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{{#Wiki_filter:Safety Analysis Ginna Station UFSAR Table 6.2-13 Changes Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 NSL-0000-SA024 Revision 1 October 3, 1990 Prepared by: | {{#Wiki_filter:Safety Analysis Ginna Station UFSAR Table 6.2-13 Changes Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 NSL-0000-SA024 Revision 1 October 3, 1990 Prepared by: K) -z.-'9Q Nu lear Engineer Date Reviewed by: | ||
Letter from J.E.Maier, RG&E, to D.M.Crutchfield, NRC, | Nucle r Engine r Date Approved by: | ||
anag r, Nuclear S fety & Licensing Date Page i 90i0240i'i9 90iOi5 05000244 PDR ADOCK P PDC I | |||
Revision Status Sheet Latest Latest Latest Page Revision Page 'evision Page Revision 14h 37 15 38 16 39 17 40 18 41 19 42 20 0 43 21 44 7 22 45 8 23 46 9 24 47 | |||
,10 25 48 12 27 13 28 14 29 14a 30 14b 31 14c 32 14d 33 0 14e 34 14f 35 14g 36 Safety Analysis Revision NSL-0000-SA024 Page ii Date 1 | |||
10 3 90 | |||
Safet Anal sis Descri tion and f | |||
1.0 Sco e The purpose of this evaluation is to determine are any unreviewed safety questions related to updating if there UFSAR Table 6.2-13, Containment Piping Penetrations and Isolation Valves. This update is necessary to reflect information obtained during a detailed review of the containment isolation system and the result of the 1988 Inservice Test (IST) Program submittal to the NRC. | |||
2.0 References 2.1 Updated Final Safety Analysis Report, Revision 5. | |||
2.1.1 Section 6.2.4, Containment Isolation System. | |||
2.1.2 Table 6.2-13, Containment Piping Penetrations and Isolation Valves. | |||
2.2 R.E. Ginna Nuclear Power Plant Technical Specifications, dated April 12, 1990. | |||
2.2.1 | |||
~ ~ Section 3.6.3, Containment Isolation Valves. | |||
2.2.2 Table 3.6-1, Containment Isolation Valves. | |||
2.2.3 Section 3.8.1, Refueling. | |||
2.3 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC, | |||
==Subject:== | ==Subject:== | ||
SEP Topic VI-4, Containment Isolation Valves (Systems); | SEP Topic VI-4, Containment Isolation Valves (Systems); dated August 30, 1982. | ||
dated August 30, 1982.Letter from L.D.White, RG&E, to D.L.Ziemann, NRCg | 2.4 Letter from L.D. White, RG&E, to D.L. Ziemann, NRCg | ||
==Subject:== | ==Subject:== | ||
Discussion of Lessons Learned Short Term Requirements; dated November 19, 1979.2.5 | Discussion of Lessons Learned Short Term Requirements; dated November 19, 1979. | ||
2.5 Letter from L.D. White, RG&E, to B.H. Grier, NRC, | |||
==Subject:== | ==Subject:== | ||
IE Bulletins 79-06A and 79-06A Revision 1;dated June 22, 1979.Letter from L.D.White, RG&E, to D.L.Ziemann, NRC, | IE Bulletins 79-06A and 79-06A Revision 1; dated June 22, 1979. | ||
2.6 Letter from L.D. White, RG&E, to D.L. Ziemann, NRC, | |||
==Subject:== | ==Subject:== | ||
Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI Unit 2 Accident;dated October 17, 1979.2.7 Letter from D.M.Crutchfield, NRC, to J.E.Maier, NRC, | Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI Unit 2 Accident; dated October 17, 1979. | ||
2.7 Letter from D.M. Crutchfield, NRC, to J.E. Maier, NRC, | |||
==Subject:== | ==Subject:== | ||
Forwarding Final Evaluation Report of SEP Topic VI-4, Containment Isolation System for the Ginna Nuclear Power Plant;dated April 12, 1982.Safety Analysis NSL-0000-SA024 | Forwarding Final Evaluation Report of SEP Topic VI-4, Containment Isolation System for the Ginna Nuclear Power Plant; dated April 12, 1982. | ||
Safety Analysis Revision 0 Page 1 NSL-0000-SA024 | |||
2.8 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC, | |||
==Subject:== | ==Subject:== | ||
SEP Topic VI-4, Containment Isolation System;dated December 30, 1981.NUREG-0821, Integrated Plant Safety Assessment, Systematic Evaluation Program, R.E.Ginna Nuclear Power Plant;dated December 1982.RG&E Inter-Office Correspondence from G.J.Wrobel, to S.T.Adams, | SEP Topic VI-4, Containment Isolation System; dated December 30, 1981. | ||
2.9 NUREG-0821, Integrated Plant Safety Assessment, Systematic Evaluation Program, R.E. Ginna Nuclear Power Plant; dated December 1982. | |||
2.10 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams, | |||
==Subject:== | ==Subject:== | ||
Necessary Clarifications Associated With Technical Specification Table 3.6-1;dated July 2, 1990.RG&E Inter-Office Correspondence from G.J.Wrobel, to S.T.Adams, | Necessary Clarifications Associated With Technical Specification Table 3.6-1; dated July 2, 1990. | ||
2.11 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams, | |||
==Subject:== | ==Subject:== | ||
Containment Isolation Valves AOV 745 (Penetration 124a), MOV 749A (Penetration 127), and MOV 749B (Penetration 128);dated June 22, 1990.RG&E Inter-Office Correspondence from G.J.Wrobel, to S.T.Adams, | Containment Isolation Valves AOV 745 (Penetration 124a), MOV 749A (Penetration 127), and MOV 749B (Penetration 128); dated June 22, 1990. | ||
2.12 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams, | |||
==Subject:== | ==Subject:== | ||
Technical Specification Interpretation of Containment Isolation Valves MOVs 749 A/B;dated June 21, 1990.USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants;Revision 3, November 1978.Letter from D.D.Di?anni, USNRC, to R.W.Kober, RG&E, | Technical Specification Interpretation of Containment Isolation Valves MOVs 749 A/B; dated June 21, 1990. | ||
2.13 USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants; Revision 3, November 1978. | |||
2.14 Letter from D.D. Di?anni, USNRC, to R.W. Kober, RG&E, | |||
==Subject:== | ==Subject:== | ||
SEP Topic VI-4, NUREG-0821 Section 4.22.2, Containment Isolation Valves;dated January 30, 1987.NUREG-0800, Standard Review Plan, Section 6.2.4, Revision 2, July 1981.Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, | SEP Topic VI-4, NUREG-0821 Section 4.22.2, Containment Isolation Valves; dated January 30, 1987. | ||
2.15 NUREG-0800, Standard Review Plan, Section 6.2.4, Revision 2, July 1981. | |||
2.16 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC, | |||
==Subject:== | ==Subject:== | ||
Operability of AOV 745 and MOVs 749A/B;dated July 9, 1990.Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, | Operability of AOV 745 and MOVs 749A/B; dated July 9, 1990. | ||
2.17 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC, | |||
==Subject:== | ==Subject:== | ||
Modification of Containment Penetration | Modification of Containment Penetration $ 2; dated March 13, 1990. | ||
$2;dated March 13, 1990.Ginna Station Procedure 0-2.3.1A, Containment Closure Capability in Two Hours During RCS Reduced Inventory Operations, Revision 5, dated April 28, 1990.Ginna Station Quality Assurance Manual.Appendix B, Inservice Inspection Program For the 1990-1999 Interval, Revision 0, dated January 1, 1990.10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.Safety Analysis NSL-0000-SA024 | 2.18 Ginna Station Procedure 0-2.3.1A, Containment Closure Capability in Two Hours During RCS Reduced Inventory Operations, Revision 5, dated April 28, 1990. | ||
Instead, Attachment B provides a detailed listing of all changes made to the table.Attachment B is divided into four (4)sub tables. | 2.19 Ginna Station Quality Assurance Manual. | ||
The second table provides a listing of changes made to the format and overall structure of the UFSAR table.The third table lists the changes made to each individual penetration on the UFSAR table.The fourth table identifies all changes made to the UFSAR table notes.However, since many modifications were made to the UFSAR table, most notes have been renumbered and revised.Consequently, to eliminate confusion, a change associated with the notes column for a particular penetration is only identified in Table 3 if a note has been added or deleted.There is no change identified in Table 3 if a note number has | 2.19.1 Appendix B, Inservice Inspection Program For the 1990-1999 Interval, Revision 0, dated January 1, 1990. | ||
2.20 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. | |||
updates to better represent actual plant conditions, and updates for consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.Safety Analysis NSL-0000-SA024 | Safety Analysis Revision 0 Page 2 NSL-0000-SA024 Date 9 24 90 | ||
~~s~3.3.1 | |||
If this column was not modified, it would require most valves to list"0/C".The column now provides a clear listing of the valve positions prior to any operator action (i.e.,"immediate" post accident).3.3.1.2 The Notes column was changed to only supplement UFSAR Section 6.2.4.4.2 text.All duplications of information contained in the UFSAR text was removed from the Notes.The Notes column now only identify exceptions, references, etc., not contained in the UFSAR text.3.3.1.3 removed from the table since they do not provide any information relevant to the UFSAR Table.This information can be obtained from other sources including Appendix B of the Ginna Station Quality Assurance Manual.Consequently, the information contained in these columns remains in other RG&E controlled documents. | I4 II | ||
3.3.1.4 The Position Indication In Control Room column was modified to show the type of indication instead of"Yes/No".This is a significant enhancement since the table now identifies if there is a white status light or a red/green light associated with the valve on the Main Control Board, or both.3.3.2 | |||
$2 was added to the table.This spare penetration was modified during the 1990 Refueling Outage to enhance containment closure during mid-loop operations. | 3.0 Safet Anal sis 3~1 The system affected, by this UFSAR change is the containment isolation system. This system is designed to isolate non-essential process lines which penetrate the containment to ensure that the total leakage of activity will be within design limits in the event of an accident. In addition, the parent systems (e.g., | ||
The penetration meets all current containment penetration criteria.See Reference 2.17.Safety Analysis NSL-0000-SA024 | Safety Injection) of the components contained in the containment isolation system can be considered affected by this UFSAR change. However, there is no change to the capability of these systems to perform their intended design function, only an update of their ability to isolate containment when required. | ||
~~~~3.3.2.2 | 3.2 The updated UFSAR Table 6.2-13 is presented in Attachment A. Due to the significant number of changes, a marked-up version of the current UFSAR table was not generated. Instead, Attachment B provides a detailed listing of all changes made to the table. | ||
¹)in this category include: 370B (¹100), 879 (¹110b), 371 (¹112), 846 (¹120a), 539 (¹120b), 547 (¹121a), 528 (121a), 508 (¹121b), 743 (¹124a), 745 (¹124a), 1569 (¹124b)g 1571 (¹124b)g 1572 (¹124b)I 1574 (¹124b)I 759B (¹125)I 759A (¹126)I 749A (¹127)749B (¹128)I 1787 (¹129)I 1786 (¹129)/7971 (¹132), 1076B (¹202), 1084B (¹202)I 1563 (¹203b)I 1565 (¹203b)I 1566 (¹203b)~1568 (¹203b)I 5869 (¹204), 966C (¹205), 966B (¹206a), 5735 (¹206b), 966A (¹207a), 5736 (¹207b), 1080 (¹210), 5879 (¹300)g 6151 (¹301)g 6165 (¹301)~6175 (¹303)6152 (¹303)g 1 07 6A (¹304)I 1 084A (¹304)g 1554 (¹305c), 1556 (¹305c), 1557 (¹305c), 1559 (¹305c)f 1560 (¹305c), 1562 (¹305c), 7141 (¹310a), 921 (¹332c), 922 (¹332c), 923 (¹332c), and 924 (¹332c).Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a comparable position.That is, the valve position changed from either a"0" to"0/C" or"0/C" to"0".(See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.)For these cases where the valve was listed as open, the valve and penetration was required to be evaluated previously assuming that | Attachment B is divided into four (4) sub tables. | ||
Valves (and penetration | The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy. | ||
¹)in this category include: 1723 (¹107), 1728 (¹107), 313 (¹108), 1789 (¹123 bottom), 1003A (¹143), 1003B (¹1 43)g 5869 (¹204)g 5735 (¹206b)I 5736 (¹207B)5879 (¹300)~4629 (¹308)g 4630 (¹31 1)I 4642 (¹312)g 4643 (¹315)I 4628 (¹316)g 4627 (¹319)f 4641 (¹320), 4644 (¹323), and 8418 (¹324).Safety Analysis NSL-0000-SA024 | (2) The second table provides a listing of changes made to the format and overall structure of the UFSAR table. | ||
~~~~ | (3) The third table lists the changes made to each individual penetration on the UFSAR table. | ||
Consequently, these changes do not | (4) The fourth table identifies all changes made to the UFSAR table notes. However, since many modifications were made to the UFSAR table, most notes have been renumbered and revised. | ||
Consequently, to eliminate confusion, a change associated with the notes column for a particular penetration is only identified in Table 3 if a note has been added or deleted. There is no change identified in Table 3 only been changed, if a note number has if changes were made to the note itself, or if the note was deleted globally. | |||
~~(b)4629 ($308)g 4630 ($31 1)~4642 ($312)g 4643 (f315) | Instead, these changes are provided in Table 4. | ||
Consequently, the line is not required to isolate.See UFSAR Table Note 17.Therefore, the change in valve position does not negatively impact the penetration or the containment isolation system.3.3.2.6 a"No" for valve 745 ($124a).The Maximum Isolation Time column was also changed from"60" to"NA".These changes are justified per Reference 2.16.3.3.2.7 Several penetrations had valves added to the table, deleted, or both.These are described below by penetration number.(a)Penetration 103 | 3.3 The changes to UFSAR Table 6.2-13 fall into three categories: | ||
The penetration now reflects the current configuration. | clarifications or corrections of typographical errors and omissions,. | ||
The use of the Blind Flange is consistent with the previous locked-closed manual valve.(b)Penetration 111 | (2) updates to better represent actual plant conditions, and (3) updates for consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E. | ||
~~ | Safety Analysis Revision 0 Page 3 NSL-0000-SA024 | ||
~~~~(e)Penetration 141 | |||
The significant changes are described below.Notes 7 and 19 were added to ensure that consistency is maintained between Technical Specification Table 3.6-1 and the UFSAR Table.These notes mainly provide clarification and do not involve a technical change.Safety Analysis NSL-0000-SA024 | ~ ~ s ~ | ||
~I~~3.3.3.2 | 3.3.1 The correction of typographical errors and omissions does not involve any technical change to the UFSAR table nor the function and capability of the containment isolation system. All columns and rows in the table now contain either the 'necessary information or "NA". No blanks or "-" remain in the table. In addition, the clarifications made to the UFSAR table are minor and do not involve any technical changes. | ||
The events related to this UFSAR change are: Safety Analysis NSL-0000-SA024 | Significant clarifications are discussed below. | ||
~~ | 3.3.1.1 The Position At Postaccident column was changed to reflect plant conditions immediately following a Containment Isolation Signal (CIS) . This column was modified since system configurations can be changed during recovery operations. If this column was not modified, it would require most valves to list "0/C". The column now provides a clear listing of the valve positions prior to any operator action (i.e., "immediate" post accident) . | ||
There is no physical modification to Ginna Station as a result of these changes.No fire barriers are affected by these changes, nor is there any increase in area fire loadings.The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a seismic event.The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. | 3.3.1.2 The Notes column was changed to only supplement UFSAR Section 6.2.4.4.2 text. All duplications of information contained in the UFSAR text was removed from the Notes. The Notes column now only identify exceptions, references, etc., not contained in the UFSAR text. | ||
No changes are made with respect to the seismic design of the affected penetrations. | 3.3.1.3 removed from the table since they do not provide any information relevant to the UFSAR Table. This information can be obtained from other sources including Appendix B of the Ginna Station Quality Assurance Manual. Consequently, the information contained in these columns remains in other RG&E controlled documents. | ||
The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to respond to a radiological release within containment. | 3.3.1.4 The Position Indication In Control Room column was modified to show the type of indication instead of "Yes/No". This is a significant enhancement since the table now identifies if there is a white status light or a red/green light associated with the valve on the Main Control Board, or both. | ||
The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. | 3.3.2 The updates to the UFSAR table to better represent actual plant conditions are described below. | ||
The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. | 3.3.2.1 Penetration $ 2 was added to the table. This spare penetration was modified during the 1990 Refueling Outage to enhance containment closure during mid-loop operations. The penetration meets all current containment penetration criteria. See Reference 2.17. | ||
