventory available for such a test. Partial stroking of the valves can be achieved by pressurizing the upstream piping with air or nitrogen via the air test connection. Performing partial flow exercising by this method ' ' during any mode of plant opention (at power or cold shutdown), however, has the potential of creating an airborne contamination personnel hazard in the auxiliary building and containment.
Page F-19 RELIEF REQUEST NO. VR-11 (cont., BASIS FOR RELIEF (cont.h The attemate testing proposed below meets the intent of NRC Generic Letter 89-04, Position 2 for sample inspection programs. Each of these valves has been disassembled and inspected in , *e past and they have not displayed any indication of degradation that would impede the.. capability to perform their safety function to open. Background ' Each of these valves has been disassembled and inspected in the past and they have not displayed any indication of degradation that would impede their capability to perform their safety function to open. ALTERNATE TESTINQ During each reactor refueling outage at least one of these valves will be disassembled, inspected, and manually exercised on a sequential and rotating schedule. If, in the course of this inspection a valve is found to be inoperable with respect to its function to fully open, then the other valve will be inspected during the same outage. During activities l associated with valve disassembly and inspection and prior to system closure, appropriate l precautions will be applied and inspections performed to ensure internal cleanliness standards are inaintained and foreign materials are excluded from valve and system internals. These measures may include creating controlled work areas, maintaining a tool and equipment accounting system, installation of covers during non-work periods, and final close-out inspections. Following valve re-assembly, the subject valve will be partial-stroked in the open direction and a seat leakage test will be performed. These functional testing activities will ensure that the subject valve has been re-assembled and aligned properly Nrt-stroking of these check valves is included in the cold shutdown testing program.
Page F-20 RELIEF REQUEST NO, VR-12 !
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S.Y. STEM: Instrument Air (60-712, Sheet S & 62-712 Sheet 3) COMPONENTS: ' l-IA-728, 2-IA-314,2-IA-317, and 2-IA-1110 , _ CATEGORY: . B l- FUNCTION: ( These manual valves are opened to align back-up operating air from the Saltwater Air Compressors (SWACs) to the AFW portion of the IA System, in order to maintain operating air to AFW control valves during later stages of an accident. PART 10 REOUIREMENT: Active Category A and B valves shall be tested nominally every 3 months, except as provided by paras; 4.2.1.2,4 2.1.5, and 4.2.1.7. (Note that these manual valves are aqt - within the ASME/ISI class boundaries.) B ASIS FOR RELIEF: These manual valves are opened during the later stages of an accident after the dedicated
--. AFW air accumulators are exhausted to allow operating the AFW control valves using SWAC air. However, this function would not be required to achieve CCNPP's safe shutdown condition. Although not required, this function is considered desireable.
Note that these manual valves are not within the ASME/ISI class boundaries. Therefore, their inclusion in the IST Program is not required. However, they have been included in the Augmented Testing Program which was consolidated with the IST Program to allow __ efficient allocation of testing resources. The purpose of this " relief reguest" is to document, for completeness, the basis for the apparent " deviation" from the Code.
Page F-21 RELIEF REQUEST NO. VR-12 (cont.) B ASIS FOR RELIEF (cont.): The requirement to exercise these valves comes from the Code requirement to test all those valves needed to shut down and cool down the reactor plant to cold shutdown. Per the Calvert Cliffs licensing documents, the plants (Units 1&2) are clearly licensed and designed to achieve " safe shutdown" vs. cold shutdown where safe shutdown is defined as the hot standby condition. In NUREG-1482 (Paragraph 2.2) the NRC agrees that for i cases such as this, components that are not required to operate to achieve safe shutdown and are only needed to achieve cold shutdown need not be included in the IST Program as l active valves. This is clearly the case fo'r these valves and, as such, testing of these valves i is consideted to be an additional requirement imposed by the plant staff but not required l by the rec.ilation (10CFR50.55a), These manual valves are exercised during refueling outages when the instrument air check valves are full-stroke exercised. This is considered adequate to ensure continued operational readiness and reliability for these valves. Exercising these valves quarterly is not considered to provide any additional benefit. Note also that, recognizing the apparent lack of value in exercising manual valves, the ASME OM 10 working group is currently considering extension of the exercise interval for manual valves to as much as five (5) years.
<ERNAIE_ TESTING:
Each of these valves will be exercised during refueling outages when the instrument air check valves are full-stroke exercised. I a
Page F-22 RELIEF REQUEST NO. VR 13 i SYSTEht Reactor Coolant (60/62-729-E, Sheet 1) COMPONENTS: 1-RC-200-RV and 1-RC-201-RV 2-RC-200-RV and 2-RC-201-RV CATEGORY: ' C ElJNCTION: The pressurizer safety valves provide overpressure protection for the reactor coolant system in the event of a loss ofload without a reactor trip. They also act as the ASME l Code safety / relief valves. I PART I REOUIREMENT: Valves insulated in service shall be insulated in like manner during testing. (Paragraph 8.1.1.4 - Temperature Stability). BASIS FOR RELIEF: Changes in safety / relief valve body temperature can change the lift setpoint measured during inservice testing. Changes in ambient temperature or modifications to insulation also may change the lift setpoint by virtue of the resulting effect on the valve body temperature. The purpose of Paragraph 8.1.1.4 is to ensure the effect of temperature variations are minimized. Requiring insulation to be installed during testing is clearly intended to also ensure the valve body's temperature, and therefore its performance, is similar to that under normal operating circumstances. Calvert Cliffs has determined the normal operating temperature profile for the pressurizer safety valves by instrumenting each valve body at several locations and recording empirical data during normal operation. Recently, Calvert Cliffs commissioned testing using the valves' actual operating temperature profile at a national vendor's testing facility to determine the impact of having the insulation removed versus installed during testing of the pressurizer safety valves. This testing showed that pressurizer safety valves which have had their setpoints satisfactorily verified in-situ will perform satisfactorily two years
Page F-23 RELIEF REQUEST NO. VR 13 (cont.) BASIS FOR RELIEF { cont,): later in a laboratory setting if the valve body's actual operating temperature profile is recreated. The test was conducted using two valves adjusted to their respective setpoints (which differ by only 65 psi). The first series of tests was performed with each valve uninsulated. Prior to setpoint testing, each valve was thermally stabilized at the specified temperature profile to match normal operating conditions. The valves performed within their as-found setpoint tolerance. ' The second series of tests was performed with each valve insulated (using the actual insulation from the plant normally installed on each valve). Prior to setpoint testing, each valve was thermally stabilized. However, due to the test configuration, the valve could not be thermally stabilized at the actual operating temperature profile. Instead, it could only be stabilized at a higher temperature. The overall impact of the higher temperature profile is that the lift pressure for the valves is lower than when at the correct temperature profile. This is a non-conservative error because, if the valves were adjusted to lift at their operating setpoint under these conditions, they would then be set to lift by as much as approximately 2% high when retumed to their normal plart installation. t l The third series of tests was performed with each valve insulated and with the j ambient temperature being varied. The variations in ambient temperature had little effect on the valve's lift pressure. Because of differences in the test configuration and the normal plant configuration, the vendor was unable to stabilize the valves' temperature profile when insulated consistent with the one specified for normal plant operating conditions. Rather, the temperatures measured at all the points being monitored, most notably the upper and lower bonnet, were higher. The higher temperature profile for the insulated valves in the testing configuration occurred because, when installed in the plant, these valves are attached to long runs of pipin3 with numerous associated piping supports which serve as heat sinks for the valves, but in the testing facility these long runs of piping are no longer attached. In the plant, these heat sinks allow the valves to stabilize at a lower temperature profile even when insulated, as compared to the temperature profiles when insulated in the vendor test facility. Additionally, the presence of forced ventilation in the field increases the heat transfer out of each valve body through the insulation for the same ambient temperature when compared to the stahnant conditions present in the test configuration.
Page F-24 RELIEF REQUEST NO. VR-13 (cont.) BASIS FOR REltlEF (cont.): 1 l In other words, the heat input and heat output of the insulated valves in a stagnant l environment cannot be balanced in the testing facility until the valves are hot enough to I create the necessary heat transfer rate through the insulation needed to offset the heat input. Since the heat transfer out of the valve to the attached piping is lost, more heat output through the insulation is required. This effect is additionally aggravated by the lack of forced ventilation. As a result, the valves stabilize at a higher temperature and the lift pressure measured was lower (by as much as approximately 2%) with the valves insulated and at these higher temperatures. ALTERNATE TESTING. OM-1 Paragraph 8.1.1.5 requires the ambient temperature of the operating environment to be simulated during the set pressure test. Additionally, if the effect of ambient temperature on set pressure can be established for a particular valve type, then OM-1 allows set pressure tests to be performed using an ambient temperature different from the operating ambient temperature as long as applicable correlations between the operating and testing ambient temperatures are used. The intent of using the normally installed insulation per Paragraph 8.1.1.4 and testing using the operating ambient temperature (or test ambient temperature with the appropriate correlation) is to ensure the valve performance during the test is indicative ofits expected performance under service conditions. However, Calvert Cliffs' has shown through comparative laboratory and in-situ tests that controlling the actual temperature profile of the valve body is a more realistic and more effective way of simulating insenice conditions and testing these valves. Additionally, it is much less likely to produce misleading test results that could lead to inappropriate setpoint adjustments. Therefore, Calvert Cliffs considers the requirements of Paragraph 8.1.1.5 to be satisfied by such testing and, based on the test results obtained at the vendor's laboratory, no correlation factor is applicable. When testing is performed in a vendor testing facility, vice in-situ testing, the valve body's temperature profile necessary to simulate normal operating conditions for these valves will be specified. The valve shall be stabilized at the required temperature profile per the remaining portion of Paragraph 8.1.1.4 prior to setpoint testing without requiring the valve to be insulated in a like manner to its inservice configuration.
