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{{#Wiki_filter: | {{#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: Nu lear Engineer K)-z.-'9Q Date Reviewed by: Nucle r Engine r Date Approved by: anag r, Nuclear S fety&Licensing Date Page i 90i0240i'i9 90iOi5 PDR ADOCK 05000244 P PDC I Revision Status Sheet Page Latest Revision Latest Page'evision Page Latest Revision 7 8 9 ,10 14h 15 16 17 18 19 20 21 22 23 24 25 0 37 38 39 40 41 42 43 44 45 46 47 48 12 13 14 14a 14b 14c 14d 14e 14f 14g 27 28 29 30 31 32 33 34 35 36 0 Safety Analysis NSL-0000-SA024 Page ii Revision 1 Date 10 3 90 Safet Anal sis 1.0 2.0 f Descri tion and Sco e The purpose of this evaluation is to determine if there are any unreviewed safety questions related to updating 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.References 2.1 2.1.1 2.1.2 Updated Final Safety Analysis Report, Revision 5.Section 6.2.4, Containment Isolation System.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~~2.2.2 2.2.3 2.3 2.4 Section 3.6.3, Containment Isolation Valves.Table 3.6-1, Containment Isolation Valves.Section 3.8.1, Refueling. | ||
Letter from J.E.Maier, RG&E, to D.M.Crutchfield, NRC, | |||
==Subject:== | ==Subject:== | ||
SEP Topic VI-4, Containment Isolation Valves (Systems); | |||
dated August 30, 1982.Letter from L.D.White, RG&E, to D.L.Ziemann, NRCg | |||
==Subject:== | ==Subject:== | ||
Discussion | Discussion of Lessons Learned Short Term Requirements; dated November 19, 1979.2.5 2.6 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, | |||
==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, | |||
==Subject:== | ==Subject:== | ||
Forwarding | 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 Page 1 Revision 0 2.8 2.9 2.10 2.11 2.12 2.13 2.14 2.15 2.16 2.17 2.18 2.19 2.19.1 2.20 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, | |||
==Subject:== | ==Subject:== | ||
Necessary Clarifications Associated | 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, | ||
==Subject:== | ==Subject:== | ||
Containment Isolation | 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, | ||
==Subject:== | ==Subject:== | ||
Technical Specification Interpretation | 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, | ||
==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, | |||
==Subject:== | ==Subject:== | ||
Operability | Operability of AOV 745 and MOVs 749A/B;dated July 9, 1990.Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, | ||
==Subject:== | ==Subject:== | ||
Modification | Modification of Containment Penetration | ||
$2; | $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 Page 2 Revision 0 Date 9 24 90 I 4 II 3.0 Safet Anal sis 3~1 3.2 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.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.(2)(3)(4)The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy. | |||
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 only been changed, 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: | |||
(2)(3)clarifications or corrections of typographical errors and omissions,. | |||
Instead,Attachment | 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 Page 3 Revision 0 | ||
~~s~3.3.1 3.3.1.1 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.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. | |||
Instead, | 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. | ||