There is no physical modification to Ginna Station as a result of these changes.Consequently, the containment isolation system is still within its design basis limits.The changes as described in Section 3.3 and Attachment B do not create the potential for the affected penetrations to cause a decrease in RCS inventory (i.e., a loss-of-coolant-accident) | Safety Analysis Revision 0 Page 4 NSL-0000-SA024 Date 9 24 90 | ||
.The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. | |||
The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. | ~ ~ ~ ~ | ||
No changes were made to capability of the parent systems (e.g., Residual Heat Removal)to perform their function.Consequently, the containment isolation system and associated parent systems remain within their design basis limits.Safety Analysis NSL-0000-SA024 | 3.3.2.2 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a more conservative position. That is, the valve position changed from either a "0/C" to "C", | ||
nO<r to nCn npn to nLCIr or srCtt to nLCn (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases, the valve is now identified as being in an isolated or closed position which is the function of a containment isolation valve. Valves (and penetration ¹) in this category include: 370B (¹100), 879 (¹110b), | |||
The changes to the UFSAR Table do not affect the capability of the containment isolation system to perform its function.All changes were rev'iewed to ensure continued compliance with the design basis for the containment isolation system and the Ginna Station Licensing Basis.4.0 Preliminar Safet Evaluation 4.1 | 371 (¹112), 846 (¹120a), 539 (¹120b), 547 (¹121a), | ||
All changes considered"less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.Thus, there is no change in system function, nor a reduction in system reliability. | 528 (121a), 508 (¹121b), 743 (¹124a), 745 (¹124a), | ||
The containment isolation and parent systems will remain within their design limits.The proposed UFSAR changes will not increase the consequences of an accident previously evaluated in the UFSAR.The modification does not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR.All changes considered"less conservative" are acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.'6, and 3.3.3.3.All additions and deletions to the table are also acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.Thus,-the function and capability of the containment isolation system to isolate any radiological release within containment is not degraded.Safety Analysis NSL-0000-SA024 | 1569 (¹124b) g 1571 (¹124b) g 1572 (¹124b) I 1574 | ||
~~~~ | (¹124b) I 759B (¹ 125) I 759A (¹126) I 749A (¹127) 749B (¹ 128) I 1787 (¹129) I 1786 (¹ 129) / 7971 | ||
4.3 The proposed UFSAR changes will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR.All changes considered"less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.Thus, the changes do not degrade the performance of the containment isolation system, nor the associated parent systems.4.4 The proposed UFSAR changes will not increase the consequences of a malfunction of equipment important to ,.safety previously evaluated in the UFSAR.The changes do not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR.All changes considered"less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.Thus, the function and capability of the containment isolation system to isolate any radiological release from containment is not degraded.=4.5 The proposed UFSAR changes will not create the possibility of an accident of a different type than any previously evaluated in the UFSAR.These changes are mainly clarifications and updates to reflect current plant conditions. | (¹132), 1076B (¹202), 1084B (¹202) I 1563 (¹203b) I 1565 (¹203b) I 1566 (¹203b) ~ 1568 (¹203b) I 5869 | ||
All changes considered"less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.There are no adverse affects upon other systems, nor any new failure modes induced.4.6 The proposed UFSAR changes will not create the possibility of a different type of malfunction of equipment important to safety than any previously evaluated in the UFSAR.The additions and deletions to the table are acceptable as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8, The changes do not degrade the containment isolation or associated parent systems.Safety Analysis NSL-0000-SA024 | (¹204), 966C (¹205), 966B (¹206a), 5735 (¹206b), | ||
~~4.7 | 966A (¹207a), 5736 (¹207b), 1080 (¹210), 5879 | ||
The functions and characteristics of the containment isolation system remains unchanged. | (¹300) g 6151 (¹301) g 6165 (¹301) ~ 6175 (¹303) 6152 (¹303) g 1 07 6A (¹304) I 1 084A ( ¹304) g 1554 | ||
However, changes are made to valve isolation times and the valves listed for specific penetrations. | (¹305c), 1556 (¹305c), 1557 (¹305c), 1559 (¹305c) f 1560 (¹305c), 1562 (¹305c), 7141 (¹310a), 921 | ||
These changes will be addressed in the Amendment Request to remove Table 3.6-1 from the Technical Specifications and reference this updated UFSAR table.Based on the above analysis, it has been determined | (¹332c), 922 (¹332c), 923 (¹332c), and 924 | ||
Attachment A Safety Analysis NSL-0000-SA024 | (¹332c) . | ||
3.3.2.3 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a comparable position. That is, the valve position changed from either a "0" to "0/C" or "0/C" to "0". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases where the valve was listed as open, the valve and penetration was required to be evaluated previously assuming that was the most conservative position. | |||
it was open since this Therefore, changing the valve's position for these cases does not negatively impact the penetration or containment isolation system since the valve was conservatively evaluated under open conditions previously. Valves (and penetration ¹) in this category include: 1723 (¹107), 1728 (¹107), 313 | |||
(¹108), 1789 (¹123 bottom), 1003A (¹143), 1003B | |||
(¹1 43) g 5869 (¹204) g 5735 (¹206b) I 5736 (¹207B) 5879 (¹300) ~ 4629 (¹308) g 4630 (¹31 1) I 4642 | |||
(¹312) g 4643 (¹315) I 4628 (¹316) g 4627 (¹319) f 4641 (¹320), 4644 (¹323), and 8418 (¹324) . | |||
Safety Analysis Revision 0 Page 5 NSL-0000-SA024 Date 9 24 90 | |||
~ ~ ~ ~ | |||
3.3.2.4 Several valves had their positions as listed under the Position At Cold Shutdown column in the UFSAR | |||
' Table changed to a less conservative position. | |||
That is, the valve position changed from either a "Cn to nOn or nCn to nO/Cn (See Table 3 of Attachment B =for a detailed description of these changes on a penetration by penetration basis.) | |||
However, containment integrity is not required in the Cold Shutdown condition (Technical Specification 3.6.1) . In addition, during reduced RCS inventory operations, the position of these valves (or an automatic isolation valve in the same line) is verified by Reference 2.18. Thus, these valves can be'closed if needed. | |||
during Refueling Operations, Technical Also, Specification 3.8.1 requires that all "automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed." Therefore, containment isolation is assured during refueling operations. | |||
Consequently, these changes do not the penetration or the containment negatively'mpact isolation system since administrative controls are in place. Valves (and penetration 0) in this category include: 7970 ($ 132), 7971 ($ 132), 5393 | |||
($ 310b), 7443 ($ 317), 5738 ($ 321), and 5737 | |||
($ 322) . | |||
3.3.2.5 Several valves had their positions as listed under the Position At Normal 0 eration and Position At Immediate Postaccident columns in the UFSAR Table changed to a less conservative position. That is, the valve position changed either from a "C" to "0/C", or "0" to "LO". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) There are two categories of valves which meet this criteria (organized by justification) . | |||
(a) 529 (g12lb) This penetration has an automatic isolation valve in the line to perform the necessary isolation function. In addition, since this check valve sees the same conditions as the associated automatic isolation valve, their positions should be the same. Consequently, the change does not negatively impact the penetration or the containment isolation system. | |||
Safety Analysis Revision 0 Page 6 NSL-0000-SA024 | |||
~ ~ | |||
(b) 4629 ($ 308) g 4630 ($ 31 1) ~ 4642 ($ 312) g 4643 (f315) 4628 ($ 316) | |||
~ g 4627 ($ 319) g 4641 | |||
($ 320), 4644 ($ 323) These essential Service Water System penetrations operate at a higher pressure than the containment accident pressure and are missile protected inside containment. Consequently, the line is not required to isolate. See UFSAR Table Note | |||
: 17. Therefore, the change in valve position does not negatively impact the penetration or the containment isolation system. | |||
3.3.2.6 a "No" for valve 745 ($ 124a) . The Maximum Isolation Time column was also changed from "60" to "NA". These changes are justified per Reference 2.16. | |||
3.3.2.7 Several penetrations had valves added to the table, deleted, or both. These are described below by penetration number. | |||
(a) Penetration 103 Valve 5129 was deleted from the table and replaced by a Blind Flange. | |||
This change enabled the elimination of the previous note of "No longer in use" that was associated with this penetration. The penetration now reflects the current configuration. The use of the Blind Flange is consistent with the previous locked-closed manual valve. | |||
(b) Penetration 111 Added valve 959. The addition of this valve to the table ensures that all valves receiving a containment isolation signal are listed. This valve was previously missing from the table, but credit was not taken for the valve during the SEP (see Reference 2.7) . Consequently, this is not considered an actual isolation valve and is not tested per Appendix J. | |||
(c) Penetration 112 - Valves 204A and 821 were deleted .-and replaced with valves 200A, 200B, and 202. Valve 427 was also added. The addition of these valves enables explicit compliance with GDC 55 versus the use of the two redundant isolation valves. These new valves are included in the current IST program (see Reference 2.19). | |||
(d) 123 (bottom) Added valve 1600A. See explanation for 3.3.2.7 (b) above. | |||
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(e) Penetration 141 Deleted valve 851A and added valve 1813A. Valve 851A does not meet the selection criteria for 10CFR50 Appendix J, Section IIH, items 1 through 4. | |||
Consequently, the valve was deleted from the table. Valve 1813A was previously missing from the table. This valve is locked-closed with its breaker locked open. | |||
(f) 'enetration 142 Deleted valve 851B and added valve 1813B. See explanation for 3.3.2.7 (e) above. | |||
(g) Penetration 205 Added valve 955. See explanation for 3.3.2.7 (b) above. | |||
(h) Penetration 206a Added valve 953. See explanation for 3.3.2.7 (b) above. | |||
(i) Penetration 207a Added valve 951. See explanation for 3.3.2.7 (b) above. | |||
(j) Penetration 210 Added valves 10214S1 and 10215S1. These valves were previously missing from the table, but receive an isolation signal. | |||
3.3.2.8 Penetration 332b Deleted entire penetration branch from the table. This penetration branch contains double isolation, fits the criteria as a test connection, and performs no active function. | |||
Therefore, there is no requirement to test the valves as containment isolation valves. | |||
Consequently, this penetration branch was removed from the table. | |||
3.3.3 Several updates were made to the UFSAR table to ensure consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E. | |||
These changes are typically only clarifications. The significant changes are described below. | |||
3.3.3.1 Notes 7 and 19 were added to ensure that consistency is maintained between Technical Specification Table 3.6-1 and the UFSAR Table. | |||
These notes mainly provide clarification and do not involve a technical change. | |||
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3.3.3.2 The Maximum Isolat'ion Time of several valves was changed to a more conservative duration. That is, the time was changed from "NA" to either "3" seconds for solenoid valves, or "60" seconds for AOVs and MOVs. (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) The UFSAR Table now identifies an isolation time for all valves receiving a containment isolation signal. | |||
Valves (and penetration 4) in this category include: 1787 ($ 129), 10211S1 ($ 202), 10213S1 | |||
($ 202), 966C ($ 205), 966B ($ 206a), 5735 ($ 206b), | |||
966A ($ 207a), 5736 ($ 207b), 10214S ($ 210), 10215S1 | |||
($ 210) / 10205S1 ($ 304) g 10209S1 ($ 304) g 1597 | |||
($ 305a), 1599 ($ 305b), and 8418 ($ 324) . | |||
3.3.3.3 The Maximum Isolation Time of several valves was changed to a less conservative duration. There are three categories of valves which meet this criteria (organized by justification): | |||
(a) 749A (f127), 749B ($ 128) These valves do not receive a containment isolation signal. | |||
Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time. | |||
(b) 5869 ($ 204) This valve does not require an isolation time since the associated blind flange acts as the isolation boundary. See, UFSAR Table Note 19. Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time. | |||
(c) 7970 ($ 132), 7971 ($ 132), 7478 (f309), and 7445 (f309) The isolation time for these butterfly valves was changed from "2" seconds to "3" seconds. Technical Specification Table 3.6-1 allows five seconds with instrument delay. However, the Maximum Isolation Time column does not include instrument delay per Note "b". The instrument delay time for these valves is approximately 2 seconds. Consequently, the valve isolation time was changed to "3" seconds. | |||
3.4 A review of the design basis events analyzed in the Ginna Station UFSAR and,the events requiring analysis as described in USNRC Reg. Guide 1.70 was performed. | |||
The events related to this UFSAR change are: | |||
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(a) Fires (b) Seismic Events (c) Radiological Release From a Subsystem or Component (d) Decrease in Reactor Coolant Inventory (e) Events Initiating a Safety Injection Signal 3.4.1 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a fire. | |||
The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. No fire barriers are affected by these changes, nor is there any increase in area fire loadings. | |||
3.4.2 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a seismic event. The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. No changes are made with respect to the seismic design of the affected penetrations. | |||
3.4.3, | |||
~ ~ The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to respond to a radiological release within containment. The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. Consequently, the containment isolation system is still within its design basis limits. | |||
3.4.4 The changes as described in Section 3.3 and Attachment B do not create the potential for the affected penetrations to cause a decrease in RCS inventory (i.e., a loss-of-coolant-accident) . The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. No changes were made to capability of the parent systems (e.g., Residual Heat Removal) to perform their function. Consequently, the containment isolation system and associated parent systems remain within their design basis limits. | |||
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3.4.5 Events which initi'ate Safety Injection also result in the need for containment isolation. The changes to the UFSAR Table do not affect the capability of the containment isolation system to perform its function. | |||
All changes were rev'iewed to ensure continued compliance with the design basis for the containment isolation system and the Ginna Station Licensing Basis. | |||
4.0 Preliminar Safet Evaluation 4.1 The proposed UFSAR changes will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. The changes to the UFSAR Table are to correct typographical errors, provide additional clarification, and update the table to reflect actual plant conditions. All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. | |||
Thus, there is no change in system function, nor a reduction in system reliability. The containment isolation and parent systems will remain within their design limits. | |||
4.2 The proposed UFSAR changes will not increase the consequences of an accident previously evaluated in the UFSAR. The modification does not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.'6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus,- the function and capability of the containment isolation system to isolate any radiological release within containment is not degraded. | |||
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4.3 The proposed UFSAR changes will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR. | |||
All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the changes do not degrade the performance of the containment isolation system, nor the associated parent systems. | |||
4.4 The proposed UFSAR changes will not increase the consequences of a malfunction of equipment important to | |||
,. safety previously evaluated in the UFSAR. The changes do not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the function and capability of the containment isolation system to isolate any radiological release from containment is not degraded. = | |||