Page G-1 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-01 l COMPONENTS: 1-AFW-102 and 1-AFW-116 l 2-AFW-102 and 2-AFW-116 l AFW Pump 11 (21) and 12 (22) Discharge Check Valves SAFETY FUNCTION: These valves open on to pmvide flowpaths from the respective AFW pump to the discharge headers. They close to prevent backflow through an idle pump. BASIS: These are simple check valves with no external means of exercising; l thus the only practical means of opening these valves u to operate L cach pump discharging to the steam generators. During plant
- operation at power this is not practical due to the potential for thermal shock of the steam generator nozzles or internals. During j
quarterly testing of the AFW pumps, flow is routed through a minimum flow recirculation line branching off upstream of these check valves that returns condensate to the condensate stomge tank and the respective pump's suction line, thus panial flow exercising is also impractical. In addition, the quanerly testing does not pressurize the common discharge header, thus verifying the closure of the check valve at the discharge of the idle pump is not possible without an extensive change in the system valve lineup. This is - consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G-2 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-02 COMPONENTS: 1-AFW-129 and 1-AFW-130 2-AFW-129 and 2-AFW-130 AFW Discharge To Steam Generators Check Valves SAFETY FUNCTION: These valves open on initiation of auxiliary feedwater flow to provide flowpaths from the AFW Pumps' discharge headers to the steam generators. ! BASIS: These are simple check valves with no external means of exemising; thus the only practical means of opening these valves is to operate i each pump discharging to the steam generators. During plant operation at power this is not practical due to the potential for thermal shock of the steam generator nozzles and internals. During quarterly testing of the AFW pumps, flow is routed through a minimum flow recimulatica line branching off upstream of these check valves that returns condensate to the condensate storage tank and the respective pump's suction line, thus partial flow exercising is also impractical. This is consistent with the position stated in t NUREG-1482, Paragraph 2.4.5.
Page G-3 -I APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-03 I COMPONENTS: 1-AFW-183 l 2-AFW-183 AFW Pump 13 (23) Discharge Check Valves SAFETY FUNCTION: These valves open to provide flowpaths fmm the AFW Pumps 13(23) to the disclarge headers. In addition, they are internally ported to pass 140 gpm to the recirculation header for minimum pump flow regardless of the valves' position. They close in the same manner as a check valve to prevent backflow through an idle pump when only steam-driven pump (s) are in operation - if the blocking valves remain in their normally-open position. BASIS: These are check valves with no external means of exercising; thus the only practical means of opening these valves is to opemte each pump discharging to the steam generators. During plant operation at power this is not practical due to the potential for thermal shock of the steam generator nozzles or internals. During quarterly testing of the AFW pumps, flow is routed through a minimum flow recirculation line branching off at these check valves that mturns condensate to the condensate storage tank and the respective pump's suction line, thus partial flow exercising is also impractical. This is consistent with the position stated in NUREG-1482, Pangmph 2.4.5.
Page G-4 i APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-04 COMPONENTS: 1-AFW-190 2-AMV-190 Unit 1(2) AMV Cross-Connect Check Valves SAFETY FUNCTION: These valves open to pmvide flowpaths from the opposite unit. BASIS: These are simple check valves with no extemal means of exemising; thus the only practical means of opening these valves is to operate each pump discharging to the steam generators. During plant operation at power this is not practical due to the potential for thermal shock of the steam generator nozzles or internals. During quanerly testing of the AFW pumps, flow is muted through a minimum flow recirculation line branching off upstream of these l check valves that returns condensate to the condensate storage tank and the respective pump's suction line, thus panial flow exercising is also impractical. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. NUMBER: CSJ-05 COMPONENTS: 1-AMV-193,1-AMV-194,1-AFW-199 and 1-AMV-200 2-AFW-193,2-AMV-194,2-AFW-199 and 2-AMV-200 AFW S/G Supply Check Valves SAFETY l'INCTION: Open on intiation of auxiliary feedwater flow from the AFW Pumps to provide flowpaths from the AFW pumps to the steam generators. BASIS: These are simple check valves with no external means of exercising; thus the only practical means of exercising is to operate each pump discharging to the steam generators. During plant opemtion at power this is not practical due to the potential for thermal shock of the steam generator nozzles or internals. During quarterly testing of the AMV pumps, flow is routed through a minimum flow recirculation line branching off upstream of these check valves that returns co.9densate to the condensate storage tank and the respective pump's suction line, thus partial flow exercising is also impractical. This is , consistent with the pc sition stated in NUREG-1482, Paragraph 2.4.5. T
Page G-5 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-06 COMPONENTS: 1 C VC-162 2-CVC-162 VCT Outlet Check Valves SAFETY FUNCTION: During emergency boration operations ther valves close to prevent backflow of borated water into the VCT, j BASIS: These are simple check valves with no' means of noting obturater position nor for manual exercising. Exercising these valves in the closed direction requires malignment of the CVCS system and 1 shifting the suction of the charging pumps to an alternate source of water or securing the pumps. During plant operation this would dismpt the CVCS system balance with the potential for causing severe pressurizer level transients or reactor coolant make-up boron concentration variations. Partial stmke exercising of these valves presents the same risks and pmblems that are associated with full-stmke exercising; thus it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G 6 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-07 COMPONENTS: 1-CVC-228 2-CVC-228 Emergency Boration Gravity Feed Check Valves SAFETY FUNCTION: During emergency boration operations these valves open to pro noe flowpaths from the boric acid storage tanks to the chargirg pump suction header. They close to prevent recirculation from 9 emergency boration line when the boric acid pumps are operating. BASIS: These are simple check valves with no means of noting obturater position nor for manual exercising. Exercising these valves in the - open direction requires realignment of the CVCS system and injection of concentrated boric acid into the reactor coolant system via the charging pumps. During plant operation this could disrupt the CVCS system balance with the potential for causing severe pressurizer level transients or reactor coolant make-up boron concentration variations, Partial-stroke exercising of these valves presents the same risks and problems that are associated with full-stroke exercising, thus it is also not feasible during operation. These valves can be confirmed closed (statically tested) quarterly. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. A
Page G-7 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-08 COMPONENTS: 1-CVC-235 2-CVC-235 Emergency Boration Check Valves SAFETY FUNCTION: During emergency boration operations these valves open to provide flowpaths from the discharge of the boric acid pumps to the charging pump suction headers. L BASIS: These are simple check valves with no means of noting obturater position nor for manual exercising. Exercising these valves in the open direction requires injection of concentrated boric acid into the reactor coolant system via the charging pumps. During plant operation this could dis:upt the CVCS system balance with the potential for causing severe pressurizer level transients or reactor coolant make-up boron concentration variations, Partial-stroke exercising of these valves presents the same risks and problems that are associated with full-stroke exercising, thus it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G 8 APPENDIX G: COLD SMUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-08A COMPONENTS: 1.CVC-251 2 C VC-251 Deeninerall ed Water Supply To VCT Check Valves SAFETY FUNCTION: If emergency boration is initiated while conceMrated boric acid is being added to the VCT, this check valve must close to prevent diversion of bode' acid into the demineralized water system and ensure sufficient boric acid is delivered to the suction of the charging J pumps. BASIS: Verifying the ability of this cheek valve to close requires applying a back pressure. The only source of a bachpretsure during normal operation is a boric acid pump (temporarily installing a test pump each quaner is not considered practical). However, the boric acid pump discharge pressure is high enough to create a concern regarding possible leakage past CV512 into the VCT (since there are no isolation valves between CV512 and the VCT). Under accident conditions with CV210Y open, seat leakage past CV512 into the VCT doce not present a concem because enough boric acid will still
)
reach the charging pump suction. However, during power operation, 1 any leakage of concentrated boric acid past CV512 into the VCT will affect reactivity and cause a reactor power transient. Furthermore, as the fuel cycle progresses and less boric acid is required in the RCS, the impact of such a reactivity changes will become more pronounced. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. When concentrated boric acid is batch added to the VCT during power operation, the operators are required to verify the plant response by checking the appropciste parameters, including VCT level, VCT pressure, and boric aes/ flow rate. This effectively verifies CVC251 is adequately closed, After each addition of concentrated boric acid to the VCT, demineralized water is used to flush the piping. This strokes open CVC251. Therefore, over the course of each quaner, this check valve is at least part stroked open and closed several times, However, since the degree of RCS boration declines as the fuel cycle progrestes, the frequency of adding concentrated boric acid to the VCT also decreases. It is not practical to add concentrated boric acid to the VCT sole y for the purpose of part-stroking CVC251.
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Page G 9 i j APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION ! NUMBER: CSJ49 COMPONENTS: 1 CVC 257 2-CVC 257
- RWT To Charging Pump Suction Check Valves SAFETY FUNCTION
- During normal plant operation, charging pump suction is fmtn the
- VCTs with makeup water supplied from the demlemlized water j storage tanks. H6 wever, should the VCT level decirase to 5 %, the nonnally-closed upstream MOVs (504 MOV) automatically open,
- VCT discharge salves (501 MOV) close, and these valves open to ensure a continuous supply of borated water to the charging pumps.