(2)(3)clarifications | 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 3.3.2.1 The updates to the UFSAR table to better represent actual plant conditions are described below.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. | |||
~~s~3.3. | The penetration meets all current containment penetration criteria.See Reference 2.17.Safety Analysis NSL-0000-SA024 Page 4 Revision 0 Date 9 24 90 | ||
~~~~3.3.2.2 3.3.2.3 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 | |||
.3.3.1 | 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 it was open since this was the most conservative position.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. | ||
3.3.1. | 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 NSL-0000-SA024 Page 5 Revision 0 Date 9 24 90 | |||
$ | ~~~~'3.3.2.4 3.3.2.5 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.Also, during Refueling Operations, Technical 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 negatively'mpact the penetration or the containment 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).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 NSL-0000-SA024 Page 6 Revision 0 | |||
~~~~3.3.2. | ~~(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. | |||
¹) | 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.Safety Analysis NSL-0000-SA024 Page 7 Revision 0 Date 9 24 90 | |||
Therefore, | |||
Valves( | |||
¹) | |||
~~~~'3.3.2. | |||
Consequently, | |||
.(a)529(g12lb)- | |||
~~(b)4629($308) | |||
Consequently, | |||
~~ | ~~ | ||
~~~~(e)Penetration 141- | ~~~~(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.3.3.2.8 (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.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 3.3.3.1 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. | ||
Therefore, | 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 Page 8 Revision 0 | ||
~I~~3.3.3.2 3.3.3.3 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).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. | |||
~I~~3.3.3. | The events related to this UFSAR change are: Safety Analysis NSL-0000-SA024 Page 9 Revision 0 | ||
~~3.4.1 3.4.2 3.4.3,~~3.4.4 (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 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.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. | |||
(a)749A(f127),749B($128)- | No changes are made with respect to the seismic design of the affected penetrations. | ||
See, | 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. | |||
~~3.4. | 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.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.Safety Analysis NSL-0000-SA024 Page 10 Revision 0 Date 9 24 90 P | |||
4~~k~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 4.2 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.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 Page 11 Revision 0 Date 9 24 90 | ||
Consequently, | |||
4~~k~3.4. | |||
~~~~ | ~~~~ | ||
4. | 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. | ||
=4. | 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 Page 12 Revision 9 24 90 k | ||
~~4.7 4.8 The proposed UFSAR changes will not reduce any margin of safety as defined in the basis of any technical specification. | |||
~~4. | 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. | |||
However, | 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 that: (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.Safety Analysis NSL-0000-SA024 Page 13 Revision 0 Date 9 24 90 l~/ | ||