4.5 The proposed UFSAR changes will not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. These changes are mainly clarifications and updates to reflect current plant conditions. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. | |||
All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. There are no adverse affects upon other systems, nor any new failure modes induced. | |||
4.6 The proposed UFSAR changes will not create the possibility of a different type of malfunction of equipment important to safety than any previously evaluated in the UFSAR. The additions and deletions to the table are acceptable as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8, The changes do not degrade the containment isolation or associated parent systems. | |||
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4.7 The proposed UFSAR changes will not reduce any margin of safety as defined in the basis of any technical specification. The functions and characteristics of the containment isolation system remains unchanged. | |||
However, changes are made to valve isolation times and the valves listed for specific penetrations. These changes will be addressed in the Amendment Request to remove Table 3.6-1 from the Technical Specifications and reference this updated UFSAR table. | |||
4.8 Based on the above analysis, that: | |||
it has been determined (a) The margins of safety during normal operation and transient conditions anticipated during the life of the plant has not been reduced, and (b) The adequacy of structures, systems, and components provided for the prevention of accidents and for the mitigation of the consequences of accidents have not been affected. | |||
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Attachment A Safety Analysis Revision 0 Page 14 NSL-0000-SA024 Date 9 24 90 | |||
2-13 CONTAI PENETRATIONS AND I PIPINC Position Position At Maxisans Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Normal Cold Ixaedf ate UFSAR Notes | |||
~Sstea No. No. Shutdovn Postaccfdent~ | |||
Steam Cenerator Blind Flanges Both 0/C C (add) 5 I~ 2 Inspection/ | |||
Maintenance Fuel Transfer 29 Blind Flange Inside 0/C 6 '-13 5 2I 3 Tube Charging Line 100 370B Check Inside 6.2-18 3B to B Loop Safety 101 870B Check Outside 0 6 '-15 3B Infection Pury 889B Check Outside 0 6 '-15 3B IB Discharge Alternate 102 3838 Check Inside C 6.2-16 3B Charging to A Cold Leg Construction 103 NA Blind Flange NA NA Inside C C NA 6 '-17 5 Ffre Service Water Containment 105 8 62A Check NA Outside C 0 NA 6 '-18 3B Spray Pusy IA Reactor Coolant 106 306k Check Nh Inside 0 6 '-19 3B Puxy h Seal Water Inlet Susy h Dfs 107 1723 Diaphraga Afr Status Outside 0 0/C C FC Yes 60 6.2 20 2 charge to Waste 1728 Dfaphraga hir Status Outside 0 0/C C FC Yes 60 6 '"20 2 Holdup Tank Reactor Coolant 108 313 Motor Both Outside 0/C AI Yes 60 F 2-21 8, 6 Pump Seal Water Return Lfne and Excess Letdovn to VCT Containment 109 862B Check Nh NA Outside C Nh 6.2 22 3B Spray Pury IB end AI Falls As Is MQV Moto~rated Valve Refers to position fsuediately follovfng receipt of containment AOV Air Operated Valve MV ~ Manual Valve isolation signal and containment ventilation fsolation signal. | |||
C ~ Closed 0 ~ Open s The maxfxaa isolation time does not include diesel start time CIS ~ Contafnment Isolation Signal 0/C Open or Closed nor instrument delay tfme. | |||
CV Check Valve R/C ~ Red / Creen Light on Main Control Board 'efers to classes defined in Section 6.2.6.6.2. | |||
s Notes only used to supplement Section 6.2.6.6.2. | s Notes only used to supplement Section 6.2.6.6.2. | ||
Safety Analysis'I" NSL-'.OO,OO-SA024 | FC ~ Falls Closed Status White Status Light, FO Fails Open SOV Solenoid Operated Valve LC ~ Locked Closed Safety Analysis Revision 1 | ||
-13 CONTAI PENETRATIONS AND I PIPING | 'I Page 14a | ||
" NSL-'.OO,OO-SA024 | |||
-13 CONTAI PENETRATIONS AND I PIPING Position Position At Maxi xixa Valve Indication Position Isolation Penetratfon Valve Valve Operator In Control Relative to Homal Cold lxxaadf ate Paver | |||
~Satan No. No. Roon Contafnnent OHeratfon Shutdovn Postaccfdentv Failure Trip on Tfxe DFSAR Notes CIS Reactor Coolant 110a (topi 304B Check NA Nh InsMe 0 0~ C Purp B Seal NA Nh 6.2-23 3B Nater Inlet Safety 110b <bottoni 879 Globe Manual No Outside LC LC Inlectfon Test NA 6 ~ 2-15 1 Lfne Residual Hea't 720 Gate Motor R/C Inside 0 AI Renoval to B 959 Globe Alr Status 6.2-24 3B 4 ~ 7g 8 Outs fde 0/C FC 6.2-24 Cold Leg 3B 4, 1 I | |||
Letdown to 112 200A Globe Afr R/G Inside 0/C Nonregenerative 200B Globo Alr R/G Inside 0/C C C Yes 60 6~ 225 I 10 Heat Exchanger 202 Clobe Air R/G Inside C C | |||
C C Tes $0 $ e2 25 I 10 371 Globe Air Both Outside 0 0 C Yes 60 6~ 225 1 10 421 Globe Alr R/C Inside 0 0/C C Yes $0 6.2-25 I C Yes $ .2-25 I Safety 113 810A Check NA Outside C 6.2-15 In)ection Puxp 889A Check NA Outside C 3B IA Discharge 6.2 15 3B Standby Auxf I- 119 9104A Stop-Check Motor R/G OutsMe AI fary Feedwater 9105A No 6.2 26 Check NA Nh Inside NA Nh 6.2-26 Line to Stean Generator lh Nitrogen to 120a 846 Globe Air Both Outside C 0/C C FC Yes 60 hccuxaIlators 4623 6 ~ 2 21 3A Check NA NA Inside 0/C '/C | |||
, C NA Nh $ .2-27 3A Pressurlxer 120b 539 Globe Air Sta'xus Outside 0/C Relief Tank to 546 Globe Manual C FC Yes 6 ~ 2-28 2 No Outside 0 0 Nh Nh F 2-24 Gas Analyxer 2 Nitrogen to 121a 528 Check NA NA Inside 0/C 6.2-29 Pressurixer 547 Globe lanual No Outside OIC 3A Relief Tank $ .2 29 3A 12 Makeup Rater to 121b 504 Dfaphragn Air Both Outside C OIC C Pressurixer 529 FC Yes 60 6 ~ 2-30 3A Check NA NA Inside 0/C OIC C NA Nh $ .2-30 Relief Tank NA 3A Conte funest 121c PT945 NA NA Outside Pressure 1819A Globe 6 2-31 2 13 Manual Outs Me 6.2 31 2 Transnftt@r PT945 Contafnnent 121d F2946 Nh NA NA Outside Nh NA Pressure 1819B Globe Manual 6.2-31 2 13 No Outside 0 0 6 2-31 2 TransxLit'tox'T946 Standby Auxfl- 123 ltopl 9104 B Stop-Check Motor Outside C C AI NA 6.2-26 fary I'eedvater 91058 Check Nh Inside C C Nh Nh 6.2-26 Line to Stean 4 Generator IB Safety Analysis Revision 1 Page 14b NSL-,OOOO-SA024 Date 10 3 90 | |||
) | ) | ||
~ 2-13 ~ | |||
CONTAI PENETRATION~a AND PIPIhG Position Posftfon At f Max aaxa Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Homal Cold Iacaediate Pover Tilac | |||
~Sat cmc No. ~T Rocvm, Contafnacent OEeratfon Shutdovn postaccfdcntr Trip on UFSAR Notes Failure CI8 ~Fi re Reactor Coolant 123 (button) 1600A Globe Solenoid No Outsfde 0 0/C Drain Tank to 1655 Globe Manual C Ycls NA 6.2-32 Analyzer No Outside 0 0 0 NA 6.2-32 Gas Line 1789 Diaphragca hfr Status Outside 0 0/C C Yes 60 6 '-32 Excess Letdovn 124a 743 Check Q Q Inside 0 Beat Exchanger 745 Globe hi r C C NA 6.2-33. | |||
RIG Outside 0 C C No 6.2-33 Cooling Water 14 Supply 4 Return Postaccfdcnt 124b 1569 Dfaphragca Afr Sag>le to C Manual Outs fde LC 6 '-34 5 Fan 1571 1572 Dfsphragca Dfaphragrc Manual Manual OutsMe Outside IC, 6.2 34 5 LC 6.2-34 5 1574 Dfaphragal Manual Outsfde LC 6.2-34 5 r | |||
Component 125 7598 Cate Hotor R/C Outside C 0 AI No 6.2-35 Cooling Water 4 fraa Reactor r Coolant Pump 1B Ccxcponent 126 759A Gate Motor R/C Outside 0 Cooling Water AI No Nh 6.2<<36 frees Reactor Coolant Pump IA Componen't 127 749A Cate Hotor Outside 0 Cooling Nater 750A Check Inside 0 C 0 AI Q 6.2-37 4 to Reactor NA C 0 NA Q 6.2-37 Coolant Pump lh Cccmponeat 128 7498 Cate Motor Cooling Water OutsMe 0 C 0 AI No Q 6 '-38 to Reactor Coolant ~ | |||
Reactor Coolant 1B 129 7508 1713 Check Check NA Inside 0 C 0 NA NA Q 6 '-38 4 NA NA Outside C 0/C C NA NA 6. 2-39 Drain Tank and Pressurizer 1786 Dfaphragal hir Sta'tus Outsfde 0 C C FC Yes NA 60 6 '-39 3A 3A Relist 1787 Dfaphragca Air S'ta'tua Outside 0 C C FC Yes 6.2-39 Tank to 1793 Dfaphragal Manual No Outside LC 0/C LC 60 3A Containnent Nh NA NA 6 ~ 2-3S 3A 12 Vent Reader Component 130 814 Gate Motor Both Outside 0 Cooling Water AI Yes 60 6.2-40 4 frcxa Reactor Support Cooling Cc~nent 131 813 Cate Hotor Both Outside 0 0 AI Cooling Nater Yes 60 6.2-40 4 to Ream'tor Support Cooling Containment Nfnf-Purge 132 7970 Butterfly hir Both Inside 0/C OIC C FC Yes 3 6.2-41 5 Exhaust 7971 Buttertly Alr Both OutsMe C 0/C C FC Yes 3 6.2-41 5 | |||
',Safety Anal'ysis Revision 1 r | |||
Page 14c NSL-0000-SA024 | |||
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2 13 CONTAI PENETRATION< | |||
AND I ~ PIPING Position Position At Kaxfmsus Valve Indication Posftfon Imoist fon Penetration Valve Valve Operator In Control Relative to Normal Cold Imnediate Fever Trip on Time OFSAR Notes | |||
~zs ten No. No. Room Containment OHeratfon Shutdovn Postaccidcnt'ailure CIS ~Ff re Classs See end of table ~ | |||
Residual Beat 140 701 Gate Hotor R/C Inside 0 C AI 6.2-42 1 7i 8 Removal Pump Suctfon from A Hot, Leg Residual Heat 141 85th Cate Hotor R/0 Outside C C 0 AI No Nh 6.2-42 5 15 Removal No. 1 1813A Cate Hotor R/C Outside C 0/C C AI No NA 6.2-42 5 8 Pump Suction from Sump B Residual Heat 142 SSOB Gate Hotor R/C Outside C C AI NA 6 ~ 2-42 5 15 Removal No. 2 1813B Gate Hotor R/0 Outside C 0/C AI NA 6.2-42 5 8 Pump Suction from Su~ B Reactor Coolant 143 1003A DIa phragn Air Status Outside 0 0/C C Yes 60 '.2-43 2 Drain Tant 1003B Diaphragm Afr Status Outside 0 0/C C Yes 60 6 ~ 2-43 2 Discharge Lfne 1721 Diaphragm Alr Status Outside 0 0 C Yes 60 6.2-42 2 Reactor | |||
Removed notes associated with Technical Specification 4.4.2.4 section a. Deleted Mini-purge valves have been installed so the Technical Specification can be considered reference to section d. effective. Section d will be removed from Technical Specifications. No technical change. | |||
: 11. Added steam generator Addition of this penetration inspection/maintenance provides testing criteria similar penetration to Technical to the equipment hatch and Specification 4.4.2.4 containment air locks. | |||
section b. | |||
: 12. Removed Technical Blind flanges have been installed Specification 4.4.2.4 so the Technical Specification can section d and associated be considered effective. No note. technical change. | |||
1 3. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.5.1. 10CFR50.59 program. | |||
: 14. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.6.2. 10CFR50.59 program. | |||
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Latest revision as of 09:50, 4 February 2020
ML17262A193 | |
Person / Time | |
---|---|
Site: | Ginna |
Issue date: | 10/03/1990 |
From: | ROCHESTER GAS & ELECTRIC CORP. |
To: | |
Shared Package | |
ML17262A190 | List: |
References | |
NSL--SA24, NSL-0000-SA024, NUDOCS 9010240119 | |
Download: ML17262A193 (82) | |
Text
Safety Analysis Ginna Station UFSAR Table 6.2-13 Changes Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 NSL-0000-SA024 Revision 1 October 3, 1990 Prepared by: K) -z.-'9Q Nu lear Engineer Date Reviewed by:
Nucle r Engine r Date Approved by:
anag r, Nuclear S fety & Licensing Date Page i 90i0240i'i9 90iOi5 05000244 PDR ADOCK P PDC I
Revision Status Sheet Latest Latest Latest Page Revision Page 'evision Page Revision 14h 37 15 38 16 39 17 40 18 41 19 42 20 0 43 21 44 7 22 45 8 23 46 9 24 47
,10 25 48 12 27 13 28 14 29 14a 30 14b 31 14c 32 14d 33 0 14e 34 14f 35 14g 36 Safety Analysis Revision NSL-0000-SA024 Page ii Date 1
10 3 90
Safet Anal sis Descri tion and f
1.0 Sco e The purpose of this evaluation is to determine are any unreviewed safety questions related to updating if there UFSAR Table 6.2-13, Containment Piping Penetrations and Isolation Valves. This update is necessary to reflect information obtained during a detailed review of the containment isolation system and the result of the 1988 Inservice Test (IST) Program submittal to the NRC.
2.0 References 2.1 Updated Final Safety Analysis Report, Revision 5.
2.1.1 Section 6.2.4, Containment Isolation System.
2.1.2 Table 6.2-13, Containment Piping Penetrations and Isolation Valves.
2.2 R.E. Ginna Nuclear Power Plant Technical Specifications, dated April 12, 1990.
2.2.1
~ ~ Section 3.6.3, Containment Isolation Valves.
2.2.2 Table 3.6-1, Containment Isolation Valves.
2.2.3 Section 3.8.1, Refueling.
2.3 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC,
Subject:
SEP Topic VI-4, Containment Isolation Valves (Systems); dated August 30, 1982.
2.4 Letter from L.D. White, RG&E, to D.L. Ziemann, NRCg
Subject:
Discussion of Lessons Learned Short Term Requirements; dated November 19, 1979.
2.5 Letter from L.D. White, RG&E, to B.H. Grier, NRC,
Subject:
IE Bulletins79-06A and 79-06A Revision 1; dated June 22, 1979.
2.6 Letter from L.D. White, RG&E, to D.L. Ziemann, NRC,
Subject:
Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI Unit 2 Accident; dated October 17, 1979.
2.7 Letter from D.M. Crutchfield, NRC, to J.E. Maier, NRC,
Subject:
Forwarding Final Evaluation Report of SEP Topic VI-4, Containment Isolation System for the Ginna Nuclear Power Plant; dated April 12, 1982.
Safety Analysis Revision 0 Page 1 NSL-0000-SA024
2.8 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC,
Subject:
SEP Topic VI-4, Containment Isolation System; dated December 30, 1981.
2.9 NUREG-0821, Integrated Plant Safety Assessment, Systematic Evaluation Program, R.E. Ginna Nuclear Power Plant; dated December 1982.
2.10 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,
Subject:
Necessary Clarifications Associated With Technical Specification Table 3.6-1; dated July 2, 1990.
2.11 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,
Subject:
Containment Isolation Valves AOV 745 (Penetration 124a), MOV 749A (Penetration 127), and MOV 749B (Penetration 128); dated June 22, 1990.
2.12 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,
Subject:
Technical Specification Interpretation of Containment Isolation Valves MOVs 749 A/B; dated June 21, 1990.
2.13 USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants; Revision 3, November 1978.
2.14 Letter from D.D. Di?anni, USNRC, to R.W. Kober, RG&E,
Subject:
SEP Topic VI-4, NUREG-0821 Section 4.22.2, Containment Isolation Valves; dated January 30, 1987.
2.15 NUREG-0800, Standard Review Plan, Section 6.2.4, Revision 2, July 1981.
2.16 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Operability of AOV 745 and MOVs 749A/B; dated July 9, 1990.
2.17 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Modification of Containment Penetration $ 2; dated March 13, 1990.
2.18 Ginna Station Procedure 0-2.3.1A, Containment Closure Capability in Two Hours During RCS Reduced Inventory Operations, Revision 5, dated April 28, 1990.
2.19 Ginna Station Quality Assurance Manual.
2.19.1 Appendix B, Inservice Inspection Program For the 1990-1999 Interval, Revision 0, dated January 1, 1990.
2.20 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
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3.0 Safet Anal sis 3~1 The system affected, by this UFSAR change is the containment isolation system. This system is designed to isolate non-essential process lines which penetrate the containment to ensure that the total leakage of activity will be within design limits in the event of an accident. In addition, the parent systems (e.g.,
Safety Injection) of the components contained in the containment isolation system can be considered affected by this UFSAR change. However, there is no change to the capability of these systems to perform their intended design function, only an update of their ability to isolate containment when required.
3.2 The updated UFSAR Table 6.2-13 is presented in Attachment A. Due to the significant number of changes, a marked-up version of the current UFSAR table was not generated. Instead, Attachment B provides a detailed listing of all changes made to the table.
Attachment B is divided into four (4) sub tables.
The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy.
(2) The second table provides a listing of changes made to the format and overall structure of the UFSAR table.
(3) The third table lists the changes made to each individual penetration on the UFSAR table.
(4) The fourth table identifies all changes made to the UFSAR table notes. However, since many modifications were made to the UFSAR table, most notes have been renumbered and revised.
Consequently, to eliminate confusion, a change associated with the notes column for a particular penetration is only identified in Table 3 if a note has been added or deleted. There is no change identified in Table 3 only been changed, if a note number has if changes were made to the note itself, or if the note was deleted globally.
Instead, these changes are provided in Table 4.
3.3 The changes to UFSAR Table 6.2-13 fall into three categories:
clarifications or corrections of typographical errors and omissions,.
(2) updates to better represent actual plant conditions, and (3) updates for consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.
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3.3.1 The correction of typographical errors and omissions does not involve any technical change to the UFSAR table nor the function and capability of the containment isolation system. All columns and rows in the table now contain either the 'necessary information or "NA". No blanks or "-" remain in the table. In addition, the clarifications made to the UFSAR table are minor and do not involve any technical changes.
Significant clarifications are discussed below.