If emergency boration was required while in this line up, this check valve would shut to prever.t diversion of boric acid flow to the RWT, since MOV504 does not receive an emergency closure actuating signal. Additionally, following a SIAS (after the BASTS are empty) the charging pumps would be aligned to take suction from the RWT (requiring these valves to open) to de-pressurire the RCS to the shutdown cooling window upon the loss of the letdown system with or without auxiliary spray. BASIS: Exercising these valves requires realignment of the CVCS system and shifting the suction of the charging pumps to the refueling water storage tank (RWT). During plar,t operation tht) could disrupt the CVCS system balance with the potential for causing severe pressurizer level transients or reacter coolant make-up boron concentration variations. Panial stmke exercising of these valves presents the same risks and pmblems that are associated with full-stmke exercising, thus it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G 10 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 10 l COMPONENTS: 1 CVC-501-MOV l 2 CVC 501 MOV VCT Outlet Isolation Valves SAFETY FUNCTION: Close on SIAS to prevent backflow of concentrated boric acid solution into the VCT from the charging pump suction header. They also isolate the VCT to prevent dilution of the boric acid solution during emergency boration activities. BASIS: Exercising these valves requires a major realignment of the CVCS system. During plant operation this could dismpt the CVCS system - balance with the potential for causing severe pressurizer level tmnslents and a plant shutdown. Partial stroke exercising of these valves presents the same risks and pmblems that are associated with full stmke exercising, thus it is also not feasible during operation. This is consistent with the position stated in NUREG 1482, Paragmph 2.4.5. i
, - . , . -. . , _ ~ . , ._. . , _ . . , . . _ . _ . . _ , . . . _ _ . _ _ , ..-
1 I Page G 11 i 1 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION l NUMBER: CSJ 11 COMPONENTS: 1-CVC-504 MOV l 2-CVC-504-MOV l AWT To Charging Pump Suction Isolation Valves SAFETY FUNCTION: During nonnal plant operation, charging pump sNf bi is from the VCT with makeup water supplied from demineranc s water. Thould the VCT level decrease to 5 %, these valves automatically open and the VCT discharge valves, MOV 501, close to ensure e continuous supply of borated water to the charging pumps. If this were to occur in the early stages of an accident, valve closure would be required later in the accident scenario when transferring the charging pump ' - suction to the boric acid makeup tanks for emergency boration. Note that these valves do not automatically close on a SIAS. 'these valves - are manually opened within one hour following a SIAS to allow the charging pumps to take suction from the RWT to de-pressurize the . RCS to the shutdown cooling window upon the loss of the letdown I system with or without auxiliary spray. BASIS: Exercising these valves could result in an imbalance in the boron concentration of the reactor coolant makeup and a possible undesirable reactor power transient. Partial stroke exercising of these valves presents the same risks and problems that are associated with full stroke exercising, thus it is also not feasible during operation. This is consistent with the position stated in NUREG. 1482, Paragraph 2.4.5.
Page G 12 APPENDIX G: COLD SHUTDOWN TBSTING JUSTIFICATION NUMBER: CS,I 12 COMPONENTS: 1-C V C 184 2-CVC-184 Regenerative IIcat Exchanger Charging inlet Cheek Valves SAFETY FUNCTION: Open to provide nowpaths to the reactor coolant system and pressurizer auxiliary spray line for core Hush. Close for containment isolation. - BASIS: These are simple check valves with no extemal means of exercising or position indication. They are stroked open during r,ormal charging pump opemtion and during quarterly testing of the charging pumps. The pump testing opens 1/2 CVC 184 adequately to pass the flow required by the applicable accident analyses for reactor coolant makeup; however, this is considered to be a part stroke test since the Downte is less than that required for core Dush. The Howrate required for core flush cannot be charged to the RCS during normal opention as it would require abnormal system line ups and likely result in undesirable pressurizer level transients. Verifying closure of these valves requires a shutdown of the charging pumps which would lead to an unacceptable pressurizer level tmnsient and plant shutdown. This also would place excessive thermal cycles on system equipment due to starting and stopping charging and letdown now. This is consistent with the position stated in NUREG 1482, Paragmph 2.4.5, Additionally, entry into this area during plaat operation would result in significant personnel radiation exposure.
Page G 13 APPENDIX G: COLD SilUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 13 COMPONENTS: 1 C VC-185 2 C VC-185 Auxillary Preosurizer Spray Check Valves SAFETY FUNCTION: These normally-closed valves open when initiating auxiliary pressurizer spray. In the event of a cold leg break, uie safety i injection pumps can inject into the pressurizer via this line for core flush. . ! BASIS: These are simple check valves with no extemal means of exercising or position indication. Exerrising these valves to the open position l would require initiation of auxiliary pressurizer spray flow and injection of cold water into the pressurizer spray nozzle placing significant thennal stress on the spray line and spray nozzle as well as unnecessarily consuming the limited number of thennal cycles allowed for the pressurizer nozzles. Such an evolution could also result in an undesirable reactor pressure transient and the potential plant shutdown or trip. Since they cannot be stroked open during operation, it is also not possible to stroke or otherwise verify closure of these valves. Partial stroking of these valves presents the same risks and problems that are associated with full stroking, thus it is also not feasible during opemtion. Due to the system configuration, insufficient instrumentation exists to verify either check valve's closure upon cessation of flow. During cold shutdown periods, the valves can be instrumented to pennit non-intrusive verification of their closure; however, due to their location in the containment and equipment limitations, these valves cannot remain instrumented during nonnal operations. Additionally, instrumenting them each quarter during nonnal operation is impractical due to the excessive personnel mdiation exposure which would be experienced. This is consistent with the position stated in NUREG 1482, Paragraphs 2.4.5 and 3.1.1.
Page G 14 APPENDlX G: COLD Si!UTDOWN TESTING JUSTIFICATION NUh1BER' CSJ 14 COhfPONENTS: 1-CVC-186 and 1 CVC-187 2 CVC 186 and 2 CVC 187 Charging Check Valves I SAFETY FUNCTION: Open to provide flowpaths from the charging header to the reactor coolant system. . IIASIS: These are simple check valves with no external means ofexercising or position indication. They are stroked open during quarterly testing of 1/2 CVC-518 CV and 1/2 CVC-519 CV, as well as the charging pumps. When 1/2-CVC 519 CV is closed, iaw can pass through either 1/2 CVC 186 (which is in series with 1/2 CVC-518-CV) or bypass around the closed 1/2 CVC 519 CV through 1/2 CVC-435 and then l pass through 1/2 CVC-187 (which is in series with 1/2 CVC-519 CV and 1/2-CVC-435). Therefore, it is assumed tha; 1/2 CVC 186 (and 1/2 CVC-435) are only part stroked during qut terly testing. When 1/2 CVC-518 CV is closed, flow must pass through 1/2-CVC-187 (which is in series with 1/2 CVC 519 CV and 1/2 CVC-435) although it is assumed to split equally between parallel valves 1/2 CVC-519-CV and 1/2-CVC 435. Therefore,1/2 CVC-187is full stroked during quarterly testing (since there is no comparable bypass flowpath around 1/2-CVC-518-CV). Due to the system conf:guration, insuflicient instmmentation exists to verify either check valve's closure upon cessation of flow. During cold shutdown periods, the valves can be instrumented to permit non-intmsive verification of their closure, however, due to their location in the containment and equipment limitations, these valves cannot remain inwumented during nornni operations. Additionally, instrumenting them each quarter during normal operation is impractical due to the excessive personnel radiation exposure which would be experienced. This is consistent with the position stated in NUREG-1482, Paragraphs 2.4.5 and 3.1.1.
l Page G 15 , APPENDIX G: COLD JHUTDOWN TESTING )USTIFICATION 1 NUMBER: CSJ-15 COMPONENTS: 1-CVC-435 2 C VC-435 Charging Control Valve Bypass Check Valves
- SAFETY FUNCTION: Protect the charging headers and regenerative heat exchangers in the event that charging now is secured while letdown is continued.
Closed for containment isolation. BASIS: These are simple spring loaded check valves with no external means ! of exercising or position indication. Exercising them would require l shutdown of the normal charging lineup which would result in severe - pressurizer level tunsients and plant shutdown. Due to system l configuration, insufficient instrumentation exists to verify if a valve opens during quarterly stroke testing of 1/2-CVC 519-CV or > quarterly charging pump testing. During cold shutdown periods, the valves may be instrumented to pennit non-intrusive verification of their closure; however, due to their location in the containment and equipment limitations, these valves cannot remain instrumented during normal operations, and instrumenting them each quarter during normal operation is impractical due to the excessive personnel radiation exposure which would be required. Additionally, lining up the CVCS system to ensure this valve is opened during normal operation would require securing all other charging flowpaths - not considered prudent action during normal plant operation. Due to the system configuration, insufficient instrumentation exists to verify either check valve's closure upon cessation of flow. During cold shutdown periods, the valves can be instrumented to permit non-intrusive verification ef their closure; however, due to their location in the containment and equipment limitations, these valves cannot remain instrumented during normal operations.- Additionally, instrumenting them each quarter during nonnal operation is impractical due to the excessive personnel radiation exposure which would be experienced. This is consistent with the position stated in NUREG-1482, Paragraphs 2.4.5 and 3.1.1.