Attachment A Safety Analysis NSL-0000-SA024 Page 14 Revision 0 Date 9 24 90 CONTAI AND I 2-13 PENETRATIONS PIPINC~Sstea Penetration No.Valve No.Valve Position Valve Indi cation Position Operator In Control Relative to Normal Position At Cold Ixaedf ate Shutdovn Postaccfdent~ | |||
Maxi sans Isolation UFSAR Notes Steam Cenerator Inspection/ | |||
Attachment | Maintenance Blind Flanges Both 0/C C (add)5 I~2 Fuel Transfer Tube Charging Line to B Loop Safety Infection Pury IB Discharge Alternate Charging to A Cold Leg 29 100 101 102 370B 870B 889B 3838 Blind Flange Check Check Check Check Inside Inside Outside Outside Inside 0/C 0 0 C 6'-13 5 6.2-18 3B 6'-15 3B 6'-15 3B 6.2-16 3B 2I 3 Construction Ffre Service Water 103 NA Blind Flange NA NA Inside C C NA 6'-17 5 Containment Spray Pusy IA Reactor Coolant Puxy h Seal Water Inlet 105 106 8 62A 306k Check Check NA Outside C Nh Inside 0 0 NA 6'-18 3B 6'-19 3B Susy h Dfs charge to Waste Holdup Tank Reactor Coolant Pump Seal Water Return Lfne and Excess Letdovn to VCT 107 108 1723 1728 313 Diaphraga Dfaphraga Afr hir Motor Status Status Both Outside Outside Outside 0 0 0/C 0/C 0/C C C FC Yes FC Yes AI Yes 60 6.2 20 2 60 6'"20 2 60 F 2-21 8, 6 Containment Spray Pury IB 109 862B Check Nh NA Outside C Nh 6.2 22 3B end AI Falls As Is AOV Air Operated Valve C~Closed CIS~Contafnment Isolation Signal CV Check Valve FC~Falls Closed FO Fails Open LC~Locked Closed MQV MV 0 0/C R/C Status SOV Moto~rated Valve~Manual Valve~Open Open or Closed~Red/Creen Light on Main Control Board White Status Light, Solenoid Operated Valve Refers to position fsuediately follovfng receipt of containment isolation signal and containment ventilation fsolation signal.s The maxfxaa isolation time does not include diesel start time nor instrument delay tfme.'efers to classes defined in Section 6.2.6.6.2. | ||
s Notes only used to supplement Section 6.2.6.6.2. | |||
Maintenance | Safety Analysis'I" NSL-'.OO,OO-SA024 Page 14a Revision 1 | ||
-13 CONTAI PENETRATIONS AND I PIPING~Satan Reactor Coolant Purp B Seal Nater Inlet Penetratfon No.110a (topi Valve No.304B Valve Check Position Valve Indication Position Operator In Control Relative to Homal Roon Contafnnent OHeratfon NA Nh InsMe 0 Position At Cold lxxaadf ate Paver Trip on Shutdovn Postaccfdentv Failure CIS 0~C NA Nh Maxi xixa Isolation Tfxe DFSAR Notes 6.2-23 3B Safety Inlectfon Test Lfne 110b<bottoni 879 Globe Manual No Outside LC LC NA 6~2-15 1 Residual Hea't Renoval to B Cold Leg 720 959 Gate Globe Motor Alr R/C Status Inside Outs fde 0 0/C AI FC 6.2-24 6.2-24 3B 3B 4~7g 8 I 4, 1 Letdown to Nonregenerative Heat Exchanger Safety In)ection Puxp IA Discharge Standby Auxf I-fary Feedwater Line to Stean Generator lh 112 113 119 200A 200B 202 371 421 810A 889A 9104A 9105A Globe Globo Clobe Globe Globe Check Check Stop-Check Check Afr Alr Air Air Alr Motor NA R/G R/G R/G Both R/C NA NA R/G Nh Inside Inside Inside Outside Inside Outside Outside OutsMe Inside 0/C 0/C C 0 0 C C C C C 0 0/C C C C C C AI NA Yes Tes Yes Yes Yes No Nh 60$0 60$0 3B 3B 6.2-15 6.2 15 6.2 26 6.2-26 6~225 I$e2 25 I 6~225 1 6.2-25 I$.2-25 I 10 10 10 Nitrogen to hccuxaIlators Pressurlxer Relief Tank to Gas Analyxer Nitrogen to Pressurixer Relief Tank Makeup Rater to Pressurixer Relief Tank Conte funest Pressure Transnftt@r PT945 120a 120b 121a 121b 121c 846 4623 539 546 528 547 504 529 PT945 1819A Globe Check Globe Globe Check Globe Dfaphragn Check NA Globe Air NA Air Manual NA lanual Air NA NA Manual Both NA Sta'xus No NA No Both NA Outside Inside Outside Outside