3.3.1.1 The Position At Postaccident column was changed to reflect plant conditions immediately following a Containment Isolation Signal (CIS) . This column was modified since system configurations can be changed during recovery operations. If this column was not modified, it would require most valves to list "0/C". The column now provides a clear listing of the valve positions prior to any operator action (i.e., "immediate" post accident) .
3.3.1.2 The Notes column was changed to only supplement UFSAR Section 6.2.4.4.2 text. All duplications of information contained in the UFSAR text was removed from the Notes. The Notes column now only identify exceptions, references, etc., not contained in the UFSAR text.
3.3.1.3 removed from the table since they do not provide any information relevant to the UFSAR Table. This information can be obtained from other sources including Appendix B of the Ginna Station Quality Assurance Manual. Consequently, the information contained in these columns remains in other RG&E controlled documents.
3.3.1.4 The Position Indication In Control Room column was modified to show the type of indication instead of "Yes/No". This is a significant enhancement since the table now identifies if there is a white status light or a red/green light associated with the valve on the Main Control Board, or both.
3.3.2 The updates to the UFSAR table to better represent actual plant conditions are described below.
3.3.2.1 Penetration $ 2 was added to the table. This spare penetration was modified during the 1990 Refueling Outage to enhance containment closure during mid-loop operations. The penetration meets all current containment penetration criteria. See Reference 2.17.
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3.3.2.2 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a more conservative position. That is, the valve position changed from either a "0/C" to "C",
nO<r to nCn npn to nLCIr or srCtt to nLCn (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases, the valve is now identified as being in an isolated or closed position which is the function of a containment isolation valve. Valves (and penetration ¹) in this category include: 370B (¹100), 879 (¹110b),
371 (¹112), 846 (¹120a), 539 (¹120b), 547 (¹121a),
528 (121a), 508 (¹121b), 743 (¹124a), 745 (¹124a),
1569 (¹124b) g 1571 (¹124b) g 1572 (¹124b) I 1574
(¹124b) I 759B (¹ 125) I 759A (¹126) I 749A (¹127) 749B (¹ 128) I 1787 (¹129) I 1786 (¹ 129) / 7971
(¹132), 1076B (¹202), 1084B (¹202) I 1563 (¹203b) I 1565 (¹203b) I 1566 (¹203b) ~ 1568 (¹203b) I 5869
(¹204), 966C (¹205), 966B (¹206a), 5735 (¹206b),
966A (¹207a), 5736 (¹207b), 1080 (¹210), 5879
(¹300) g 6151 (¹301) g 6165 (¹301) ~ 6175 (¹303) 6152 (¹303) g 1 07 6A (¹304) I 1 084A ( ¹304) g 1554
(¹305c), 1556 (¹305c), 1557 (¹305c), 1559 (¹305c) f 1560 (¹305c), 1562 (¹305c), 7141 (¹310a), 921
(¹332c), 922 (¹332c), 923 (¹332c), and 924
(¹332c) .
3.3.2.3 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a comparable position. That is, the valve position changed from either a "0" to "0/C" or "0/C" to "0". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases where the valve was listed as open, the valve and penetration was required to be evaluated previously assuming that was the most conservative position.
it was open since this Therefore, changing the valve's position for these cases does not negatively impact the penetration or containment isolation system since the valve was conservatively evaluated under open conditions previously. Valves (and penetration ¹) in this category include: 1723 (¹107), 1728 (¹107), 313
(¹108), 1789 (¹123 bottom), 1003A (¹143), 1003B
(¹1 43) g 5869 (¹204) g 5735 (¹206b) I 5736 (¹207B) 5879 (¹300) ~ 4629 (¹308) g 4630 (¹31 1) I 4642
(¹312) g 4643 (¹315) I 4628 (¹316) g 4627 (¹319) f 4641 (¹320), 4644 (¹323), and 8418 (¹324) .
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3.3.2.4 Several valves had their positions as listed under the Position At Cold Shutdown column in the UFSAR
' Table changed to a less conservative position.
That is, the valve position changed from either a "Cn to nOn or nCn to nO/Cn (See Table 3 of Attachment B =for a detailed description of these changes on a penetration by penetration basis.)
However, containment integrity is not required in the Cold Shutdown condition (Technical Specification 3.6.1) . In addition, during reduced RCS inventory operations, the position of these valves (or an automatic isolation valve in the same line) is verified by Reference 2.18. Thus, these valves can be'closed if needed.
during Refueling Operations, Technical Also, Specification 3.8.1 requires that all "automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed." Therefore, containment isolation is assured during refueling operations.
Consequently, these changes do not the penetration or the containment negatively'mpact isolation system since administrative controls are in place. Valves (and penetration 0) in this category include: 7970 ($ 132), 7971 ($ 132), 5393
($ 310b), 7443 ($ 317), 5738 ($ 321), and 5737
($ 322) .
3.3.2.5 Several valves had their positions as listed under the Position At Normal 0 eration and Position At Immediate Postaccident columns in the UFSAR Table changed to a less conservative position. That is, the valve position changed either from a "C" to "0/C", or "0" to "LO". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) There are two categories of valves which meet this criteria (organized by justification) .
(a) 529 (g12lb) This penetration has an automatic isolation valve in the line to perform the necessary isolation function. In addition, since this check valve sees the same conditions as the associated automatic isolation valve, their positions should be the same. Consequently, the change does not negatively impact the penetration or the containment isolation system.
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(b) 4629 ($ 308) g 4630 ($ 31 1) ~ 4642 ($ 312) g 4643 (f315) 4628 ($ 316)
~ g 4627 ($ 319) g 4641
($ 320), 4644 ($ 323) These essential Service Water System penetrations operate at a higher pressure than the containment accident pressure and are missile protected inside containment. Consequently, the line is not required to isolate. See UFSAR Table Note
- 17. Therefore, the change in valve position does not negatively impact the penetration or the containment isolation system.
3.3.2.6 a "No" for valve 745 ($ 124a) . The Maximum Isolation Time column was also changed from "60" to "NA". These changes are justified per Reference 2.16.
3.3.2.7 Several penetrations had valves added to the table, deleted, or both. These are described below by penetration number.
(a) Penetration 103 Valve 5129 was deleted from the table and replaced by a Blind Flange.
This change enabled the elimination of the previous note of "No longer in use" that was associated with this penetration. The penetration now reflects the current configuration. The use of the Blind Flange is consistent with the previous locked-closed manual valve.
(b) Penetration 111 Added valve 959. The addition of this valve to the table ensures that all valves receiving a containment isolation signal are listed. This valve was previously missing from the table, but credit was not taken for the valve during the SEP (see Reference 2.7) . Consequently, this is not considered an actual isolation valve and is not tested per Appendix J.
(c) Penetration 112 - Valves 204A and 821 were deleted .-and replaced with valves 200A, 200B, and 202. Valve 427 was also added. The addition of these valves enables explicit compliance with GDC 55 versus the use of the two redundant isolation valves. These new valves are included in the current IST program (see Reference 2.19).
(d) 123 (bottom) Added valve 1600A. See explanation for 3.3.2.7 (b) above.
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(e) Penetration 141 Deleted valve 851A and added valve 1813A. Valve 851A does not meet the selection criteria for 10CFR50 Appendix J, Section IIH, items 1 through 4.
Consequently, the valve was deleted from the table. Valve 1813A was previously missing from the table. This valve is locked-closed with its breaker locked open.
(f) 'enetration 142 Deleted valve 851B and added valve 1813B. See explanation for 3.3.2.7 (e) above.
(g) Penetration 205 Added valve 955. See explanation for 3.3.2.7 (b) above.
(h) Penetration 206a Added valve 953. See explanation for 3.3.2.7 (b) above.
(i) Penetration 207a Added valve 951. See explanation for 3.3.2.7 (b) above.
(j) Penetration 210 Added valves 10214S1 and 10215S1. These valves were previously missing from the table, but receive an isolation signal.
3.3.2.8 Penetration 332b Deleted entire penetration branch from the table. This penetration branch contains double isolation, fits the criteria as a test connection, and performs no active function.
Therefore, there is no requirement to test the valves as containment isolation valves.
Consequently, this penetration branch was removed from the table.
3.3.3 Several updates were made to the UFSAR table to ensure consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.
These changes are typically only clarifications. The significant changes are described below.
3.3.3.1 Notes 7 and 19 were added to ensure that consistency is maintained between Technical Specification Table 3.6-1 and the UFSAR Table.
These notes mainly provide clarification and do not involve a technical change.
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3.3.3.2 The Maximum Isolat'ion Time of several valves was changed to a more conservative duration. That is, the time was changed from "NA" to either "3" seconds for solenoid valves, or "60" seconds for AOVs and MOVs. (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) The UFSAR Table now identifies an isolation time for all valves receiving a containment isolation signal.
Valves (and penetration 4) in this category include: 1787 ($ 129), 10211S1 ($ 202), 10213S1
($ 202), 966C ($ 205), 966B ($ 206a), 5735 ($ 206b),
966A ($ 207a), 5736 ($ 207b), 10214S ($ 210), 10215S1
($ 210) / 10205S1 ($ 304) g 10209S1 ($ 304) g 1597
($ 305a), 1599 ($ 305b), and 8418 ($ 324) .
3.3.3.3 The Maximum Isolation Time of several valves was changed to a less conservative duration. There are three categories of valves which meet this criteria (organized by justification):
(a) 749A (f127), 749B ($ 128) These valves do not receive a containment isolation signal.
Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.
(b) 5869 ($ 204) This valve does not require an isolation time since the associated blind flange acts as the isolation boundary. See, UFSAR Table Note 19. Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.
(c) 7970 ($ 132), 7971 ($ 132), 7478 (f309), and 7445 (f309) The isolation time for these butterfly valves was changed from "2" seconds to "3" seconds. Technical Specification Table 3.6-1 allows five seconds with instrument delay. However, the Maximum Isolation Time column does not include instrument delay per Note "b". The instrument delay time for these valves is approximately 2 seconds. Consequently, the valve isolation time was changed to "3" seconds.
3.4 A review of the design basis events analyzed in the Ginna Station UFSAR and,the events requiring analysis as described in USNRC Reg. Guide 1.70 was performed.
The events related to this UFSAR change are:
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(a) Fires (b) Seismic Events (c) Radiological Release From a Subsystem or Component (d) Decrease in Reactor Coolant Inventory (e) Events Initiating a Safety Injection Signal 3.4.1 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a fire.
The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. No fire barriers are affected by these changes, nor is there any increase in area fire loadings.
3.4.2 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a seismic event. The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. No changes are made with respect to the seismic design of the affected penetrations.
3.4.3,
~ ~ The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to respond to a radiological release within containment. The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. Consequently, the containment isolation system is still within its design basis limits.
3.4.4 The changes as described in Section 3.3 and Attachment B do not create the potential for the affected penetrations to cause a decrease in RCS inventory (i.e., a loss-of-coolant-accident) . The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. No changes were made to capability of the parent systems (e.g., Residual Heat Removal) to perform their function. Consequently, the containment isolation system and associated parent systems remain within their design basis limits.
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3.4.5 Events which initi'ate Safety Injection also result in the need for containment isolation. The changes to the UFSAR Table do not affect the capability of the containment isolation system to perform its function.
All changes were rev'iewed to ensure continued compliance with the design basis for the containment isolation system and the Ginna Station Licensing Basis.
4.0 Preliminar Safet Evaluation 4.1 The proposed UFSAR changes will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. The changes to the UFSAR Table are to correct typographical errors, provide additional clarification, and update the table to reflect actual plant conditions. All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.
Thus, there is no change in system function, nor a reduction in system reliability. The containment isolation and parent systems will remain within their design limits.
4.2 The proposed UFSAR changes will not increase the consequences of an accident previously evaluated in the UFSAR. The modification does not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.'6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus,- the function and capability of the containment isolation system to isolate any radiological release within containment is not degraded.
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4.3 The proposed UFSAR changes will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR.
All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the changes do not degrade the performance of the containment isolation system, nor the associated parent systems.
4.4 The proposed UFSAR changes will not increase the consequences of a malfunction of equipment important to
,. safety previously evaluated in the UFSAR. The changes do not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the function and capability of the containment isolation system to isolate any radiological release from containment is not degraded. =
4.5 The proposed UFSAR changes will not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. These changes are mainly clarifications and updates to reflect current plant conditions. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.
All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. There are no adverse affects upon other systems, nor any new failure modes induced.
4.6 The proposed UFSAR changes will not create the possibility of a different type of malfunction of equipment important to safety than any previously evaluated in the UFSAR. The additions and deletions to the table are acceptable as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8, The changes do not degrade the containment isolation or associated parent systems.
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4.7 The proposed UFSAR changes will not reduce any margin of safety as defined in the basis of any technical specification. The functions and characteristics of the containment isolation system remains unchanged.
However, changes are made to valve isolation times and the valves listed for specific penetrations. These changes will be addressed in the Amendment Request to remove Table 3.6-1 from the Technical Specifications and reference this updated UFSAR table.
4.8 Based on the above analysis, that:
it has been determined (a) The margins of safety during normal operation and transient conditions anticipated during the life of the plant has not been reduced, and (b) The adequacy of structures, systems, and components provided for the prevention of accidents and for the mitigation of the consequences of accidents have not been affected.
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Attachment A Safety Analysis Revision 0 Page 14 NSL-0000-SA024 Date 9 24 90
2-13 CONTAI PENETRATIONS AND I PIPINC Position Position At Maxisans Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Normal Cold Ixaedf ate UFSAR Notes
~Sstea No. No. Shutdovn Postaccfdent~
Steam Cenerator Blind Flanges Both 0/C C (add) 5 I~ 2 Inspection/
Maintenance Fuel Transfer 29 Blind Flange Inside 0/C 6 '-13 5 2I 3 Tube Charging Line 100 370B Check Inside 6.2-18 3B to B Loop Safety 101 870B Check Outside 0 6 '-15 3B Infection Pury 889B Check Outside 0 6 '-15 3B IB Discharge Alternate 102 3838 Check Inside C 6.2-16 3B Charging to A Cold Leg Construction 103 NA Blind Flange NA NA Inside C C NA 6 '-17 5 Ffre Service Water Containment 105 8 62A Check NA Outside C 0 NA 6 '-18 3B Spray Pusy IA Reactor Coolant 106 306k Check Nh Inside 0 6 '-19 3B Puxy h Seal Water Inlet Susy h Dfs 107 1723 Diaphraga Afr Status Outside 0 0/C C FC Yes 60 6.2 20 2 charge to Waste 1728 Dfaphraga hir Status Outside 0 0/C C FC Yes 60 6 '"20 2 Holdup Tank Reactor Coolant 108 313 Motor Both Outside 0/C AI Yes 60 F 2-21 8, 6 Pump Seal Water Return Lfne and Excess Letdovn to VCT Containment 109 862B Check Nh NA Outside C Nh 6.2 22 3B Spray Pury IB end AI Falls As Is MQV Moto~rated Valve Refers to position fsuediately follovfng receipt of containment AOV Air Operated Valve MV ~ Manual Valve isolation signal and containment ventilation fsolation signal.
C ~ Closed 0 ~ Open s The maxfxaa isolation time does not include diesel start time CIS ~ Contafnment Isolation Signal 0/C Open or Closed nor instrument delay tfme.
CV Check Valve R/C ~ Red / Creen Light on Main Control Board 'efers to classes defined in Section 6.2.6.6.2.
s Notes only used to supplement Section 6.2.6.6.2.