Page G 16 APPENDIX G: COLD SIIUTDOWN TESTING JUSTIFICATION NUhfBER: CSJ 16 COhfPONENTS: 1 CVC-505-CV and 1 CVC-506-CV 2-CVC-505-CV and 2-CVC-506-CV RCP Seal Bleed-off Containment Isolation Valves L SAFETY FUNCTION: Close on SIAS signal to provide containment isolation. BASIS: Exercising these valves to the closed position when the reactor coolant pumps (RCP.'s) are in operation would interrupt flow from the RCP seals and can result in damage to the pumps' seals. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. Note that these valves are not within the AShiFJISI class boundaries. - NUhfBER: CSJ-17 COhfPONENTS: 1 CVC-515-CV and 1 CVC 516-CV 2 CVC-515-CV and 2-CVC-516-CV Letdown Stop Valves SAFETY FUNCTION: Close on SIAS and CVCS isolation signals to secure letdown flow from the RCS and in the event of a letdown piping ruptare. During plant cooldown they may be required to be closed to pirvent voiding in the steam generators. They close for containment isolation. BASIS: Closing either of these valves during operation would result in severe pressurizer level or CVCS system transients with the potential for a plant trip. In' addition, such an operation would cause unnecessary thermal cycles on the Regenerative Heat Exchanger and, in general, is not a prudent action in the context of plant operation. If either valve failed to re-open, an expedited plant shutdown would te required. Partial closure of these valves presents the same risks and problems that are associated with full closure, thus it is also not feasible during operation. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5.
Page G 17 l APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-18 COMPONENTS: 1.CVC-517-CV l 2-CVC-517-CV Auxiliary Pressuriser Spray Line Stop Valves SAFETY FUNCTION: Open to pmvide nowpaths to de-pressurize and cool the pressurizer wher the RCP's are not in operation. Although there are alternate methods of reduclag RCS pressure during an accident, the pathways including these valves is the preferred method. In the event of a cold leg break, these valves are required to open to provide flowpaths from the safety injection pumps inte $e pressurizer for core Dush. They also close for containment isoladon. - BASIS: Opening these valves would result in initiation of auxiliary preGurirer spray now and injection of cold water into the pressurizer spray nozzle placing signincant thermal stress on the spray line and spray nozzle, as well as unnecessarily consuming the limited number of thermal cycles allowed for the pressurizer nozzles. Such an evolution could result in an unacceptable reactor pressurizer transient and a potential plant shutdown or trip. Partial stroking of these valves presents the same risks and problems that are associated with full stroking; thus, it is also not feasible during operation. This is consistent with the position stated ir, NUREG 1482, Paragraph 2.4.5.
Pag) G 18 APPENDIX 0: COLD SHUTDOWN TESTING JUS 11FICATION i NUMBER: CSJ 19 COMPONENTS: 1-CC-3832-CV and 1 CC-3833-CV I 2-CC-3832-CV and 2-CC-3833-CV l Component Cooling Containment Supply / Return Valves l SAFETY FUNCTION: Containment isolation valves, close on a CIS. On a rupture of the non-classed piping inside containment these valves are closed to provide Code Class boundary isolation. BASIS: Dene normally-open valves provide flowpaths for cooling water ' (nomial cooling) to and from to the control rod drive mechanisms, reactor coolant pumps, and the reactor and steam generator supports.
- Closing any of these valves during plant operation at power will interrupt cooling flow and cause overheating and damage to the associated components. Should any one of these valves fall to re-open after closure, an immediate plant shutdown or trip and cooldown would follow. Partial closure of these valves presents the same risk as full closure; thus it is also not feasible during operation, nis is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. Additionally, consistent with NUREG 1482, Paragraph 3.1.1.4, component cooling containment heat loads (such as the RCPs) will not necessarily be secured solely to test these control valves.
Page G 19 APPENDIX 0: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 20 COMPONENTS: 1 CPA 1410-CV,1.CPA 1411 CV,1 CPA-1412 CV and 1 CPA-1413-CV 2-CPA 1410-CV,2 CPA 1411 CV,2-CPA-1412-CV and 2-CPA 1413-CV Containment Bldg. Purge Supply / Exhaust isolation Valves SAFETY FUNCTION: Close for containment isolation. 1 BASIS: These valves are normally locked shut with power removed in Modes 1-4 per Technical Specification 3.6.1.7. They are only reyulred to stroke in Modes 5 and 6 in the event of a refueling accident. During all other modes of operation, they remain closed and are essenthily - passive. If containment purge is established during a cold shutdown period, then these valves will be stroke tested; however, they are not necessarily opened during each cold shutdown period. Note that, if they are not opened they remain in their safety position and are not required to be operable with respect to their automatic closure capability, it is undesirable to stroke these valves during each cold shutdown since excessive operation can damage the sealing surfaces of these valves and cause degradation of the valve's leak tight capability which would result in additional testing, maintenance, and cold shutdown extension. Therefore, these valves will be stroke tested during each refueling outage and during cold shutdown periods whenever containment purge is established. Partial closure of these valves presents the same risks and problems that are associated with full closurt; thus it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. (NOTE. Following completion of ESP 94 205 the outboard purge valves will be eliminated and the lines will be blanked in Modes 1-4 to provide containment integrity) Note that these valves are et within the ASMF11SI class boundaries.
Page G 20 APPENDIX G: COI.D SIIUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 21 COMPONENTS: 1 IIP-6903-MOV 2 IIP-6903-MOV liydrogen Purge Supply Isolation Valves SAFETY FUNCTION: Close for containment isolation. BASIS: These normally-closed valves are required to remain closed during power operation per Calvert Cliffs Technical Specifications. If a valve were to fall in the open position during testing, then primary containment integrity would depend on a single check valve (1/2 IIP-104) inside containment whose position cannot be verified. In this - case, a plant shutdown would likely be required. This is consistent with the position stated in NUREG 1482, Paragraph 3.1.l(2). Note that these valves are agl within the ASMFJISI class boundaries. NUMBER: CSJ 22 COMPONENTS: 1 FW-130 and 1-FW 133 2-15V-130 and 2-FW 133 Steam Generator Feedwater Supply Check Valves SAFITIY FUNCTION: These normally-open check valves provide flowpaths for nonnal feedwater flow to the steam generators. They close to isolate the j steam generators and the non-Code portions of the main feedwater system to prevent back leakage of steam generator inventory into the main feedwater system when the main feedwater pumps trip on a ESFAS signal and the feedwater headers de pressurize. BASIS: Exercising these valves to the closed position requires securing feedwater flow to the associated steam generator. During nonnal plant operation at power, this would result in a severe plant transient and trip. Partial closure of these valves presents the same risks and problems that are associated with full closure; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G 21 APPENDIX 0: COLD SHUTDOWN TESTING JUST1FICATION NUMBER: CSJ 23 l COMPONENTS: 1 FW-4516 MOV and 1 FW 4517 MOV 2 FW-4516 MOV and 2-FW-4517 MOV Steam Generator Foodwater Supply isolation Valves SAFETY FUNCTION: nese normally-open valves provide flowpaths for normal feedwater flow to the steam generators. Dey close on SGIS to isolate the steam generators to mitigate the effects of a steamline break, to isolate the non Code. portions of the main feedwater system, and to
- prevent back leakage of steam generator inventory into the main feedwater system. In the event of a steam generator tube leak, they would be closed by the operator to prevent over feeding the affected -
steam generator. BASIS: Exercising (closing) these valves will result in securing hedwater flow to the associated steam generator. During normal plant operation at power, this would result in a severe plant transient and trip Partial closure of these valves will cause severe transients in steam generator water level with the potential for a plant trip. Partial closure of these valves presents the same risks and problems that are associated with full closure; thus, it is also not feasible during plant operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G 22 APPENDIX 0: COLD SIIUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-24 COMPONENTS: 1 IA-2085-CV 2 IA 2085-CY Containment Air Control Valves SAFETY FUNCTION: These nonnally-open valves close following a containment isolation signal when downstream line pressure drops to 75 psig. to extend the air supply to the containment air inlet valves and other critical containment air loads for as long as possible. This also ensures that it is safe to re+ pen 1/2-2080 MOV later in an accident scenario to allow opemtion of CVCS valves 1/2 CVC 517-CV,1/2 CVC-518-i CV, and 1/2 CVC-519 CV and the PASS isolation valves. BASIS: Closing these valves will isolate instmment air to the containment I and secure operating air to several components critical for plant operation including the pressurizer spray control valves. If the valve were to fall in the closed position, a plant shutdown would be requinxi. Partial closure of these valves presents the same risk as full closure; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5. Note that these valves are Del within the ASME/ISI c!ns boundaries.