Inside Outside Outside Inside Outside Outs Me C 0/C C 0/C 0/C'/C , 0/C 0 0/C OIC OIC OIC C C C 0 C C FC Yes NA FC Yes Nh Nh FC Yes NA Nh 60 Nh 60 NA 6~2 21 3A$.2-27 3A 6~2-28 2 F 2-24 2 6.2-29 3A$.2 29 3A 6~2-30 3A$.2-30 3A 6 2-31 2 6.2 31 2 12 13 Contafnnent Pressure TransxLit'tox'T946 121d F2946 Nh NA NA Outside Nh NA 1819B Globe Manual No Outside 0 0 6.2-31 2 6 2-31 2 13 Standby Auxfl-fary I'eedvater Line to Stean Generator IB 123 ltopl 9104 B 91058 Stop-Check Check Motor Nh Outside Inside C C C C AI Nh NA 6.2-26 Nh 6.2-26 4 Safety Analysis NSL-,OOOO-SA024 Page 14b Revision 1 Date 10 3 90 | |||
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) | ) | ||
CONTAI AND~2-13~PENETRATION~a PIPIhG~Sat cmc Penetration Valve No.Valve Position Valve Indication Position Operator In Control Relative to Homal~T Rocvm, Contafnacent OEeratfon Posftfon At Cold Iacaediate Pover Trip on Shutdovn postaccfdcntr Failure CI8 Max f aaxa Isolation Ti lac UFSAR~Fi re Notes Reactor Coolant Drain Tank to Gas Analyzer Line Excess Letdovn Beat Exchanger Cooling Water Supply 4 Return Postaccfdcnt Afr Sag>le to C Fan Component Cooling Water fraa Reactor Coolant Pump 1B 123 (button)124a 124b 125 1600A 1655 1789 743 745 1569 1571 1572 1574 7598 Globe Globe Diaphragca Check Globe Dfaphragca Dfsphragca Dfaphragrc Dfaphragal Cate Solenoid Manual hfr Q hi r Manual Manual Manual Manual Hotor No No Status Q RIG R/C Outsfde Outside Outside Inside Outside Outs fde OutsMe Outside Outsfde Outside 0 0 0 0 0 0/C 0 0/C C C LC IC, LC LC r C r C 0 C C C 0 AI Ycls NA Yes NA No No NA 60 6.2-32 6.2-32 6'-32 6.2-33.6.2-33 6'-34 5 6.2 34 5 6.2-34 5 6.2-34 5 6.2-35 4 14 Ccxcponent Cooling Water frees Reactor Coolant Pump IA 126 759A Gate Motor R/C Outside 0 AI No Nh 6.2<<36 Componen't Cooling Nater to Reactor Coolant Pump lh 127 749A 750A Cate Check Hotor NA Outside Inside 0 0 C C 0 0 AI NA Q 6.2-37 4 Q 6.2-37 Cccmponeat Cooling Water to Reactor Coolant~1B Reactor Coolant Drain Tank and Pressurizer Relist Tank to Containnent Vent Reader 128 129 7498 7508 1713 1786 1787 1793 Cate Check Check Dfaphragal Dfaphragca Dfaphragal Motor NA NA hir Air Manual NA Sta'tus S'ta'tua No OutsMe Inside Outside Outsfde Outside Outside 0 0 C 0 0 LC C C 0/C C C 0/C 0 0 C C C LC AI NA No NA Q 6'-38 Q 6'-38 4 NA NA NA 6.2-39 3A FC Yes 60 6'-39 3A FC Yes 60 6.2-39 3A Nh NA NA 6~2-3S 3A 12 Component Cooling Water f rcxa Reactor Support Cooling 130-814 Gate Motor Both Outside 0 AI Yes 60 6.2-40 4 Cc~nent Cooling Nater to Ream'tor Support Cooling Containment Nfnf-Purge Exhaust 131 813 Cate Hotor Both Outside 0 0 132 7970 Butterfly hir Both Inside 0/C OIC 7971 Buttertly Alr Both OutsMe C 0/C C C AI Yes FC Yes FC Yes 60 6.2-40 4 3 6.2-41 5 3 6.2-41 5',Safety Anal'ysis r NSL-0000-SA024 Page 14c Revision 1 | |||
~, | ~, | ||
2 13 CONTAI PENETRATION< | |||
AND I~PIPING~zs ten Residual Beat Removal Pump Suctfon from A Hot, Leg Penetration No.140 Valve No.701 Valve Valve Operator Gate Hotor Position Indication Posftfon In Control Relative to Room Containment R/C Inside Position At Normal Cold Imnediate Fever OHeratfon Shutdovn Postaccidcnt'ailure 0 C AI Trip on CIS Kaxfmsus I moist f on Time OFSAR Notes~Ff re Classs See end of table~7i 8 6.2-42 1 Residual Heat Removal No.1 Pump Suction from Sump B 141 85th 1813A Cate Cate Hotor Hotor R/0 Outside C C R/C Outside C 0/C 0 C AI No Nh 6.2-42 5 AI No NA 6.2-42 5 15 8 Residual Heat Removal No.2 Pump Suction from Su~B 142 SSOB Gate Hotor R/C Outside C C 1813B