FC ~ Falls Closed Status White Status Light, FO Fails Open SOV Solenoid Operated Valve LC ~ Locked Closed Safety Analysis Revision 1
'I Page 14a
" NSL-'.OO,OO-SA024
-13 CONTAI PENETRATIONS AND I PIPING Position Position At Maxi xixa Valve Indication Position Isolation Penetratfon Valve Valve Operator In Control Relative to Homal Cold lxxaadf ate Paver
~Satan No. No. Roon Contafnnent OHeratfon Shutdovn Postaccfdentv Failure Trip on Tfxe DFSAR Notes CIS Reactor Coolant 110a (topi 304B Check NA Nh InsMe 0 0~ C Purp B Seal NA Nh 6.2-23 3B Nater Inlet Safety 110b <bottoni 879 Globe Manual No Outside LC LC Inlectfon Test NA 6 ~ 2-15 1 Lfne Residual Hea't 720 Gate Motor R/C Inside 0 AI Renoval to B 959 Globe Alr Status 6.2-24 3B 4 ~ 7g 8 Outs fde 0/C FC 6.2-24 Cold Leg 3B 4, 1 I
Letdown to 112 200A Globe Afr R/G Inside 0/C Nonregenerative 200B Globo Alr R/G Inside 0/C C C Yes 60 6~ 225 I 10 Heat Exchanger 202 Clobe Air R/G Inside C C
C C Tes $0 $ e2 25 I 10 371 Globe Air Both Outside 0 0 C Yes 60 6~ 225 1 10 421 Globe Alr R/C Inside 0 0/C C Yes $0 6.2-25 I C Yes $ .2-25 I Safety 113 810A Check NA Outside C 6.2-15 In)ection Puxp 889A Check NA Outside C 3B IA Discharge 6.2 15 3B Standby Auxf I- 119 9104A Stop-Check Motor R/G OutsMe AI fary Feedwater 9105A No 6.2 26 Check NA Nh Inside NA Nh 6.2-26 Line to Stean Generator lh Nitrogen to 120a 846 Globe Air Both Outside C 0/C C FC Yes 60 hccuxaIlators 4623 6 ~ 2 21 3A Check NA NA Inside 0/C '/C
, C NA Nh $ .2-27 3A Pressurlxer 120b 539 Globe Air Sta'xus Outside 0/C Relief Tank to 546 Globe Manual C FC Yes 6 ~ 2-28 2 No Outside 0 0 Nh Nh F 2-24 Gas Analyxer 2 Nitrogen to 121a 528 Check NA NA Inside 0/C 6.2-29 Pressurixer 547 Globe lanual No Outside OIC 3A Relief Tank $ .2 29 3A 12 Makeup Rater to 121b 504 Dfaphragn Air Both Outside C OIC C Pressurixer 529 FC Yes 60 6 ~ 2-30 3A Check NA NA Inside 0/C OIC C NA Nh $ .2-30 Relief Tank NA 3A Conte funest 121c PT945 NA NA Outside Pressure 1819A Globe 6 2-31 2 13 Manual Outs Me 6.2 31 2 Transnftt@r PT945 Contafnnent 121d F2946 Nh NA NA Outside Nh NA Pressure 1819B Globe Manual 6.2-31 2 13 No Outside 0 0 6 2-31 2 TransxLit'tox'T946 Standby Auxfl- 123 ltopl 9104 B Stop-Check Motor Outside C C AI NA 6.2-26 fary I'eedvater 91058 Check Nh Inside C C Nh Nh 6.2-26 Line to Stean 4 Generator IB Safety Analysis Revision 1 Page 14b NSL-,OOOO-SA024 Date 10 3 90
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~ 2-13 ~
CONTAI PENETRATION~a AND PIPIhG Position Posftfon At f Max aaxa Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Homal Cold Iacaediate Pover Tilac
~Sat cmc No. ~T Rocvm, Contafnacent OEeratfon Shutdovn postaccfdcntr Trip on UFSAR Notes Failure CI8 ~Fi re Reactor Coolant 123 (button) 1600A Globe Solenoid No Outsfde 0 0/C Drain Tank to 1655 Globe Manual C Ycls NA 6.2-32 Analyzer No Outside 0 0 0 NA 6.2-32 Gas Line 1789 Diaphragca hfr Status Outside 0 0/C C Yes 60 6 '-32 Excess Letdovn 124a 743 Check Q Q Inside 0 Beat Exchanger 745 Globe hi r C C NA 6.2-33.
RIG Outside 0 C C No 6.2-33 Cooling Water 14 Supply 4 Return Postaccfdcnt 124b 1569 Dfaphragca Afr Sag>le to C Manual Outs fde LC 6 '-34 5 Fan 1571 1572 Dfsphragca Dfaphragrc Manual Manual OutsMe Outside IC, 6.2 34 5 LC 6.2-34 5 1574 Dfaphragal Manual Outsfde LC 6.2-34 5 r
Component 125 7598 Cate Hotor R/C Outside C 0 AI No 6.2-35 Cooling Water 4 fraa Reactor r Coolant Pump 1B Ccxcponent 126 759A Gate Motor R/C Outside 0 Cooling Water AI No Nh 6.2<<36 frees Reactor Coolant Pump IA Componen't 127 749A Cate Hotor Outside 0 Cooling Nater 750A Check Inside 0 C 0 AI Q 6.2-37 4 to Reactor NA C 0 NA Q 6.2-37 Coolant Pump lh Cccmponeat 128 7498 Cate Motor Cooling Water OutsMe 0 C 0 AI No Q 6 '-38 to Reactor Coolant ~
Reactor Coolant 1B 129 7508 1713 Check Check NA Inside 0 C 0 NA NA Q 6 '-38 4 NA NA Outside C 0/C C NA NA 6. 2-39 Drain Tank and Pressurizer 1786 Dfaphragal hir Sta'tus Outsfde 0 C C FC Yes NA 60 6 '-39 3A 3A Relist 1787 Dfaphragca Air S'ta'tua Outside 0 C C FC Yes 6.2-39 Tank to 1793 Dfaphragal Manual No Outside LC 0/C LC 60 3A Containnent Nh NA NA 6 ~ 2-3S 3A 12 Vent Reader Component 130 814 Gate Motor Both Outside 0 Cooling Water AI Yes 60 6.2-40 4 frcxa Reactor Support Cooling Cc~nent 131 813 Cate Hotor Both Outside 0 0 AI Cooling Nater Yes 60 6.2-40 4 to Ream'tor Support Cooling Containment Nfnf-Purge 132 7970 Butterfly hir Both Inside 0/C OIC C FC Yes 3 6.2-41 5 Exhaust 7971 Buttertly Alr Both OutsMe C 0/C C FC Yes 3 6.2-41 5
',Safety Anal'ysis Revision 1 r
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2 13 CONTAI PENETRATION<
AND I ~ PIPING Position Position At Kaxfmsus Valve Indication Posftfon Imoist fon Penetration Valve Valve Operator In Control Relative to Normal Cold Imnediate Fever Trip on Time OFSAR Notes
~zs ten No. No. Room Containment OHeratfon Shutdovn Postaccidcnt'ailure CIS ~Ff re Classs See end of table ~
Residual Beat 140 701 Gate Hotor R/C Inside 0 C AI 6.2-42 1 7i 8 Removal Pump Suctfon from A Hot, Leg Residual Heat 141 85th Cate Hotor R/0 Outside C C 0 AI No Nh 6.2-42 5 15 Removal No. 1 1813A Cate Hotor R/C Outside C 0/C C AI No NA 6.2-42 5 8 Pump Suction from Sump B Residual Heat 142 SSOB Gate Hotor R/C Outside C C AI NA 6 ~ 2-42 5 15 Removal No. 2 1813B Gate Hotor R/0 Outside C 0/C AI NA 6.2-42 5 8 Pump Suction from Su~ B Reactor Coolant 143 1003A DIa phragn Air Status Outside 0 0/C C Yes 60 '.2-43 2 Drain Tant 1003B Diaphragm Afr Status Outside 0 0/C C Yes 60 6 ~ 2-43 2 Discharge Lfne 1721 Diaphragm Alr Status Outside 0 0 C Yes 60 6.2-42 2 Reactor 201 (top) 4757 Butterfly Hanual No Outside 0 0 6.2-44 4 16 Compartment 201 (bottom) 4636 Butterfly Hanual No Outside 0 0 6.2-45 4 17 Cooling Onits h and B B Hydrogen 202 1076B Diaphragm Hanuaf No Outside LC LC LC Nh NA 6. 2-46 Recombiner 1084B Diaphragm Nanuel No Outside LC LC LC NA NA F 2-46 (Pilot and 1021181 Globe Solenoid Status Outside C C C Yes 3 6.2-46 18 Hafn) 1021351 Clobe Solenoid Status Outside C C C Yes 3 6.2-46 18 Containment 2Q3a F2947 NA NA NA Outside NA NA NA 6.2-47 2 13 Pressure PT948 NA Nh Nh Outside NA Nh NA 6.2 47 2 13 Transmitter 1819C Clobe Hanua 1 No Outs Me 0 0 0 6,2 47 2 PT947 and PT948 1819D Globe , Hanual No Outs Ide 0 0 0 6 ~ 2 47 2 PostaccMent 203b 1563 Diaphragm Hanual No Outside 6.2 48 Air 8~le to B 1565 Diaphragm Hanual No Outside 6.2-48 Fan 1566 Diaphragm Hanuel No OutsMe 6.2 48 1568 Diaphragm Hanual No Outside 6.2 48 Purge Supply 204 Blind Flange NA Inside C 0 Nh 6.2 49 2, 19 Duct 5869 Butterfly Afr Both Outside C 0/C FC 6.2 49 19 Hot Leg Loop 205 955 Clobe Air St&'tus Inside C C C Yes NA 6' 50 Sample 956D Globe Hanual No Outside 0 0 0 NA NA 6 ~ 2 50 966C Globe Air Status Outside C C C Yes 60 6.2-50 Pressurizer 206a (top) 953 Globe Alr Status Inside C C C Yes NA 6.2 51 Liquid Space 956E Clobe Manual Outside 0 0 0 6.2-51
~le 966B Globe Alr No S'ta'tus Outside C C C Nh Yes NA 60 6 ~ 2 Sl A Stean 206b (bottom) 5733 Globe Hanual No Outside 0 Nh NA 6~2 52 Cenerator 5735 Globe Alr Status Outsfde C FC 60 6.2 52 Sample Pressurizer 207a (top) 951 Globe Alr Status Inside C C C FC Yes Nh 6.2 S3 1 Steam Space 956F Globe Hanuel No Outside 0 0 0 NA NA NA 6.2-53 I Sample 966A Globe Air Status Outside C C C FC Yes 60 6~ 253 1 ss 3
'Safety Analysis Revise.on 1 Page 14d
'SL-0000-SA024
l 2-13 CONTAIN PENETRA TIGHT AND I N PIPING Position Posftfon At Maxisum Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Normal Cold irumdfate Power Trip on Time UFSAR Notes Mo. No. Roon Containment OBeratfon Shutdovn Postaccfdent'aflur* CIS ~F( re Cla ass See end of table a B Steam 207b (bottom) 5734 Globe Manual No Outside C Nh 6.2-54 Generator 5736 Globe Air Status Outside C 60 6.2-54 Sample Reactor 209 (top) 4635 Butterfly Manual No Outside 6.2-44 16 Cocpartment 209 (bottom) 4758 Butterfly Manual No Outside 6.2-45 17 Cooling Units h and B Oxygen Makeup 210 1080A Globe Manual No Outside LC LC LC Nh 6.2-55 to h 4 B 102145 Clobe Solenoid S'tatus Outside C C C Tes 3 6.2-55 14 Reconbiners 1021481 Globe Solenoid Sta'kus Outs fde C C ~ C Tes 3 6.2 55 14 102158 Globe Solenoid Status Outside C C C Tes 3 6.2-55 14 1021531 Globe Solenoid S'tatus Outside C C C Yes 3 6 '-55 14 Purge Exhaust 300 Nh Blind Flange NA NA Insfde 0 NA 6 '-56 2, 19 Duct 5479 Butterfly Air Both Outs ide OIC Yes F 2-56 19 Auxiliary Steam 301 6151 Globe Manual Outs ide NA 6.2-57 Supply to 6165 Globe Manual Outside NA 6.2-57 Containment Auxiliary Steam 303 6152 Globe Manual No Outside 6.2-57 Condensate 6175 Globe Manual No Ou'teide 6.2-57 Return A Hydrogen 304 1076A Diaphragm Hanual No Outside LC LC LC Nh 6.2-58 Recoebiner 108(A Diaphragm Manual No Outside LC LC LC Nh 6.2-58 (Pilot and 1020551 Globe Solenoid Status Outside C C C Tes 6.2-54 18 Nein) 1020951 Globe Solenoid S'ta'tus Outside C C C Yes 6.2-58 18 Contafnment Alr 305a (bottom) 1596 Globe Manual No Outside NA 6.2 59 2 Saxple Out 1597 Diaphragm Air Both Outside Tes 6 ~ 2 59 2 Containment Air 305b (top} 1598 Diaphragm Air Both Outsfde Tes 60 6.2 60 3A Sarpf e Inlet 1599 Diaphragm Alr Both Outside Tes 60 6' 60 3h Containment Alr 305C 1554 Diaphragm Manual No Outside 6 ~ 2 61 Sa=ple 1556 Die ph rage Manual No Outside 6.2 61 Postaccident 1557 Diaphragm Manual No Outside 6.2 61 1559 Diaphragm Hanual No Outside 6.2-61 1560 Diaphragm Manual No Outside 6.2 61 1562 Diaphragm Manual No Outside 6.2 61 Fire Service 307 9227 Cate Afr Both Outside Tes 60 6.2 62 Mater 9229 Check NA Nh Insfde Nh Nh $ .2-62 Service Mater 308 4629 Butterfly Manual Outside 0/C 6.2 63 to h Fan Cooler Nini-Purge 309 7445 Butterfly hir Both Outsfde OIC Yes 6,2 64 Supply 7474 Butterfly Alr Both Inside OIC Tes 6.2 64 Service Air to 310a (bottcm) 7141 Cata Manual No Outside 0/C 6 ~ 2-65 3A Containment 7226 Check Nh Nh Inside OIC 6.2 65 3A Safety Analysis Revision E
Page 14e
-NSL-0000-SA024 Date 10 3 90
-13 CONTAINNEN PENETRATIONS AND I ON PIPING Position Posftfon ht f Hex sum Valve Indicatfon Position Isolation Penetration Valve Valve Operator In Cont rol Relative to Normal Cold irradiate Trip on Time VFSAR Notes
~Sat em No. Mo, Room Contain>nant OEeratfon Shutdovn Postaccfdent'over Failure CI8 ~Ff re Instrument Air 310b (top) 5392 Globe Both Outside 0 C Yes 60 6.2 66 3A to Contafnmnnt 5393 Check NA Inside 0 C NA IR 6.2-66 3A Service Mater 311 4630 Butterfly Manual Outside 0/C from B Fan 6.2-63 16 Cooler Service Mater 312 4642 Butterfly Hanual Outside 0/C . NA 6.2-63 to D Fan Cooler ~ 17 Leakage Test 313 NA Blind Flange Inside Depressurira- 7444 Butterfly Nh Hotor NA Sta'tus Outsfde C NA NA Q 6.2-67 5 t ion C Al Yes Q 6 ~ 2 67 5 19 Service Mater 315 4643 Butterfly Hanuel Outside 0/C From C I'an > NA NA NA 6.2-63 4 16 Cooler Service Mater 316 4628 Butterfly Hanual No Outside 0/C to B Fan Cooler NA 6.2-63 4 17 Leakage Test 317 NA Blind Flange NA NA Inside Q Supply 7443 Butterfly Hotor Sta'cus NA 6.2 68 5 Outside AI Yes 6.2"68 5 19 Deadveight 31d NA Tes'ter lR NA 20 Service Mater 319 4627 Butterfly Hanual No Outside 0/C from A Fan 6 ~ 2-63 4 16 Cooler Service Mater 320 46li Butter fly Manual No Outside 0/C to C Fan Cooler NA 6.2-63 17 A Steam 321 5701 Globe Hanua1 Outside Generator 5738 Globe Air No Status Outside 0
0 0 NA Q Q 6.2-6S Blovdovn 0/C C FC Yes 60 6 ~ 2 69 B Steam 322 5702 Globe Manual Outside Generator 5737 Globe hir No Status Outside 0 NA Q 6.2-70 Blovdovn 0/C Yes 60 6270 Servfca Mater 323 4644 Butterfly Hanual No Outside fran D I'an 0/C Q 6.2-63 16 Containment Cooler Demineralized Mater to 324 l 4 1d Globe Air Both Outside C 0/C C Yes 60 6. 2-71 5 8l 1 9 Check NA NA Inside C 0/C C NA lVL 6 ~ 2-71 5 Contafment 332a PT944 NA NA NA Outside Q Pressure IVL Nh NA NA NA 6.2-72 2 13 PTS49 NA NA NA Outside IR NA NA Nh Nh IVL 6.2-72 2 Transmitters PT950 Q Nh NA Outside NA NA NA N1L NA IR 6.2-72 13 PT944, F2949> 1819E Globe 2 13 Hanual No Outside 0 0 0 NA . NA NA 6.2-72 2 and PT950 Globe 1419F 18190 Globe Manual Manual No No Outside Outside 0
0 0
0 0 NA NA NA 6 '-72 2 0 NA Nh Nh 6.2-72 2 Safety Analysis Revision 1 Page 14f
. NSL-0000-SA024 Date 10 3 90
2 13 CONTAI 'C PENETRATIONS AND IS ION PIPING Position Position At Maxi sans Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relatfve to Normal Cold Ismedfate Trip on Time CFSAR Notes
~Sstem No. No. Room Contafnvent OBeratfon Shutdovn Postaccfdent'oser Failure CIS ~Ff re Classv See <<nd ot table s Hydrocen 332c 921 Cate Solenoid Both Outside C C C yes 6.2 74 21 Monitor 922 Cate Solenoid Both Outside C C C yes 6.2 74 21 Instrumentatfon 923 Cate Solenoid Both Outside C C C yss 6.2 74 21 Lines 924 Cate Solenoid Both 0 teide C C C Tes 6.2 74 21 Main Steam from 401 3505A Cate Motor R/0 Outside C 0 AI No 6.2 75 11 A Steam 3507 Cate Manual No Outsfde C 0 NA NA 6.2 75 11 Generator 3517 3519 Swine Check Check Air NA R/C NA Outside Outside C
C C
C AI NA No NA 6.2 75 6 ' 75 ll ll 3521 Cate Manual No Outside 0 0 NA NA 6.2 75 ll Main Steam B Steam Iron 402 3504A 3506 Cate Cate Motor Manual R/0 No Outside Outside C
0 C
C 0
0 AI NA No NA 6.2 75 6.2 75 ll ll Generator 3516 Suing Check Air R/0 Outside 0 C C AI No 6.2 75 11 3518 3520 Check Cate NA Manual NA No Outside Outsfde 0
0 C
0 C
0 NA NA NA NA 6 ' 75 6.2"75 ll ll Fcedvater Line 403 3993 Check NA NA Outside 0 C C NA NA 6.2 76 11 to A Steam 3995 Clohe Manual No Outside 0 0 0 NA NA 6.2-76 11 Generator 4008C Check NA NA Outside C C 0 NA NA 6.2 76 11 4083 Check NA NA Outside C C 0 NA NA 6.2-76 11 4885 Globe Manual No Outside 0 0 0 NA NA 6.2-76 11 4011 Globe Manual No Outside 0 0 0 NA NA 6.2-76 11 1'eedvater line 404 3992 Check NA NA Outside 0 C C NA 6.2-76 11 to B Steam 3994 Clohe Manual No Outside 0 0 0 NA 6.2-76 11 Generator 40000 4084 Check Check NA NA NA NA Outside Outside C
C C
C 0
0 NA NA 6.2-76 6.2-76 ll 11 4806 Globe Manual No Outside 0 0 0 'NA 6.2-76 11 4012 Clohe Manual No Outside 0 0 0 NA 6.2-76 11 Personnel Hatch 1080 Both 0/C NA 3.8-31 Equfpcent Hatch 2000 0/C 3.8-30 Safety Analysis Revision Page 14c4 NSL-0000-SA024 Date 10 3 90
13 CONTAINNEN PENETRATIONS'ND IS N PIPING Notes (I) penetration Number 2 was added as a result of ENR 4998 to facflftate steam generator maintenance activities during mfd-loop operation. This penetration is closed by a doubf~asketed blind flange on both ends) however, only one oI the two Ilanges are necessary for containment Integrity purposes.