Page G 23 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-25 COMPONENTS: 1 IA 2080-MOV 2-IA 2080-MOV Containment Air Supply Valves SAFETY FUNCTION: These are containment isolation valves that auto-close on CIS. In the course of an accident it may be required to operate CVCS valves CVC 517 CV, CVC-518 CV, and CVC-519 CV for core flush or makeup and valves in the PASS system, thus re-opening these valves would also be required, Note that these valves are not within the ASMPJISI class boundaries. BASIS: Closing these valves isolates operating air to several components 1 critical for plant operation including the pressurizer spray control l valves. Closing these valves will isolate instrument air to the containment, If the valve were to fall in the closed position, a plant shutdown would be mquired, Partial closum of these valves presents the same risk as full closure; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Pamgraph 2,4,5. M t i e 1
- *-r ----.% ,p_- - , - - - - - - - + --
q+y-y -+ry,.- ----
Page 0 24 APPENDIX G: COLD SIIUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 26 COMPONENTS: 1 hts-4043-CV and 1 hts-4048 CV 2-hts-4043 CV and 2-hts-4048 CV Main Stearn Isolation Valves (MSIV's) l SAFETY FUNCTION: These valves close on CSAS and SGIS to prevent the unrestricted release of steam from multiple steam generators in the event of an upstream steamline rupture and to isolate the steam generators in the event of a LOCA, steam generator tube rupture, or downstream steamline rupture. When closed, they provide isolation of the l unaffected steam generator thus ensuring an adequate supply of steam for AFW pump turbine operation. These valves are also required to
- be tested per Technical Specifications Para. 4.7.1.5 (ITS 3.7.2.1).
BASIS: During plant operation at power, full closure of any of these valves would result in a major plant transient and a turbine and reactor plant trip. These valves are provided with the capability of partial stroke (closure) exercising which can be performed at power without jeopardizing plant operation. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5.
Page G 25 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 27 COMPONENTS: 1 MS 103 and 1 MS 106 2 MS 103 and 2-MS-106 Main Steam Header to AFW Pump Turbines Check Valves SAFETY FUNCTION: nese valves open on initiation of steam now to the AFW Purnps to l provide Dowpaths from the steam generators to the AFW pump steam turbines. Dey close to prevent backDow between the steam generators in the case of a main steamline break. BASIS: These are simple check valves with no extemal means of exercising; thus, the only practical means of opening these valves is to operate each steam-driven AFW pump discharging to the steam generators. Full stmke exercising of these valves requires operating each steam- , driven AFW pump at full accident How thus requiring maximum l steam now to the turbine. During plant operation at power, this is not practical due to the potential for thennal shock of the steam generater nozzles and internals. During quarterly testing of the AFW pumps, now is routed through a minimum now recirculation line; thus, partial now exercising only is practical. The test for verifying closure is extremel; cumbersome and requires extensive system realignment and resvrces and an extended period during which the associated AFW pump is out of service. Thus, it also is not practical during plant operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. Alternatively, these check valves may be non intrusively monitored during full Dow testing of the AFW pumps when such testing is performed during a cold shutdown period. However, due to their service conditions, these check valves can not remain instrumented during nonnal openition. Instrumenting them each quaner would present personnel hazards due to their location and service conditions (additionally, it is unlikely they could be instrumented during every cold shutdown), and it is not likely the steam flow through these check valves resulting from AFW pump minimum now testing is sufficient to full stroke these check valves.
Page G 26 APPENDIX G: COLD SEIUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 28 COMPONENTS: 1 MS 108 and 1 MS-110 2415108 and 2 MS 110 Main Steam Hender to AFW Pump Turbines Check Valves i SAFETY FUNCTION: These valves open on initiation of steam now to the AFW Pumps to pmvide nowpaths from the steam generatora to the AFW pump steam turbines. - BASIS: These are simple check valves with no external means of exercising; thus, the only practical means of opening these valves is to operate each steam driven AFW pump discharging to the steam generators. Full stmke exercising of these valves requires operating each steam-l driven AFW pump at full accident flow thus requiring maximum i steam flow to the turbine, During plant ope ation at power, this is not practical due to the potential for thermal shock of the steam generator non.les and intemals. During quarterly testing of the AFW pumps, flow is routed thmugh a minimum flow recirculation line; thus, partial flow exercising only is practical. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. [
1 Page G 37 l l APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ.29 COMPONENTS: 0 Nr344 0-Nr347 Nitrogen Supply To Safety Irdection Tanks Outboard Check Valves - SAFETY FUNCTION: Close for containment isolation. BASIS: nese are simple check valves with no external means of exercising or position Indication; thus, verifying the ability of these check valves to close requires containment access to exercise them open, followed by a back leakage test. Such access is not practical on a routine basis during plant operation at power. Dese check valves are normally closed and only need to perform their active closure function in the event an accident occurred during nitrogen addition to the SITS. This is a relatively infrequent operation and one of shet duration. Additionally, these check valves are in series with 1/241-491,1/2 SI-492,1/2-SI-493, & 1/2 SI-494. This position is consistent with that set forth in NUREG 1482, Paragraph 2.4.5. Note that these valves are not within the ASME/ISI class boundaries.
Page G 28 APPENDIX G: COLD SHUTDOWN TES'I1NG JUSTIFICATION NUMBER: CSJ 30 COMPONENTS: 1 RC-105-SV and 1-RC 106-SV 2-RC 105-SV and 2 RC-106 SV Pressuriser Vent Valves SAFETY FUNCTION: These valves are opened as needed to vent non-condensable gases trapped in the pressurizer during natural recirculation to enhance core cooling. If opened during accident recovery, they will require re-closing in order to conserve reactor coolant inventory. Testing is required per Technical Specification 4.4.13.1 (ITS Technical Requirements Manual). 4 BASIS: 'these valves are administatively contmiled in the closed position to prevent inadvertent operation. Since these are Class I reactor coolant system isolation valves, failure of a valve to close or leakage following closure could result in a loss of coolant in excess of the , limits imposed by the Plant Technical Specifications necessitating a l plant shutdown. Furthennore, failure of the valve to indicate a return to the fu'ily closed position following exercising could likely result in a containment entry at power or a plant shutdown. Partial-stroke exercising of these valves presents the same risks and problems that are associated with full stmke exercising; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5. _=-
= = =
l
Page G 29 APPENDIX G: COLD SIIUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 31 COMPONENTS: 1 RC-100F-CV,1 RC-100F CV
)
2 RC-100E CV,2 RC-100F CV Preuurirer Spray Valves l SAFRTY FUNCTION: 'Ihese valves close to prevent diversion of flow to the reactor coolant cold legs when the auxiliary pres turizer spray lines are used for core ! Dush. - BASIS: Due to dynamic flow conditions in the reactor coolant system under normal steaming conditions repeatable full stroke test results for these valves are not possible; thus, these valves can only be tested during cold shutdown periods when stable test conditions can be established. (These conditions include securing RCP's and depressuriring the RCS, both of which minimize variations in now through, and differential pressure across, these valves which could affect their perfonnance.) Additionally, full stroking these valves while the plant is pressurized will cause sign 10 cant and unacceptable reactor coolant system pressure transients. These valves ait part-stroked on an on going basis in order to maintain pressure control while the plant is pressurized. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
1 Page G 30 APPENDIX 0: COLD SIlUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 32 COMPONENTS: 1 RC 103-SV and 1 RC-104-SV 2 RC-103-SV and 2 RC-104-SV Reactor Vessel Vent Valvew SAFETY FUNCTION: These valves are oper,ed as needed to vent non-condensable gases i trapped in the reac9r vessel head during natural recirculation to - enhance core cooling. If opened during accident recovery, they will , require re-closing in. order to conserve reactor coolant inventory. Testing is required per Technical Specification 4.4.13.l(ITS l Technical Requirements Manual). BASIS: These valves are administratively controlled in the closed position to 4 prevent inadvertent operation. Since these are Class I reactor coolant system isolation valves, failure of a valve to close or leakage following closure could result in a loss of coolant in excess of the limits imposed by the Plant Technical Spectrications necessitating a plant shutdown. Furthermore, failure of the valve to indicate a return to the fully closed position following exercising could likely result in a containment entry at power or a plant shutdown. Partial-stroke exercising of these valves presents the same risks and problems that are associated with full stmke exercising, thus it k also not feasible during operation. This is consistent vith the psition stated in NUREG-1482, Paragraph 2.4.5.
Page G 31 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-33 { COMPONENTS: 1-RC-402-ERV and 1 RC-404 ERY l 2-RC-402-ERV snd 2-RC-404 ERV Power-Operated Relief Valves SAFETY FUNCTION: These valves provide overpressure protection for the reactor coolant system without lifting a pressurizer safety (these are redundant to the pressurizer safetyvalves and are not credited in the FSAR, although Technical Specifications allow crediting a PORV for a limited time if the pressurizer vapor vent path is inoperable). Aho, they protect the reactor coolaint system from over-pressurization when the reactor coolant system is cooled down to less than MPT (LTOP). BASIS: Either full- or part-stroking of these valves during power opemtion - can cause significant and unacceptable reactor coolant pressure transients. Additionally, such stroking could also result in the failure t of one of these valves to rese** properly which would lead to system / equipment damage, i Y;ced plant reliability, and a possible plant shutdown. This is consistent with the position stated in NUREG 1482, Paragmph 2.4.5.