(2) Thfs penettatfon is provided with redundant seals and fs closed during normal opezatfon.
(3) The end of the tuel transfer tube inside containment fs closed by a doubf~asketed blind flange, to prevent leakage or spent fuel pit. water fnto the contafnment during plant operation.
This flange also serves as protectfon against leakage Izom the containment following a losswfwoofant accident.
(4) This is a closed system outside containment. Verification of this closed system as a contafnment isolation boundary ls accomplished via inservice and/or shutdown leakage checks.
This applfes to the following systems: Safety In)ection, Containment Spray, Charging, Residual Heat Removal, and Component Cooling Hater.
(5) This penetration was only utilized during fnltfal plant construction and fs maintained fnactfvate.
(6) A second isolation barrier is provided by the volume control tank and connectfng piping per letter from D.D. DfIanni, USNRC, to R.N. Kober, RG(E, dated January 30, 1987. This barrier is not required to be tested.
IOCFR50, Appendix J containment leakage testing fs not required per L.D. white Jr. letter to D.L. Fiemann, USNRC, dated September 21, 1978.
(8) MOVs 1813A, 1813B, 720, and 701 are maintained closed at power with their breakers locked off.
(9) This valve receives a contafnsent isolation sfgnal) however, credit is not taken for this function. Therefore, this valve is not sub)ected to J lea'kage testing, nor does ft require a maximum isolation tfme. IOCFR50, Appendix (10) Containment Isolation Signals were added to AOVs 200A. 2008, and 202 since AOV 427 falls open on loss pz power. The Isolation signal for these three valves ls relayed From AOV 427.
(11) The Main Steam, Main Feedwater, and Standby Auxiliary Feedwater isolation valves are not considered contafnmsnt fsolatfon valves. The containsmnt boundary fs the steam generator secondary side and tubes.
I (12) Manual valves 547 and 1793 are locked closed and leak tested to provide equivalent protection for GDC 56 and 57 (see UFSAR 6.2.4.4.1, Class 3A). k (13) The pressure transmitter assexbly, by its design, provides a containment pressure boundary. The fntegrity of this boundary is verified by annual leakage tests.
(14) Operations fs instructed to manually close AOV 745 following a Containment Isolation Signal until an automatic signal 1s installed through the necessary modfficatfon.
(15) Sump ]ines are fn operation and filled with Ifufd foffowfng an accident) therefore. 10CFR50, Appendix J leakage testing is not required for this penetratfon. See L.D. Nhfte Jr. letter to D.L. Ziemann, USNRC, dated September 21, 1978.
(16) This manual valve fs sub)ected to an annual hydrostatic leakage test and fs not sub]ect to 10CFR50. Appendix J leakage testing.
The service Nater System operates at a higher pressure than the contafnment accident pressure and fs missile protected inside containment. Therefore, this manual valve is used for flow control only and fs not sub]ected to 10CFR50 Appendix J leakage testing. See letter from J.E. Mafer, RG(E. to D.M. Czutchfield, hRC, dated August 30, 1982.
(18) Thfs solenoid valve is maintained Inactive in the closed position by removal of fts DC control power.
(19) The Ilanges and associated double seals provide contafnment Isolation and ensure that contafnment Integrity fs maintained Ior all modes of operation above cold shutdown. Nhen the Ilanges are removed, cold shutdovn containment integrity ls provided by the valves. These valves do not require 10CFR50, Appendix J leakage testing, nor a maximum isolation time.
(20) This penetration is decozcdssfoned and weldeci shut.
(21) Acceptable fsolatfon~pabflfty is provided For fnstrument lines by two isolation boundaries outside containment. One of the boundaries outside containment is a Seismic Class I closed system which fs sub)ected to Type C leakage testing under 10CFR50, Appendix J.
Safety Analysis Revision 1 Page 14h NSL-0000-SA024
t t 'I y 0
Attachment B Safety Analysis Revision 0 Page 15 NSL-0000-SA024 Date 09 24 90
The blanks or "-" within columns were Typographical clarification only. No replaced with "NA". technical change.
- 2. (1) The blanks or "-" for the Position (1) (2) The valve position and "NA" are At columns were replaced with the more representative of the penetration representative position; (2) The "No" configuration. In addition, listed under Position Indication in consistency is maintained within the Control Room was replaced with "NA". table. No technical change.
- 3. The "AI" or blank for the Power Failure The "NA" is more representative of the column for manual valves was replaced penetration configuration since a with "NA". manual valve does not receive any motive power. No technical change..
- 4. The "NA" is more representative of the was replaced with "NA". penetration configuration. In addition, consistency is maintained within the table. No technical change.
- 5. The blank or "No" for Maximum Isolation The "NA" is more representative of the Time was replaced with "NA". penetration configuration. In addition, consistency is maintained within the table. No technical change.
Safety Analysis Revision 0 Page 16 NSL-0000-SA024 Date 09 24 90
~ ~ J ~
Added "Cold" to Position At Shutdown Minor clarification for consistency column heading. with Technical Specifications. No technical change.
- 2. (1) Added "Immediate" to Position At (1) (2) Clarification of column since Postaccident column heading; (2) Added valve position can be potentially Note "a" changed during post accident recovery operations. Column now provides clear definition of penetration configuration following receipt of a CIS.
- 3. (1) (2) Column did not provide any table; (2) Deleted definitions for "W" information relevant to table. Fluid and "G" from table Legend. type can be inferred from stem
~S column.
4 Column did not provide any information associated Note "c" from table. relevant to table.
- 5. Added definitions for "AOV", "CV", Correction of typographical omission.
"MOV", "MV", and "SOV" to table Legend. No technical change.
- 6. (1) Modified Position Indication in (1) (2) The type of control room Control Room column to reflect type of indication is more representative of indication instead of "Yes" and "No"; the system configuration. This is a (2) Added definition for "R/G" and clarification only. No technical "Status" to table Legend. "Both" change.
indicates that a red/green light and status light exists.
- 7. Moved Table Heading Notes "a", "b", "c", Minor format change only. No technical and "d" to first page of table. change.
Safety Analysis Revision 0 Page 17 NSL-0000-SA024
~ c
- 8. (1) Renamed Note "a" to "b"; (2) Added (1) (2) Minor clarification- only. Note "nor instrument delay time" to end of is now consistent with Standard Review note. Plan Section 6.2.4. No technical change.
- 9. Renamed Note "b" to "c". No technical change.
- 10. Deleted "Line" from ~S stem column No technical change.
heading.
Added Note "d" to Notes column. Minor clarification only. The Notes column is now only used to supplement the UFSAR text which provides more information. No technical change. =
Safety Analysis Revision 0 Page 18 NSL-0000-SA024 Date 09 24 90
~ l I ~
Penetration 2 Added penetration and This spare penetration was modified to necessary information to the table. provide access for steam generator inspection and maintenance cabling during refueling outages to enhance containment closure during midloop operations. No new valves were added.
- 2. Penetration 29 (1) Global Note 1; (2) (1) (2) No technical change.
Added Note 2.
- 3. Penetration 100 (1) Global Notes 1, 2, (1) (2) No technical change. (3) Update and 4; (2) Added Note 4; (3) Changed for better representation of system Position At Immediate Postaccident from configuration since the Charging System "0/C" to "C". is isolated upon receipt of a SI signal.
4 ~ Penetration 101 (1) Global Notes 1, 2, (1) (2) No technical change. (3) 4, and 5; (2) Added Note 4; (3) Added Correction of typographical omission.
"3B" under Class for valve 889B; (4) No technical change. (4) Valves now in Reordered penetration valves. numeric order. No technical change.
- 5. Penetration 102 (1) Global Notes 1, 2, (1) (2) No technical change.
4, and 5; (2) Added Note 4.
- 6. Penetration 103 Deleted valve 5129 Replaced Note of "No longer in use" to (entire line in table) and replaced with reflect accurate configuration status Blind Flange. of Blind Flange. The use of the Blind Flange is consistent with the previously listed locked-closed manual valve.
Safety Analysis Revision 0 Page 19 NSL-0000-SA024
~ c > ~
- 7. Penetration 105 (1) Global Notes 1, 2, (1) (2) No technical change.
and 4; (2) Added Note 4.
- 8. Penetration 106 (1) Global Notes 1, 2, (1) (2) No technical change. (3) Minor and 4; (2) Added Note 4; (3) Changed clarification only. No technical "supply" to "Inlet" under ~S stem. change.
- 9. Penetration 107 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for both valves; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration.
"0/C" for both valves.
- 10. Penetration 108 (1) Added "and Excess (1) Consistency with Technical Letdown to VCT" under ~Sstem; (2) Specification Table 3.6-1. (2) Minor Changed Position Indication In Control clarification only. No technical Room from "Yes" to "Both"; (3) change. (3) Update for better At Cold Shutdown from "0" to Changed'osition representation of system configuration "0/C"; (4) Added Note 4; (5) Added Note since this line may or may not be used
- 6. during cold shutdown conditions. (4)
(5) No technical change.
Penetration 109 (1) Global Notes 1, 2, (1) (2) No technical change.
and 4; (2) Added Note 4.
- 12. Penetration 110a (1) Global Notes 1, (1) (2) No technical change.
2, and 4; (2) Added Note 4.
Safety Analysis Revision 0 Page 20 NSL-0000-SA024 Date 09 24 90
~ 4 ~
- 13. Penetration 110b (1) Global Notes 3 (1) (2) No technical change. (3) and 4; (2) Added Note 4; (3) Changed Consistency with Ginna Administrative Position At Cold Shutdown and Position Control.
At Immediate Postaccident from "C" to nLCss
- 14. Penetration 111 (1) Added Note 7 to (1) Consistency with Technical both valves; (2) Added Note 8 to valve Specifications. (2) (3) No technical 720; (3) Added Note 4 to both valves; change. (4) Minor clarification only.
(4) Changed Position Indication In No technical change. (5) Valve Control Room from "Yes" to "R/G" for MOV receives containment isolation signal 720; (5) Added valve 959 and necessary and was previously missing from the information. table.
- 15. Penetration 112 (1) Deleted valves (1) (2) Present configuration status; 204A and 821 (entire line in table) and the three new valves enable explicit replaced with valves 200A, 200B, and compliance with GDC 55 vs. the use of 202; (2) Added valve 427 and necessary redundant outboard isolation valves.
information; (3) Changed Position The 200A, 200B, 202, and 427 valves Indication In Control Room from "Yes" to have been successfully tested. (3)
"Both" for valve 371; (4) Changed Minor clarification only. No technical Position At Immediate Postaccident from change. (4) Update for better "0" to "C" for valve 371. representation of system configuration since letdown is isolated upon receipt of a SI signal.
Penetration 113 (1) Global Notes 1, 2, (1) (2) No technical change. (3) and 4; (2) Added Note 4 to both valves; Valves now in numeric order. No (3) Reordered penetration valves. technical change.
1 Safety Analysis Revision 0 Page 21 NSL-0000-SA024 Date 09 24 90
- 17. Penetration 119 (1) Global Notes 1, 2, (1) No technical change. (2) Minor 4, and 5; (2) Changed Position clarification only. No technical Indication In Control Room from "No" -to change. (3) Valves now in numeric "R/G" for valve 9704A; (3) Reordered order. No technical change.
penetration valves.
- 18. Penetration 120a (1) Global Notes 1, (1) No technical change. (2) 2, and 4 for valve 8623; (2) Changed Correction of typographical error. No valve 846 from "Gate" to "Globe"; (3) technical change. (3) Minor Changed Position Indication In Control clarification only. No technical Room from "Yes" to "Both" for valve 846; change. (4) Update for better (4) Changed Position At Normal 0 eration representation of system configuration.
from "0/C" to "C" for valve 846; (5) This valve remains closed unless the Reordered penetration valves. accumulator nitrogen blanket pressure decreases. (5) Valves now in numeric order. No technical change.
- 19. Penetration 120b (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for valve 539; (2) Changed better representation of system Position At Normal 0 eration from "0/C" configuration. (3) No technical to "C" for valve 539; (3) Global Notes 3 change.
& 4 for valve 546.
- 20. Penetration 121a (1) Global Notes 1, (1) No technical change. (2) 2, and 4 for valve 528; (2) Changed Correction of typographical error. No valve 547 from "Diaphragm" to "Globe"; technical change. (3) Consistency with (3) Changed Position At Immediate Ginna Administrative Control. (4)
Postaccident from "0" to "LC" for valve Update for better representation of 547; (4) Changed Position At Normal system configuration. No technical change. (5) No technical change. (6)
(5) Global Notes 3 and 4 for valve 547; Correction of typographical error. No (6) Deleted reference to "old" Note 9; technical change. (7) No technical (7) Added Note 12 to valve 547. change.
Safety Analysis Revision 0 Page 22 NSL-0000-SA024
- 21. Penetration 121b (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) (3) Update for "Both" for valve 508; (2) Changed better representation of system Position At Normal 0 eration from "0/C" configuration. (4) No technical to "C" for valve 508; (3) Changed change. (5) Valves now in numeric Position At Normal 0 eration from "C" to order. No technical change.
"0/C" for valve 529; (4) Global Notes 1, 2, and 4 for valve 529; (5) Reordered penetration valves.
- 22. Penetration 121c (1) Global Note 1 for (1) (2) No technical change. (3)
PT945; (2) Global Notes 3 and 4 for Correction of typographical omission.
valve 1819A; (3) Added "Gate" under No technical change.
8 9
- 23. Penetration 121d (1) Global Note 1 for (1) (2) No technical change.
PT946; (2) Global Notes 3 and 4 for valve 1819B.
- 24. Penetration 123 (bottom) (1) Added (1) Consistency with Technical "to" before "Gas Analyzer Line" under Specification Table 3.6-1. (2) No
~sstem; (2) Global Notes 3 and 4 for technical change. (3) Correction of 1655; (3) Changed valve 1789 from typographical error. No technical "Globe" to "Diaphragm"; (4) Changed change. (4) Minor clarification only.
Position Indication In Control Room from No technical change. (5) Update for "Yes" to "Status" for valve 1789; (5) better representation of system Changed Position At Normal 0 eration configuration since this line remains from "0/C" to "0" for valve 1789; (6) open. (6) Valve receives containment Added valve 1600A; (7) Reordered isolation signal and was previously penetration valves. missing from the table. (7) Valves now in numeric order. No technical change.
Safety Analysis Revision 0 Page 23 NSL-0000-SA024 Date 09 24 90
- 25. Penetration 123 (top) (1) Global Notes (1) No technical change. (2) Minor 1, 2, 4, and 5; (2) Changed Position clarification only. No technical Indication In Control Room from "No" to change.
"R/G" for valve 9704B.
- 26. Penetration 124a (1) Global Notes 1, (1) No technical change. (2) Update 2, and 4 for valve 743; (2) Changed for better representation of system Position At Immediate Postaccident from configuration. Operations is "0" to "C" for valve 743; (3) Changed instructed to manually isolate this Position Indication In Control Room from line following receipt of a containment "Yes" to "R/G" for valve 745; (4) isolation signal. (3) Minor clarification only. No technical for valve 745; (5) Changed Maximum change. (4) (5) Correction of Isolation Time from "60" to "NA" for typographical error. See letter from valve 745; (6) Changed Position At Cold R. Mecredy, RG&E, to A. Johnson, NRC, Shutdown from "0" to "C" for valve 745. dated July 9, 1990. (6) Update representation of system for'etter configuration since excess letdown is not operational during cold shutdown conditions.
Penetration 124b (1) Added "to" before (1) Minor clarification. No technical
- 27. "C Fan" under ~astern; (2) Added change. (2) Correction of typographical omission. No technical four valves; (3) Changed Position At change. (3) (4) Consistency with Ginna Cold Shutdown from "C" to "LC" for all Administrative Control. (5) No four valves; (4) Changed Position At technical change.
Immediate Postaccident from "0/C" to "LC" for all four valves; (5) Global Notes 3 and 4.
Safety Analysis Revision 0 Page 24 NSL-0000-SA024 Date 09 24 90
- 28. Penetration 125 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/G"; (2) Changed Position At Cold better representation of system Shutdown from "0" to "C"; (3) Added Note configuration since RCPs are not
- 4. operating during cold shutdown conditions. (3) No technical change.
- 29. Penetration 126 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change; (2) Update for "R/G"; (2) Changed Position At Cold better representation of system Shutdown from "0" to "C"; (3) Added Note configuration since RCPs are not
- 4. operating during cold shutdown conditions. (3) No technical change.
- 30. Penetration 127 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/B" for valve 749A; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration since RCPs are not "C" for valve 749A; (3) Global Notes 1, operating during cold shutdown 2, and 4 for valve 750A; (4) Changed conditions.. (3) No technical change.
Maximum Isolation Time from "60" to "NA" (4) Correction of typographical error.
for valve 749A. No technical change.
- 31. Penetration 128 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/B" for valve 749B; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration since RCPs are not "C" for valve 749B; (3) Global Notes 1, operating during cold shutdown 2, and 4 for valve 750B; (4) Changed conditions. (3) No technical change.
Maximum Isolation Time from "60" to "NA" (4) Correction of typographical error.
for valve 749B. No technical change.
Safety Analysis Revision. 0 Page 25 NSL-0000-SA024
- 32. Penetration 129 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Minor valve 1787; (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valves 1786 and 1787; (3) representation of system configuration.
Changed Position at Cold Shutdown from (4) (5) No technical change. (6) Minor "0" to "C" for valves 1786 and 1787. (4) clarification. No technical change.
Global Notes 1, 2, and 4 for valve 1713; (7) Correction of typographical (5) Global Notes 2, 3, and 4 for valve omission. No technical change. (8) 1793; (6) Deleted "MOV 1793 used for Correction of typographical omission.
long-term isolation" under Notes and No technical change. (9) Valves now in replaced with Note 12; (7) Added "NA" numeric order. No technical change.
>>93:
Added "Outside" under Position Relative To Containment for valve 1793; (9)
Reordered penetration valves.
- 33. Penetration 130 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Correction of "Both"; (2) Corrected associated valve typographical error. No technical number to 814. change.
- 34. Penetration 131 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Correction of "Both"; (2) Corrected associated valve typographical error. No technical number to 813. change.
Safety Analysis Revision 0 Page 26 NSL-0000-SA024
~ 'I 0
0
- 35. Penetration 132 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "2" to "3" for both Specifications. Valve design allows valves; (2) Changed Position At Normal closure as rapid as 2 (two) seconds.
Minimum closure time required by (3) Changed Position At Cold
"/'971; Technical Specifications is 5 (five)
Shutdown from "C" to "0/C" for both seconds with instrument delay. (2) (3) valves; (4) Changed Position Indication Update for better representation of In Control Room from "Yes" to "Both" for system configuration. Mini-Purge both valves. system only designed for use during shutdown conditions. (4) Minor clarification only. No technical change.
- 36. Penetration 140 (1) Added Note 6; (2) (1) Consistency with Technical Added Note 7; (3) Changed Position Specification Table 3.6-1 Note 20. (2)
Indication in Control Room from "Yes" to No technical change. (3) Minor IIR/Gll clarification only. No technical change.
- 37. Penetration 141 (1) Deleted valve 851A (1) Valve 851A does not meet the (entire line in table); (2) Added valve selection criteria of 10CFR50 Appendix 1813A and necessary information; (3) J, Section IIH, items .1 through 4.
Changed Position Indication In Control Therefore, valve was deleted from Room from "Yes" to "R/G" for valve 850A; table. (2) Valve 1813A was previously (4) Added Note 8 to valve 1813A. missing from table. (3) Minor clarification only. No technical change. (4) No technical change.
Safety Analysis Revision 0 Page 27 NSL-0000-SA024
l
- 38. Penetration 142 (1) Deleted valve 851B (1) Valve 851B does not meet the (entire line in table); (2) Added valve selection criteria of 10CFR50 Appendix 1813B and necessary information; (3) Jg Section IIH, items 1 through 4.
Changed Position Indication In Control Therefore, valve was deleted from Room from "Yes" to "R/G" for valve 850B; table. (2) Valve 1813B was previously (4) Added Note 8 to valve 1813B. missing from table. (3) Minor clarification only. No technical change. (4) No technical change.
- 39. Penetration 143 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for all three valves; (2) better representation of system Changed Position At Normal 0 eration configuration. (3) Valves now in from "0/C" to "0" for valves 1003A and numeric order. No technical change.
1003B; (3) Reordered penetration valves.
- 40. Penetration 201top Global Notes 3 and No technical change.
4.
- 41. Penetration 20lbottom Global Notes 3 No technical change.
and 4.
Safety Analysis Revision 0 Page 28 NSL-0000-SA024
- 42. Penetration 202 (1) Changed valves (1) Correction of typographical error.
1076B and 1084B from "Globe" to No technical change. (2) Consistency "Diaphragm"; (2) Changed Position At with Ginna Administrative Control. (3)
Normal 0 eration Cold Shutdown No technical change. (4) Correction Immediate Postaccident from "C" to "LC" of typographical omission. No for valves 1076B and 1084B; (3) Global technical change. (5) Update to new Notes 3 and 4 for valves 1076B and valve number only. No technical 1084B; (4) Added "No" under Position change. (6) Correction of Indication in Control Room for valves typographical omission. No technical 1076B and 1084B; (5) Changed Valve No. change. (7) (8) Update for better for IV-3B and IV-5B to 10211S1 and representation of system configuration.
10213S1, respectively; (6) Added Valves receive containment isolation "Status" under Position Indication in signal. (9) Correction of Control Room for valves 10211S1 & typographical error. No technical 10213S1; (7) Changed Position At Power change. (10) Valves now in numeric Failure from "-" to "FC" for valves order. No technical change.
1021181 and 1021381; (8) Changed ~Tri on CIS from "No" to "Yes" for valves 10211S1 and 10213Sl; (9) Changed Maximum Isolation Time from "NA" to "3" for 10211S1 and 10213Sl; (10) Reordered penetration valves.
- 43. Penetration 203a (1) Included separate (1) Minor clarification there are two lines in table for valves 1819C and valves. No technical change. (2) (3) 1819D; (2) Added "Outside" to Position Correction of typographical omission.
Relative to Containment for PT947 and No technical change. (4) (5) No PT948; (3) Added "Globe" under Valve technical change.
~T e for valves 1819C and 18190; (4)
Global Note 1 for PT947 and PT948; (5)
Global Notes 3 and 4 for valves 1819C and 1819D.
Safety Analysis Revision 0 Page 29 NSL-0000-SA024
jÃo+g)
- 44. Penetration 203b (1) Global Notes 3 (1) No technical change. (2) and 4; (2) Added "Diaphragm" under Valve Correction of typographical omission.
~T e for all four valves; (3) Changed No technical change. (3) Consistency Position At Cold Shutdown and Position with Ginna Administrative Control.
At Immediate Postaccident from "C" to "LC" for all four valves.
- 45. Penetration 204 (1) Added Note 2 to (1) (2) No technical change. (3) Minor Blind Flange; (2) Global Note 1 for clarification only. No technical Blind Flange; (3) Changed Position change. (4) (5) Update for better Indication in Control Room from "Yes" to representation of system configuration.
"Both" for valve 5869; (4) Changed Penetration only used during cold position At Normal 0 eration from "0/C" shutdown conditions. Mini-purge system to "C" for valve 5869; (5) Changed now used in place of purge system. (6)
Position At Cold Shutdown from "0" to The Blind Flange acts as the isolation "0/C" for 5869; (6) Changed Maximum boundary. Therefore, no isolation'time Isolation Time from "5" to "NA" for is required for the valve. (7) No valve 5869; (7) Added Note 19. technical change.
- 46. Penetration 205 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Valve valve 966C; (2) Added valve 955 and receives containment isolation signal necessary information; (3) Changed and was previously missing from the Position Indication in Control Room from table. (3) Minor clarification only.
"Yes" to "Status" for valve 966C; (4) No technical change. (4) Update for Changed Position At Normal 0 eration and better representation of system Position At Cold Shutdown from "0/C" to configuration. Sampling system "C" for valve 966C; (5) Global Notes 3 normally isolated. (5) No technical and 4 for valve 956D; (6) Reordered change. (6) Valves now in numeric penetration valves. order. No technical change.
Safety Analysis Revision 0 Page 30 NSL-0000-SA024 Date 09 24 90
49 Penetration 207a (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Valve valve 966A; (2) Added valve 951 and receives containment isolation signal necessary information; (3) Changed and was previously missing from the Position Indication in Control Room from table. (3) Minor clarification only.
"Yes" to "Status" for valve 966A; (4) No technical change. (4) Update for Changed Position At Normal 0 eration and better representation of system Position At Cold Shutdown from "0/C" to configuration. Sampling system "C" for valve 966A; (5) Global Notes 3 normally isolated. (5) No technical and 4 for valve 956F; (6) Reordered change. (6) Valves now in numeric penetration valves. order. No technical change.
- 50. Penetration 207b (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Minor valve 5736; (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) (4) Update for better "Status" for valve 5736; (3) Changed representation of system configuration.
Position At Normal 0 eration from "0/C" (5) No technical change. (6) Valves to "0" for valve 5736; (4) Changed now in numeric order. No technical Position At Cold Shutdown from "0/C" to change.
"C" for valve 5736; (5) Global Notes 3 and 4 for 5734; (6) Reordered penetration valves.
- 51. Penetration 209top (1) Global Notes 3 (1) No technical change. (2) Valve and 4; (2) Reordered penetration valves. order now consistent with other penetrations. No technical change.
- 52. Penetration 209bottom (1) Global (1) No technical change. (2) Valve Notes 3 and 4; (2) Reordered penetration order now consistent with other valves. penetrations. No technical change.
Safety Analysis Revision 1 Page 32 NSL-0000-SA024
- 53. Penetration 210 (1) Added "A & B" (1) Consistency with Technical before "Reoombiners" under ~3 stem; (2) Specification Table 3.6-1. (2) Minor Added Position Indication in Control clarification only. No technical Room to "Status" for all solenoid change. (3) Correction of valves; (3) Added "Yes" under ~Tri on typographical omission. No technical CIS for all solenoid valves; (4) Added change. (4) Valve receive containment valves 10214S1 and 10215S and necessary isolation signal and was previously information; (5) Changed Position At missing from the table. (5) Update for Power Failure from "-" to "FC" for all better representation of system solenoid valves; (6) Changed Position At configuration. Valves receive Normal 0 eration Cold Shutdown containment isolation signal. (6)
Immediate Postaccident from "C" to "LC" Consistency with Ginna Administrative for 1080A; (7) Global Notes 3 and 4 for Control. (7) No technical change. (8) valve 1080A; (8) Changed Valve No. for Update to new valve number only. No IV-2A and IV-2B to 10214S and 10215S1, technical change. (9) No technical respectively; (9) Added Note 18 to change. (10) Correction of solenoid valves; (10) Changed Maximum typographical error. No technical Isolation Time from "NA" to "3" for all change.-
solenoid valves.
- 54. Penetration 300 (1) Added Note 19 for (1) No technical change. (2) both valve and flange; (2) Added Note 2 Consistency with Technical to Blind Flange; (3) Global Note 1 for Specifications. No technical change.
Blind Flange; (4) Changed Position At (3) (4) Update for better representation Normal 0 eration from "0/C" to "C" for of system configuration. Penetration valve 5879; (5) Changed Position At Cold only used during cold shutdown Shutdown from "0" to "0/C" for valve conditions. Mini-purge system now used 5879; in place of purge system.
Safety Analysis Revision 0 Page 33 NSL-0000-SA024 Date 09 24 90
- 55. Penetration 301 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Cold Shutdown Consistency with Ginna Administrative and Position At Immediate Postaccident Control. (3) No technical change.
from "0" to "LC" for both valves; (3)
Added Note 5 to both valves.
- 56. Penetration 303 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Cold Shutdown Consistency with Ginna Administrative and Position At Immediate Postaccident Control. (3) No technical change. (4) from "0" to "LC" for both valves; (3) Correction of typographical error. No Added Note 5 to both valves; (4) Changed technical change. (5) Valves now in both valves from "Diaphragm" to "Globe"; numeric order. No technical change.
(5) Reordered penetration valves.
Safety Analysis Revision 0 Page 34 NSL-0000-SA024 Date 09 24 90
- 57. Penetration 304 (1) Changed valves (1) Correction of typographical error.
1076A and 1084A from "Solenoid" to No technical change. (2) Consistency "Diaphragm"; (2) Changed Position At with Ginna Administrative Control. (3)
Normal 0 eration Cold Shutdown and Correction of typographical omission.
Immediate Postaccident from "C" to "LC" No technical change. (4) No technical for valves 1076A and 1084A; (3) Added change. (5) Update to new valve number "No" under Position Indication In only. No technical change. (6) Minor Control Room for valves 1076A and 1084A; clarification only. No technical (4) Global Notes 3 and 4 for valves change. (7) (8) Update for better 1076A and 1084A; (5) Changed Valve No. representation of system configuration.
for IV-3A and IV-5A to 10205S1 and Valves receive containment isolation 10209S1, respectively; (6) Added signal. (9) No technical change. (10)
"Status" under Position Indication in Correction of typographical error. No Control Room for valves 10205Sl & technical change. (11) Valves now in 10209S1; (7) Changed Position At Power numeric order. No technical change.
Failure from "-" to "FC" for valves 10205Sl and 10209S1; (8) Changed CIS from "No" to "Yes" for valve
~Tri'n 10205S1 and 10209S1; (9) Added Note 17 for valves 10205Sl and 10209S1; (10)
Changed Maximum Isolation Time from "NA" to "3" for valves 10205S1 and 10209S1; (11) Reordered penetration valves.
- 58. Penetration 305a (bottom) (1) Changed (1) Consistency with UFSAR Drawing
~Sstem to "Containment Air Sample Out"; Title. No technical change. (2)
(2) Changed Maximum Isolation Time from Consistency with Technical "NA" to "60" for valve 1597; (3) Changed Specification Table 3.6-1. (3) valve 1596 from "Diaphragm" to "Globe"; Correction of typographical error. No (4) Global Notes 3 and 4 for valve 1597; technical change. (4) No technical (5) Changed Position Indication in change. (5) Minor clarification only.
Control Room from "Yes" to "Both" for No technical change. (6) Valves now valve 1597; (6) Reordered penetration in numeric order. No technical change.
valves.
Safety Analysis Revision 0 Page 35 NSL-0000-SA024
- 59. Penetration 305b (top) (1) Changed (1) Consistency with UFSAR Drawing
~S stem to "Containment Air Sample Title. (2) Consistency with Technical Inlet"; (2) Changed Maximum Isolation Specification Table 3.6-1. (3) Minor Time from "NA" to "60" for valve 1599; clarification only. No technical (3) Changed Position Indication in change. (4) Valves now in numeric Control Room from "Yes" to "Both" for order. No technical change.
valves 1598 and 1599; (4) Reordered penetration valves.