Page G 32 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 34 COMPONENTS. 1-SI 113,1 SI 123,1 SI-133, and 1 SI 143 2-SI 113,2-SI 123,2 S1133, and 2-SI-143 IIPSIIleader holation Check Valves SAFETY FUNCTION: These check valves open to pmvide flowpaths for HPSI into the reactor coolant system, ney close to prevent diversion of I. PSI into the HPSI headers'and can serve as an optional reacter coolant pressure isolation valve. ' ~ l BASIS: These t.re simple check valves with no means of external position l Indication or operation. In order to open these valves, the HPSI - i pumps must be operated with injection into the reactor coolant system. This cannot be performed during plant operation at power because normal RCS pressure is above the shut-off head of the HPSI pumps. RCS pressure cannot be lowered sufficiently to permit full-stroke testing these valves unless the plant is shut down. These valves are part stroked exercised open quarterly and whenever the associated HPSI pump is operated to fill the safety injection tanks. His is consistent with the position stated in NUREG 1482, Paragraph 2' .4.5.
Page G 33 APPENDIX 0: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 35 COMPONENTS: 1 SI-401 and 1-SI-410 2-SI 401 and 2-SI-410 ; HPSI Pump Suction Check Valves l SAFETY FUNCTION: These check valves open to pmvide flowpaths for water from the RWTs or containment sumps to the HPSI pumps during SIAS or
- RAS, '
L BASIS: These are simple check valves with no means of extemal position indication or operation. In order to open these valves, the HPSI pumpt must be operated with injection into the reactor coolant system, nis cannot be perfonned during plant operation at power because nonnal RCS pressure is above the shut-off head of the HPSI pumps RCS pressure cannot be lowered sufficiently to permit full-stroke testing these valves unless the plant is shut down. These valves are pan stroked exercised quanerly. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5. NUMBER: . CSJ COMPONENTS: 1-SI-405,1 SI-414, and 1 SI-427 2-SI 405,2-SI-414, and 2-SI-427 IIPSI Pump Discharge Check Valves SAFETY FUNCTION: nese check valves open to provide flowpaths for water from the HPS1 pumps to the HPSI discharge headers during SIAS or RAS. BASIS: nese are dmple check valves with no means of external position indication or operation. 'In order to open these valves the HPSI pumps must be operated with injection into the reactor coolant system. This cannot be performed during plant operation at power because nonnal RCS pressure is above the shut-off head of the HPSI pumps RCS pressure cannot be lowered sufficiently to permit full-stroke testing these valves unless the plant is shut down. These valves are pan stroked exercised quanerly, nis is consistent with the position stated in NUREG 1482, Paragraph 2.4.5.
Page G-34 APPENDIX G: COLD SilUTDOWN TESTING JUSTIFICATION NUMBER: CSJ 37 COMPONENTS: 1 SI-434 and 1 SI-446 ' 2 SI-434 and 2 SI-446 LPSI Pump Discharge Check Valves SAFITI'Y FUNCTION: Dese valves open to provide flowpaths fmm the LPSI pumps to the low pressure injection header. They close to prevent recirculation flow through an idle pump and minimum flow line that could adversely impact the. effectiveness of the operating pump. BASIS: These att simple check valves with no external means of exercising, thus exercising (open) requires operating a LPSI pump at full now and injecting into the scactor coolant system. At power operation, this is not possible because the LPSI pumps cannot develop sufficient discharge pressure to overcome scactor coolant ::ystem pressure. l These valves are part stroked exercised quarterly. This is consistent l with the position stated in NUREG-1482, Paragraph 2.4.5. NUMBER: CSJ-38 COMPONENTS: 1-SI-659-h!OV and 1 SI 660-h10V 2-SI-659-h10V and 2-SI 660 h10V SI Pump hiint Flow Reture To RWT Isolation Valves SAFETY FUNCTION: These valves provide Dowpaths for minimum flow protection. When power is restored, these valves close on a RAS to block recirculation flow from returning to the RWT. BASIS: Closure of either of these valves isolates the minimum recirculation Dowpath for all the ECCS pumps from both trains causing all safety injection and containment spray pumps to be inoperable. Failure of either of these valves in the closed position during testing will prohibit flow through the minimum now recirculation lines for all of the safety injection and containment spray pumps. Due to the probability of dams.ge should these pumps be started and operated in this condition (no Dow), exercising of these valves should only be performed during cold shutdown periods when these purups are not requinxi to be operable. Panial closure of these valves presents the same risks and problems that are associated with full closure; thus, it is also not feasible during operation. This position is consistent with that of NUREG 1482, Paragraph 3.1.1 (1).
Page G 35 i APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION I NUMBER: CSJ 39 COMPONENTS: 1 SI 114,1 SI 124,1-SI-134 and 1-SI-144 i 2 SI 114, 2 SI 124,2-SI 134 and 2-SI-144 LPSIIIeader Isolation Check Valm SAFETY FUNCTION: nese normally-closed check valves open to provide Dowpaths for borated water fmm the LPSI pumps to each of the RCS cold legs. ney close to isolate the LPSI system from the HPSI injection l headers to prevent diversion of HPSI flow to the low pressure rated ! LPSI piping and loss through the associated relief valve and can , serve as an optional reactor coolant pressure isolation valve. BASIS: These are simple check valves with no external means of exercising, thus exercising (open) requires operating a LPSI pump at full flow and injecting into the reactor coolant system. At power operation, this is not possible because the LPSI pumps cannot develop suf0clent discharge pressure to oveirome reactor coolant system pressure. These valves are part stroked exercised and verified closed quarterly. This is consistent with the position stated in NUREG 1482, Paragraph 2.4.5. NUMBER: CSJ-40 COMPONENTS: 1-SI 118,1-SI 128,1 SI-138 and 1-SI 148 2-SI-118, 2-SI-128, 2-SI-138 and 2-SI 148 Safety Indection IIeader Isolation Check Valves SAFETY FUNCTION: These valves pmvide Dowpaths for borated water from the HPSI and LPSI pumps to each of the RCS cold legs. They close to isolate the safety injection system from the reactor coolant system. They also serve as pressure isolation valves (PWs) during normal operation. BASIS: These are simple check valves with no external operator for exercising, thus exercising (open) requires operating a LPSI pump at full now and injecting into the reactor coolant system. At power operation this is not possible because the LPSI pumps cannot develop sufficient discharge pressure to overcome reactor coolant system pressure. These valves are part stroked exercised open whenever the - associated IIPSI pump is run to fill a safety injection tank and verified closed quarterly. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
I L . Page G-36 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICA'110N NUMBER: CSJ-41 , f- COMPONENTS: 1-SI-651-MOV,1-SI-652-MOV I 2-SI-651-MOV, 2-SI-652-MOV SDC Return Header Isolation Valves SAFETY FUNCTION: These normally-closed valves are opened to initiate shutdown cooling. BASIS: These are pressure isolation valves which isolate the high piessure RCS piping fmm the low pressure shutdown cooling piping. They are interlocked with RCS pressure and cannot be opened at power. Pa-Jal-stroke exercising of these valves presents the same pmblems that are associated with full-stroke exercising; thus, it is also not
' feasible during operation. This is consistent with the position stated in NUREG 1482, Pamgraph 2.4.5.
NUMBER: CSJ.42 COMPO?UINTS: 1-SI-491,1-SI-492,1-SI-493 and 1-SI-494 2-SI-491,2-SI-492,2-SI-493 and 2-SI-494 Safety Irdection Tank Nitrogen Inlet Check Valves SAFETY FUNCTION: - These valves close to ensure the integrity of the safety-related pressure boundary of the safety injection system. BASIS: These check valves are normally closed and only need to perform their active closure function in the event an accident requiring the SITS is initiated while uitmgen pressure to one of the SITS b being increased. (Additionally, these check valves are in series with 0-N2-344 & 0-N2-347.) Since this is a relatively infrequent and short duration evolution affecting only one SIT at a' time, testing these check valves quarterly would significantly increase the time during which the plant is dependent upon their active closure function. Such a test would also increase the time 6: ring which the administratively controlled upstream containment isolation control valves (1/2-CV-612, 622, 632, & 642) are open. Mc:e frequent testing would require increased personnel radiation exposure and present more frequent situations in which potential component failure or human error could affect the operability of a SIT and place the plant in a very short-duration action statement. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. p
~ -
Page G-37. APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-43 COMPONENTS: 1-SI-313,1-SI-323 2-SI-313, 2-SI-323 Containment Spray Pump Discharge Check Valves SAFETY FUNCTION: These valves open to provide flowpaths from the containment spray I pumps to the containment spray headers. BASIS: These are simple check valves with no means of external position indication or operation. In order to open these valves, the - containment spray pumps must be operated with injection into the containment spray headers. This is undesimble as it would result in spraying contaminated borated water into the containment resulting in equipment contamination and damage. The containment spray pump discharge bypass lines do not allow sufficient flow to full-stroke these valves during quanerly pump testing. These valves are part stroked quanerly. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. I f
Page G 38
' APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION-NUMBER: CSJ-44 COMPONENTS: 1-SW-5149-CV 2-SW-5149-CV -
Emergency Saltwater Discharge To Bay isolation Valve SAFETY FUNCTION: These normally-closed valves remain closed to isolate the 11 (21) , saltwater supply headers from the Emergency Overboard saltwater I discharge flowpaths to the bay in erder to ensure normal flow of saltwater is maintained to the com; onents and heat exchangers cooled by the 11 (21) saltwater trains. - Under Emergency Overboard operations, they are opened to provide proper overboard flowpaths. BASIS: Operation of these valves is tied to operation of the three valve pairs i CV5155 & CV5156, CV5165 & CV5166, and CV5177 & CV5178. The normal way to stroke CV5149 is to open one of these valve pairs using the appropriate hr.nn vitch. However, each of these valve pairs is operated from a single hanoswitch and preventing them from opening in order to operate CV5149 alone would require placing them in an abnormal configuration (e.g. securing air to their actuators or installing _- jumpers in the valves' control circuit). Opening of any of these valve pairs during plant operation at power is not acceptable (see CSJ-45). These valves also have a back-up nitrogen bottle available for - emergency operation. However, the size of this nitrogen bottle is such that there is only sufficient gas for approximately two valve strokes. This would necessitate replacing the bottle after each test, More importantly, the nitrogen bottle is not permanently tied to the valve a ctuator. Stroking these valves with nitrogen requires installation of an airjumper and pressure regulator. Installing the airjumper and replacing the nitrogen bottle quarterly increases the potential for damaging piping / tubing connections and is considered a hardship consistent with NUREG-1482 Section 3.1.1, s
Page G-39 j
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APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-45 l COMPONENTS: 1-SW-5155-CV and 1-SW-5156-CV 2-SW-5155-CV and 2-SW-5156-CV Service Water Heat Exchanger 11 (21) Emergency Overboard Bypass Valves 1 SW-5165-CV and 1-SW-5166-CV 2-SW-5165-CV and 2-SW-5166-CV Component Cooling Water Heat Exchanger 11 (21) Emergency Overboard Bypass Valves 1-SW-5177-CV and 1-SW-5178-CV 2-SW-5177-CV and 2-SW-5178-CV ECCS Pump Room Air Cooler 11 (21) Emergency Overboard Bypass Valves SAFETY FUNCTION: These normally-closed valves remain closed to isolate the 12 (22) saltwater discharge headers from the 11 (21) saltwater supply headers, at the Emergency Overboard discharge flowpath cross-connects between the Service Water Heat Exchangers, Component Cooling Heat Exchangers, and ECCS Pump Room Air Coolers, to ensure the normal cooling water flow is maintained to the components and heat exchangers cooled by the 11 (21) saltwater trains. They are opened when cooling is required in the emergency overboard lineup. BASIS: Each pair of valves is operated fmm a single handswitch and neither valve in each pair can be individually opened without placing the other valve in an abnormal configrration (e.g. securing air to the actuator or installing jumpers in a valve control circuit). Exercising any of these valve pairs daring plant operation at power would allow significant bypass flow between the headers at the respective heat exchanger or cooler. Depending on saltwater header pressure, hot discharge flow from the 12 (22) header could be introduced into the 11( 21) supply header, or supply flow from the 11 (21) header could bypass each respective heat exchanger or cooler and pass into the 12 (22) discharge header. In either case, flow between the saltwater headers would significantly degrade the heat removal capacity of the heat exchangers or coobrs supplied by the 11 (21) saltwater headers.
Page G-40 APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-45 (continued) BASIS: (continued) Additionally, while these valves are open, the two saltwater headers are not independent. As a result, both saltwater headers are considered inoperable and the plant is placed in a short-duration action statement. Should any valve pair fail to re-close after being opened, the saltwater system would no longer remain capable of performing its safety function in view of the associated single failure requirements, thereby necessitating a plant shutdown and cooldown. Partial opening of these valves presents the same risk as full opening, thus it is also not feasible during operation, This is consistent with the position stated in NUREG-1482, ! Paragmph 2.4.5. i 6.. -
Page G-41 APPENDIX G: COLD SliUTDOWN TESTING JUSTIFICATION l NUMBER: CSJ-46 COMPONENTS: 1-SRW-323,1-SRW-324,1 SRW-325 2-SRW-323, 2-SRW-324, 2-SRW-325 Service Water Return From Turbine Building Check Valves
- SAFETY FUNCTION: These normally-open valves pmvide flowpaths for nonnal cooling water return fmm non-essential components in the turbine building )
critical to the continued operation of the generating plant. They close to isolate the non-classed return piping fmm the essential load return piping during an accident when the turbine building head::ra am isolated. BASIS: Closing any of these valves during plant operation at power requires interrupting cooling flow fmm the turbine auxiliaries and associated components. This would ultimately result in a plant shutdown and overheating and damage to plant equipment, Partial closure of these valves presents the same risk as full closure; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5.
Page G-42 l APPENDIX G: COLD SHUTDOWN TESTING JUSTIFICATION NUMBER: CSJ-47 COMPONENTS: 1 -S RW- 1600-C V, 1-S RW- 1637-C V, 1-S RW- 1638-C V, j 1-SRW-1639-CV ' 2-SRW-1600-CV, 2-SRW-1637-CV, 2-SRW-1638-CV, 2-SRW-1639-CV Service Water Supply To Turbine Building SAFETY FUNCTION: These normally-open valves pmvide flowpaths for nonnal cooling water to non-essential components in the turbine building critical to the continued operation of the generating plant. They close on a SIAS to isolate non-essential heat loads and ensum adequate cooling water flow to critical heat loads. During an accident when the turbine building headers are isolated, these valves must close to isolate the non-classed piping from the critical loaa piping. BASIS: Closing any of these valves during plant operation at power will interrupt cooling flow to the turbine auxiliaries and associated components. This would ultimately result in a plant shutdown and overheating and damage to equipment. Partial closure of these valves presents the same risk as full closure; thus, it is also not feasible during operation. This is consistent with the position stated in NUREG-1482, Paragraph 2.4.5. Note that some of these valves are not within the ASME/ISI class boundaries.
Page H-1 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-1 COMPONENTS: 1-IIP-104 2-IIP-104 Ilydrogen Purge Supply Check Valves SAFETY FUNCTION: These valves close for containment isolation. BASIS: These am simple check valves with no external means of exercising or position indication; thus verifying the ability of these check valves to close requires cor.taihment access to exercise them open, followed by a back leakage test (which requires installation of a blank flange). This is not practical during normal operation and is also not considered practical during a cold shutdown period. This agrees with the NRC position per NUREG-1482, Paragraph 4.1.4, Note that these valves am n01 within the ASMF1ISI class f oundaries. l f
Page11-2 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-2 COMPONENTS: 1-IA-337 2-IA-175 Instrument Air Supply To Containment Isolation Check Valves SAFETY FUNCTION: These check valves close for containment isolation. They open if sufficient operating air is available and operation of selected air-operated control valves in containment is desired. ' BASIS: These are small spring loaded piston-type check valves with no external position indication or other means of easily verifying their position. Operation of numerous air-operated contml valves in containment l during normal operation, including quarterly surveillance testing of selected air-operated contml valves in containment, verifies the ability of these check valves to open on an ongoing basis. There are no means of verifying their ability to full-stroke closed other than by performing a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection mmoved through which air flow can be neasumd using a leak rate monitor after passing back through the check valve. However, this secures at least one, and sometimes the only, flowpath for safety-related air to the downstream air loads. Verifying closure of these valves requires containment access and a back-leakage test. Such access is not practical on a routine basis during plant operation at power. The coordination and resources needed to secure instrument air to the containment to permit testing during cold shutdown periods would be an unreasonable burden with no appreciable gain in plant safety. The number ofinstmment air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, mmoving, and relocating a flow instmment and leak rate monitor to test each check valve is considered impractical to perform during normal operation or during cold shutdown periods. This is consisterit with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are ini within the ASME/ISI class boundaries.
Page 11-3
- APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-3 COMPONENTS: 1-IA-650 2-IA-310 Normal Air Supply To Containment Air IIeader Check Valves SAFETY FUNCTION: These check valves close to isolate the non-safety related portion of the instrument air header from the safety related header supplying several important safety-related instrument air loads, including several in the containment.
BASIS: These are small spring-loaded piston type check valves with no external position indication or other means of easily verifying their position. Due to their size, design, and system configuration, they cannot be non intrusively monitored. There are no means of verifying their ability to full stroke closed other than by performing a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using a leak rate monitor after passing back through the check valve. Verifying closure of these valves requins isolation of the normal air supply to critical system components inside containment. Although there is a backup supply of air stored in the associated containment air receiver, failure to return the normal supply to service in a timely manner could result in equipment failure and plant shutdown. Also, the backup air supply is capable of providing air to only a limited number of critical loads. The number of instrument air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and relocating a flow instrument and leak rate monitor to test each check valve is considered impractical to perform during normal operation or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are not within the ASME/ISI class bouudaries.
Page H-4 APPFRDIX H: REFUELING TESTING JUSTIFICATIONS
- NUMBER: RFJ-4 COMPONENTS: 1-IA-721,1 IA-722
{ 2-IA-741, 2-IA-743 Saltwater Air Compressor (SWAC) Discharge Check Valves SAFETY FUNCTION: These valves open to provide pathways for instrument air from the SWACs to the various air loads. 'Ihey close in the event a SWAC falls to maintain supply train isolation. BASIS: These are small spring-loaded piston-type check valves with no external position indication or other means of easily verifying their position. Due to their size, design, and system conHgumtion, they cannot be non-intrusively monitored. There are no means of verifying their ability to full-stroke open other than passing the required air flow in the fonvard direction. This can only be achieved by either isolating the normal non-safety-related sources of air and operating the downstream air loads i simultaneously. However, operating all the downstream air loads simultaneously is not typically practical. Alternatively, the forward flowrate through each check valve may individually measured. In order to do this, the downstream side of each check valve must be isolated and a test connection removed through which a'r flow can be measured using a flow instrument after passing through the check
- valve. These check valves aie part-stroked open whenever the SWACs are opented.