- 60. Penetration 305c <1) Changed ~S stem to (1) Consistency with UFSAR Drawing "Containment Air Sample Postaccident"; Title. (2) Correction of typographical omission. No technical change. (3) for all six valves; (3) Changed Position Consistency with Ginna Administrative At Cold Shutdown and Position At Control. (4) No technical change. (5)
Immediate Postaccident from "C" to "LC" Valves now in numeric order. No for all six valves; (4) Global Notes 3 technical change.
and 4; (5) Reordered penetration valves.
- 61. Penetration 307 (1) Switched Valve No. (1) Correction of typographical error.
for valves 9227 and 9229; (2) Added No technical change. (2) Correction of "Gate" -under Valve 0 erator T e for typographical omission. No technical valve 9227; (3) Global Notes 1, 2, and 4 change. (3) No technical change. (4) for valve 9229; (4) Changed Position Minor clarification only. No technical Indication in Control Room from "Yes" to change.
"Both" for valve 9227.
- 62. Penetration 308 (1) Changed Valve No. (1) Correction of typographical error.
to 4629; (2) Global Notes 3 and 4; (3) No technical change. (2) No technical Changed Position At Normal 0 eration and change. (3) Consistency with Ginna Position At Immediate Postaccident from Administrative Control. (4) Update for "0" to "LO"; (4) Changed Position At better representation of system Cold Shutdown from "0" to "0/C" (5) configuration since fan coolers may be Added Note 17. isolated for maintenance during cold shutdown. (5) No technical change.
Safety Analysis Revision 0 Page 36 NSL-0000-SA024
- ,P><><~!~ A.,gyes-.gory ~gg,~: FQKQ<,.4idsi,
- 63. Penetration 309 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "2" to "3" for both Specifications. Valve design allows valves; (2) Changed Position Indication closure as rapid as 2 (two) seconds.
in Control Room from "Yes" to "Both" for Minimum closure time required by both valves; (3) Reordered penetration Technical Specifications is 5 (five) valves. seconds. (2) Minor clarification only.
No technical change. (3) Valves now in numeric order. No technical change.
- 64. Penetration 310a (1) Changed valve (1) Correction of typographical error.
7141 from "Diaphragm" to "Gate"; (2) No technical change. (2) Consistency Changed Position At Immediate with Ginna Administrative Control. (3)
Postaccident from "C" to "LC" for valve (4) No technical change. (5) Valves 7141; (3) Global Notes 3 and 4 for valve now in numeric order. No technical 7141; (4) Global Notes 1, 2, and 4 for change.
valve 7226; (5) Reordered penetration valves.
- 65. Penetration 310b (1) Changed valve (1) Correction of typographical error.
5392 from "Diaphragm" to "Globe"; (2) No technical change. (2) Minor Changed Position Indication in Control clarification only. No technical Room from "Yes" to "Both" for valve change. (3) Update for better 5392; (3) Changed Position At Cold representation of system configuration Shutdown from "C" to "0" for valve 5393; since IA is used during cold shutdown (4) Global Notes 1, 2, and 4 for 5393; conditions. (4) No technical change.
(5) Added "0" under Position At Cold (5) (6) (7) Update for better Shutdown for valve 5392; (6) Added "C" representation of system configuration.
under Position At Immediate Postaccident Valve receives containment isolation for valve 5392; (7) Changed Position at signal. (8) Valves now in numeric Power Failure from "-" to "FC" for valve order. No technical change.
5392; (8) Reordered penetration valves.
Safety Analysis Revision 0 Page 37 NSL-0000-SA024 Date 09 24 90
'I ~
Penetration 311 (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration and may be isolated for maintenance during Position At Immediate Postaccident from cold shutdown conditions. (2)
"0" to "LO"; (3) Global Notes 3 and 4. Consistency with Ginna Administrative Control. (3) No technical change.
- 67. Penetration 312 - (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration may be isolated for maintenance during and Position At Immediate Postaccident cold shutdown conditions. (2) from "0" to "LO"; (3) Global Notes 3 and Consistency with Ginna Administrative 4 ~ Control. (3) No technical change.
- 68. Penetration 313 (1) Added "Blind" (1) Correction of typographical omission. No technical change. (2) No Global Notes 1, 2, and 4 for Blind technical change. (3) Minor Flange; (3) Changed Position Indication clarification only. No technical in Control Room from "Yes" to "Status" change. (4) Correction of typographical error. No technical from "No" to "Yes" for valve 7444; (5) change. (5) No technical change.
Added Note 19.
- 69. Penetration 315 (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration and may be isolated for maintenance during Position At Immediate Postaccident from cold shutdown conditions. (2)
"0" to "LO"; (3) Global Notes 3 and 4. Consistency with Ginna Administrative Control. (3) No technical change.
Safety Analysis Revision 0 Page 38 NSL-0000-SA024 Date 09 24 90
- 74. Penetration 320 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Normal Consistency with Ginna Administrative Control. (3) Update for better Postaccident from "0" to "LO"; (3) representation of system configuration Changed Position At Cold Shutdown from since fan coolers may be isolated for f!Off to nO/Ctt maintenance during cold shutdown conditions.
- 75. Penetration 321 (1) Global Notes 3 and (1) No technical change. (2) Minor 4 for valve 5701; (2) Changed Position clarification only. No technical.
Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valve 5738; (3) Changed representation of system configuration.
Position At Cold Shutdown from "C" to (4) Valves now in numeric order. No "0/C" for valve 5738; (4) Reordered technical change.
penetration valves.
- 76. Penetration 322 (1) Global Notes 3 and (1) No technical change. (2) Minor 4 for valve 5702. (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valve 5737; (3) Changed representation of system configuration.
Position At Cold Shutdown from "C" to (4) Valves now in numeric order. No "0/C" for valve 5737; (4) Reordered technical change.
penetration valves.
- 77. Penetration 323 (1) Global Notes 3 and (1) No technical 'change. (2) 4; (2) Changed Position At Normal Consistency with Ginna Administrative Control. (3) Update for better Postaccident from "0" to "LO"; (3) representation of system configuration Changed Position At Cold Shutdown from since fan coolers may be isolated for "0" to "0/C" maintenance during cold shutdown conditions.
Safety Analysis Revision 1 Page 40 NSL-0000-SA024 Date 10 3 90
- 78. Penetration 324 (1) Changed valve 8418 (1) Correction of typographical error.
from "Diaphragm" to "Globe"; (2) Changed No technical change. (2) Update for Position At Cold Shutdown from "0" to better representation of system "0/C" for valve 8418; (3) Changed configuration. (3) Minor clarification Position Indication in Control from only. No technical change. (4) No "Yes" to "Both" for valve 8418; (4) technical change. (5) Correction of Global Notes 1, 2, and 4; (5) Changed typographical error. No technical Maximum Isolation Time from "NA" to "60" change. (6) Valves now in numeric for valve 8418; (6) Reordered order. No technical change.
penetration valves.
- 79. Penetration 332a (1) Global Note 1 for (1) No technical change. (2) pressure transmitters; (2) Added "Globe" Correction of typographical omission.
h No technical change. (3) No technical valves; (3) Global Note 3 for the manual change. (4) Valves now in numeric valves; (4) Reordered penetration order. No technical change.
valves.
- 80. Penetration 332b Deleted entire Penetration has double isolation and penetration from table. meets the criteria, for a test connection. Therefore, this penetration is not required to be tested per 10CFR50 Appendix J and does not belong on the table.
- 81. Penetration 332c (1) Added "6.2-74" (1) Correction of typographical under UFSAR Fi ure for all valves other omission. No technical change. (2) than 922. (2) Changed Position Minor clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Both" for all four valves; (3) Changed representation of system configuration.
Position At Immediate Postaccident from System isolated upon receipt of "0/C" to "C" for all valves. containment isolation signal.
Safety Analysis Revision 0 Page 41 NSL-0000-SA024 Date 09 24 90
- 82. Penetration 401 (1) Added Note 11 to (1) Correction of typographical all valves other than 3517; (2) Changed omission. No technical change. (2)
Correction of typographical error. No 3517; (3) Changed Position Indication in technical change. (3) Minor Control Room from "Yes" to "R/G" for clarification only. No technical valves 3505A and 3517; (4) Global Notes change. (4) No technical change. (5) 1, 2, 3, 4, and 5; (5) Reordered Valves now in numeric order. No penetration valves. technical change.
- 83. Penetration 402 (1) Added Note 11 to (1) Correction of typographical all valves other than 3516 and 3518; (2) omission. No technical change. (2)
Correction of typographical error. No valve 3516; (3) Changed Position technical change. (3) Minor Indication in Control Room from "Yes" to clarification only. No technical "R/G" for valves 3504A and 3516; (4) change. (4) No technical change. .(5)
Global Notes 1, 2, 3, 4, and 5; (5) Valves now in numeric order. No Reordered penetration valves. technical change.
- 84. Penetration 403 (1) Global Notes 1, 2, (1) No technical change. (2)
- 3. Correction of typographical error. No from "6.2-75" to "6.2-76" for valve technical change. (3) (4) (5) 3995; (3) Added "6.2-76" under UFSAR Correction of typographical omission.
Ficiure for all valves after valve 3995; No technical change. (6) Valves now (4) Added Note 11 to all valves other in numeric order. No technical change.
than valve 3995; (5) Added "4" under Class for all valves other than 3995; (6) Reordered penetration valves.
- 85. Penetration 404 (1) Global Notes 1, 2, (1) No technical change. (2)
Correction of typographical error. No from "6.2-75" to "6.2-76" for valve technical change. (3) Correction of 3994; (3) Added Note 9 to all valves typographical omission. No technical other than 4000D; (4) Reordered change. (4) Valves now in numeric penetration valves. order. No technical change; Safety Analysis Revision 0 Page 42 NSL-0000-SA024
- 86. Penetration 1000 (1) Global Notes 1, (1) No technical change. (2) (3)
IV'1) 2, 4, and 5; (2) Added "Both" to Correction of typographical omission.
Position Relative to Containment; (3) No technical change.
- 87. Penetration 2000 (1) Global Notes 1, No technical change. (2) (3) 2, 4, and 5; (2) Added "Both" to Correction of typographical omission.
Position Relative to Containment; (3) No technical change.
"3. 8 3 Safety Analysis Revision 0 Page 43 NSL-0000-SA024
(1) Deleted last sentence of "old" Note (1) (2) The deleted sentence of the 1 and moved it to "new" Note 2; (2)
Renumbered remaining "old" Note 1 as note is still applied to necessary penetrations. No technical change.
Note 3.
- 2. Deleted "old" Note 2. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
- 3. Deleted "old" Note 3. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
- 4. (1) Deleted first two sentences of "old" (1) These two sentences only duplicated Note 4; (2) Modified last sentence to UFSAR text. No technical change. (2) reflect system configuration; (3) Sentence now accurately reflects Renumbered "old" Note 4 as Note 6. wording of the January 30, 1987 letter.
(3) No technical change.
- 5. Deleted "old" Note 5. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
- 6. Deleted "old" Note 6. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
- 7. Deleted "old" Note 7. Note was only a duplication of the UFSAR text. No technical change.
- 8. Deleted "old" Note 8. Note was only a duplication of the UFSAR text. No technical change.
Safety Analysis Revision 0 Page 44 NSL-0000-SA024 Date 09 24 90
- 9. (1) Modified "old" Note 9; (2) (1) (2) Minor clarification only. Note Renumbered "old" Note 9 as Note 13. now describes in detail the use of the pressure transmitter as a boundary. No technical change.
- 10. Deleted "old" Note 10. Note was only a.duplication of the UFSAR text. See "new" Note 4. No technical change.
Deleted "old" Note 11. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
- 12. (1) Modified "old" Note 12; (2) Minor clarification only. No technical Renumbered to "new" Note 15. change.
- 13. Deleted "old" Note 13. Note was only a duplication of the UFSAR text. No technical change.
- 14. (1) Deleted last two sentences of "old" (1) The deleted sentence of the note is Note 14 and moved it to "new" Note 16; still applied to necessary (2) Modified remaining "old" Note 14; penetrations. No technical change.
(3) Renumbered "old" Note 14 as Note 17. (2) (3) Minor clarification of note only. No technical change.
- 15. Deleted "old" Note 15. Note was only a duplication of the UFSAR text. No technical change.
- 16. Deleted "old" Note 16. Note is incorrect and no longer applicable.
- 17. (1) Modified "old" Note 17; (2) (1) (2) Minor clarification of note Renumbered "old" note 17 as Note 21. only. No technical change.
Safety Analysis Revision 0 Page 45 NSL-0000-SA024
4
- 32. Added Note 20. Minor clarification only. Note provides additional information related to penetration's use. No technical change.
Safety Analysis Revision 0 Page 48 NSL-0000-SA024 Date 09 24 90
- 18. (1) Modified "old" Note 18; (2) (1) (2) Minor clarification of note Renumbered "old" Note 10 as Note 11. only. No technical change.
- 19. Added Note l. Note provides clarification on use of the penetration. See letter from R.
Mecredy, RG&E, to A. Johnson, NRC, dated March 13, 1990.
- 20. Added Note 2. Note provides generic description of penetration seals. Note originally part of "old" Note 1. No technical change.
- 21. Added Note 4. Minor clarification only. Note originally part of "old" Notes 2, 3, 5, 6, 10, and 11. Note now used on a global basis. No technical change.
- 22. Added Note 5. Minor clarification only. Note provides additional information related to penetration's use. No technical change.
- 23. Added Note 7. Note provides consistency with Technical Specification Table 3.6-1 Note 20. No technical change.
- 24. Added Note 8. Minor clarification only. Note provides additional information related to MOV breaker status. No technical change.
Safety Analysis Revision 0 Page 46 NSL-0000-SA024
k
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- 25. Added Note 9. Minor clarification only. Note provides additional information related to function of the valve. No technical change.
- 26. Added Note 10. Minor clarification only. Note provides detailed description of penetration valves. No technical change.
- 27. Added Note 12. Minor clarification only. No technical change.
- 28. Added Note 14. Note provides additional information related to penetration. See letter from R. Mecredy, RG&E, to A. Johnson, NRC, dated July 9, 1990.
- 29. Added Note 16. Note provides clarification of leakage test requirements. Note originally part of "old" Note 14. No technical change.
- 30. Added Note 18. Minor clarification only. Note provides additional information related to solenoid status. No technical change.
- 31. Added Note 19. Note provides consistency with Technical Specification Table 3.6-1 Note 22 and notes related to penetrations 313 and 317. No technical change.
Safety Analysis Revision 0 Page 47 NSL-0000-SA024
Table 1 Technical Specification Changes Chanches Effect Section 3.6.3.1 references No technical change.
UFSAR Table 6.2-13 instead of Technical Specification Table 3.6-1.
- 2. Table 3.6-1 removed from Valve listing remains in a Technical Specifications and licensee controlled document under information placed in UFSAR 10CFR50.59 program.
Table 6.2-13.
- 3. Revised inoperable No technical change. Clarification definition of Section only consistent with 10CFR50 3.6.3.1. Appendix J.
- 4. Removed note associated with Mini-purge valves have been Technical Specification installed so the Technical 3.6.5. Specification can be considered effective. No technical change.
- 5. Added "Pt" and necessary Addition of "Pt" provides definitions to Technical
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clarification of testing type Specification 4.4.1.4
~
~ consistent with 10CFR50, Appendix section a. J. All terms in 4.4.1.4, section a now fully defined. No technical change.
Added to the definition of Added definition "Lt" provides "Lt" in Technical clarification consistent with Specification 4.4.1.4 10CFR50, Appendix J. All terms in section b. 4.4.1.4, section b now fully defined. No technical change.
- 7. Added definition of "Pa" and Addition of "Pa" and "La" provides "Lam" in Technical clarification consistent with 10 Specification 4.4.1.4 CFR 50, Appendix J. All terms in section c. 4.4.1.4, section c now fully defined. No technical change.
- 8. Added steam generator Addition of this penetration inspection/maintenance provides testing criteria similar penetration to Technical to the equipment hatch and Specification 4.4.1.5 containment air locks.
section a (ii).
- 9. Revised first line of Minor clarification only. No Technical Specification technical change.
4.4.1.5, section a (ii) .
Removed notes associated with Technical Specification 4.4.2.4 section a. Deleted Mini-purge valves have been installed so the Technical Specification can be considered reference to section d. effective. Section d will be removed from Technical Specifications. No technical change.
- 11. Added steam generator Addition of this penetration inspection/maintenance provides testing criteria similar penetration to Technical to the equipment hatch and Specification 4.4.2.4 containment air locks.
section b.
- 12. Removed Technical Blind flanges have been installed Specification 4.4.2.4 so the Technical Specification can section d and associated be considered effective. No note. technical change.
1 3. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.5.1. 10CFR50.59 program.
- 14. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.6.2. 10CFR50.59 program.
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0