There are no means of verifying their ability to full-stroke closed other than by performing a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using ~a - leak mte monitor after passing back through the check valve. The number of instrument air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and - relocating a flow instrument and leak rate monitor to test each check valve is considered impractical to perform during normal operation or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are nel within the ASME/ISI class boundaries.
Page 11-5 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-5 COMPONENTS: 1-IA-1333,1-IA 1338 2-IA-1101, 2-IA-1106 Normal (NSR) Instrument Air Supply Check Valves SAFETY FUNCTION: These valves close to isolate the NSR instmment air header and maintair. the integrity of the SWAC air supply system. BASIS: These are small spri.ig loaded piston-type check valves with no external position indiution or other means of easily verifying their position. Due to their size, design, and system configuration, they cannot be non-intrusively monitored. There are no means of verifying their ability to full stroke closed other than by perfonning a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using a leak rate monitor after passing back through the check valve. The number of instmment air valves, the complex system re-alignments, the necessity of removing and replacing numemus test connection caps, and the difficulty of installing, removing, and relocating a flow instmment and leak rate monitor to test each check valve is considered impractical to perfonn during normal opemtion or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are nat within the ASMFlISI class boundaries.
Page H-6 APPENIMX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-6 COMPONENTS: 1-IA-729,1-IA 732 2-IA-300, 2-IA-301 ! Instrument Air Supply To A7W Supply Valves Check Valves ) SAFETY FUNCTION: These valves open to provide air to AFW Steam Generator supply / control valves. They close to maintain supply tuin isolation to preclude blowdown of the associated AFW air accumulator. BASIS: These are small spring loaded piston-type check valves with no external position indication or other means of easily verifying their position. Due to their size, design, and system connguntion, they cannot be non-intmsively monitored. There are no means of verifying their ability to full-stroke open other than passing the required air flow in the forward direction. This can only be achieved by either isolating the normal non-safety-related sources of air and opemting the downstream air loads simultaneously. However, operating all the downstream air loads simultaneously is not typically practical. Alternatively, the fonvarti flowrate through each check valve may individually measured. In I order to do this, the downstream side of each check valve must be isolated and a test connection removed thmugh which air flow can be measured using a flow instmment after passing through the check valve. There are no means of verifying their ability to full-stmke closed other than by perfonning a back seat leakage test. In order to do this, the upstream w' of each check valve must be isolated and a test connection removed through which air now can be measured using a leak rate monitor after passing back through the check valve. Testing these valves requires significant re-alignment of the air supplies to the AFW flow control valves, including securing the safety-related air supply to each set of AFW Blocking valvcs and Flow Control valves (one set at a time). The air headers / safety-related accumulators are configured such that one of the two AFW Blocking valves in each AFW Flow Leg is supplied by independent air headers / accumulators. As a result, isolating one safety-related air accumulator isolates air to one AFW Blocking valve in each AFW Flow Leg. Sirice the AFW Blocking valves fail open, this would result in limited capacity of the AFW supply system to respond to an
Page H-7 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-6 (continu:d) BASIS: (continued) ASPAS in the event steam generator isolation should be mquired. Therefore, all AFW Flow legs would be rendered inoperable. The number of instmment air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and relocating a flow instrument and leak rate monitor to test each check valve is considered iinpractical to perform every outage during normal operation or during cold shutdown periods. This is consistent with NUREG 1482 Sections 3,1.1 and 4.1.4. Note that these check valves are not within the ASMFlISI class boundaries.
Page H 8 APPENDIX H: REFUELING TESTING JUSTIFICATIONS 1 NUMBER: RFJ 7 1 COMPONENTS: 1 IA-730 2 IA-315A Instrument Air Supply to AFW Check Valves SAFETY FUNCTION: 'Ihese valves clese to isolate the normal (NSR) instmment air header from the safety-related header in order to permit supplying SWAC air to the AFW portion of the IA System if desired.- BASIS: These are small spring-loaded piston-type check valves with no 4 external position indication or other means of easily verifying their position, Due to their size, design, and system configuation, they cannot be non-intrusively monitored. Them are no means of verifying their ability to full-stroke closed i other than by perfonning a back seat leakage test,1st order to do this, the upstream side of ea:h check valve mest be isclated and a test connection removed thmugh which air flow can be measured using a
- leak rate monitor after passing back through the check valve. -
The number of instrument air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and relocating a flow instrument and leak rate monitor to test each check valve is considered impractical to perform every outage during normal operation or during cold shutdown periods, This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4, Note that these check valves are DDI within the ASME/ISI class boundaries.
Page H-9 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-8 COMPONENTS: 1-IA-736,1-IA-73N 2-IA-304, 2-IA-305 Instrument hir Supply to AFW System Wlve Accumulators Check Valves SAFETY FUNCTION: These valves close to isolate the nonnal (NSF.) instmment air header from the safety-related header to maintam supply train isolation and preclude blowdown of the associated AFW air accumulator. BASIS: These are small spring-loaded piston-type check valves with no external position indication or other means of easily verifying their position. Due to their size, design, and system configuration, they cannot be non-intmsively monitored. There are no means of verifying their ability to full-stroke closed other than by performing a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using a i leak rate monitor after passing back through the check valve. The number of instrument air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and f relocating a flow instrument and leak rate monitor to test each check valve is considered impractical to perform every outage during normal operation or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are nol within the ASME/ISI class boundaries.
Page 11-10 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-9 COMPONENTS: 1-IA 1432,1-IA-1448 2-IA-1213, 2-IA4228 Instrument Air Supply to 4070A/4071A Air Accumulators Check Valves i ' SAFETY FUNCTION: These check valve close to isolate the normal (NSR) instmment air header from the safety-related air header to maintain supply train isolation and preclude blowdown of the associated AFW air accumulator. They also close in the event SWAC air is aligned to the AFW pottic.n of the IA System. BASIS: These are small spring loaded piston type check valves with no external position indication or other means of easily verifying their position. Due to their size, design, and system configuration, they cannot be non intmsively monitored. There are no means of verifying their ability to full-stmke closed other than by performing a back seat leakage test. In order to do thi:;, the upstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using a leak rate monitor after passing back through the check valve, The number of instrument air valves, the complex system m-alignments, the necessity of removing and replacing numerous test connection caps, and the difficuhy of installin: emoving, and relocating a flow instrument and leak rate monitor to test each check valve is considered impractical to perform every outage during nonnal operation or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are not within the ASME/ISI class boundaries. i
Page1111 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ.10 COMPONENTS: 1-IA-1444,1-IA-1460 2-IA 1203,2-IA-1220 Instrument Air Supply to Steam Supply Valve Check Valves SAFETY FUNCTION: These check valve c!c >; to isolate the normal (NSR) instmment air header fmm the safett vlated air header to maintain supply train isolation and preclude inwdown of the associated AFW air accumulator. They also t r .n in the event SWAC air is aligned to the AFW portion of the IA* System. BASIS: These are small spring-Iceled piston-type check valves with no external position indication or other means of easily verifying their position, Due to their size, design, and system configuration, they cannot be non intmsively monitored. There ate no means of verifying their ability to full-stroke open other t than passing the required air now in the fonvard direction. This can only be achieved by either isolating the nonnal non-safety-related sources of air and operating the downstream air loads simultaneously. However, operating all the downstream air loads simultaneously is not typically practical. Alternatively, the forward nowrate through each check valve may individually measured. In order to do this, the downstream side of each check valve must be isolated and a test connection removed through which air flow can be measured using a How instrument after passing through the check valve. There are no means of verifying tl.eir ability to full-stroke closed other than by performing a back seat leakage test. In order to do this, the upstream side of each check valve must be isolated and a test connection removed through which air now can be measured using a leak rate monitor after passing back through the check valve. The number of instrument air valves, the complex system re-alignments, the necessity of removing and replacing numerous test connection caps, and the difficulty of installing, removing, and relocating a now instrument and leak rate monitor to test each check valve is considered impractical to perform every outage during nonnal operation or during cold shutdown periods. This is consistent with NUREG-1482 Sections 3.1.1 and 4.1.4. Note that these check valves are nR1 within the ASME/ISI class boundaries.
1 Page H-12 APPENDIX II: REFUELING TESTING JUSTIFICATIONS NUMBER: RFJ-11 COMPONENTS: 1 Al-DSA-38 and 1A2-DSA-46 , 1A2-DSA 38 and 1A2-DSA-46 1A1/1A2 Emergency Diesel Generator Starting Air Receiver Check Valves SAFETY FUNCTION: These valves close to isolate the non-safety grade air supply piping when the ED air compressors are not operating, BASIS: These are simple che'ck valves with no external means of exercising or position indication; thus verifying closure of these valves requires a back-leakage test. Due to the system configuration and the lack of vent valves, performing such a test requires realignment of the starting air receivers and bleeding down of one receiver, This would result in the plant entering a LCO condition for an extended period of time (probably in excess of 3-4 hours). In consideration of the staff support and time elements of this test, testing quarterly and at cold shutdown frequencies is impractical and would impose an excessive burden on the plant staff, Additionally, frequent de-pressurization and re-pressurization of these air receivers v'ould result in significantly increased nm-time on the associated air compressors and incirases the potential of contaminating the EDG Starting Air System, ,
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