Gate Hotor R/0 Outside C 0/C AI AI NA 6~2-42 5 NA 6.2-42 5 15 8 Reactor Coolant Drain Tant Discharge Lfne Reactor Compartment Cooling Onits h and B 143 201 (top)201 (bottom)1003A 1003B 1721 4757 4636 DI a phragn Diaphragm Diaphragm Butterfly Butterfly Air Afr Alr Hanual Hanual Status Status Status No No Outside Outside Outside Outside Outside 0 0 0 0 0 0/C 0/C 0 C C C 0 0 Yes Yes Yes 60 60 60'.2-43 2 6~2-43 2 6.2-42 2 6.2-44 4 6.2-45 4 16 17 B Hydrogen Recombiner (Pilot and Hafn)Containment Pressure Transmitter PT947 and PT948 PostaccMent Air 8~le to B Fan Purge Supply Duct Hot Leg Loop Sample Pressurizer Liquid Space~le A Stean Cenerator Sample 202 2Q3a 203b 204 205 206a (top)206b (bottom)1076B 1084B 1021181 1021351 F2947 PT948 1819C 1819D 1563 1565 1566 1568 5869 955 956D 966C 953 956E 966B 5733 5735 Diaphragm Diaphragm Globe Clobe NA NA Clobe Globe Diaphragm Diaphragm Diaphragm Diaphragm Blind Flange Butterfly Clobe Globe Globe Globe Clobe Globe Globe Globe Hanuaf Nanuel Solenoid Solenoid NA Nh Hanua 1 , Hanual Hanual Hanual Hanuel Hanual Afr Air Hanual Air Alr Manual Alr Hanual Alr No No Status Status NA Nh No No No No No No NA Both St&'tus No Status Status No S'ta'tus No Status Outside Outside Outside Outside Outside Outside Outs Me Outs I de Outside Outside OutsMe Outside Inside Outside Inside Outside Outside Inside Outside Outside Outside Outsfde LC LC C C NA NA 0 0 C C C 0 C C 0 C LC LC C C NA Nh 0 0 0 0/C C 0 C C 0 C LC LC C C NA NA 0 0 C 0 C C 0 C 0 C Nh FC Nh FC Nh NA Yes Yes Yes NA Yes Yes Nh Yes NA NA 3 3 NA NA 60 NA NA 60 NA 60 6.2-46 F 2-46 6.2-46 6.2-46 6.2-47 6.2 47 6,2 47 6~2 47 6.2 48 6.2-48 6.2 48 6.2 48 6.2 49 6.2 49 6'50 6~2 50 6.2-50 6.2 51 6.2-51 6~2 Sl 6~2 52 6.2 52 2 2 2 2 18 18 13 13 2, 19 19 Pressurizer Steam Space Sample 207a (top)951 956F 966A Globe Globe Globe Alr Hanuel Air Status No Status Inside Outside Outside C 0 C C 0 C C 0 C FC Yes Nh 6.2 S3 1 NA NA NA 6.2-53 I FC Yes 60 6~253 1 ss 3'Safety Analysis'SL-0000-SA024 Page 14d Revise.on 1 l | |||
2-13 CONTAIN PENETRA TIGHT AND I N PIPING Penetration Mo.Valve No.Valve Valve Operator Position Indication Position In Control Relative to Normal Roon Containment OBeratfon Posftfon At Cold irumdfate Power Shutdovn Postaccfdent'aflur* | |||
Trip on CIS Maxi sum Isolation Time UFSAR~F(re Cla ass Notes See end of table a B Steam Generator Sample Reactor Cocpartment Cooling Units h and B Oxygen Makeup to h 4 B Reconbiners Purge Exhaust Duct Auxiliary Steam Supply to Containment Auxiliary Steam Condensate Return A Hydrogen Recoebiner (Pilot and Nein)207b (bottom)209 (top)209 (bottom)210 300 301 303 304 5734 5736 4635 4758 1080A 102145 1021481 102158 1021531 Nh 5479 6151 6165 6152 6175 1076A 108(A 1020551 1020951 Globe Globe Butterfly Butterfly Globe Clobe Globe Globe Globe Blind Flange Butterfly Globe Globe Globe Globe Diaphragm Diaphragm Globe Globe Manual Air Manual Manual Manual Solenoid Solenoid Solenoid Solenoid NA Air Manual Manual Manual Manual Hanual Manual Solenoid Solenoid No Status No No No S'tatus Sta'kus Status S'tatus NA Both No No No No Status S'ta'tus Outside Outside Outside Outside Outside Outside Outs fde Outside Outside Insfde Outs ide Outs ide Outside Outside Ou'teide Outside Outside Outside Outside LC C C C C LC LC C C C C LC C C C C 0 OIC LC LC C C LC C~C C C LC LC C C NA NA Nh Tes Tes Tes Yes NA Yes Nh Nh Tes Yes Nh 60 3 3 3 3 6.2-54 6.2-54 6.2-44 6.2-45 6.2-55 6.2-55 6.2 55 6.2-55 6'-55 6'-56 F 2-56 6.2-57 6.2-57 6.2-57 6.2-57 6.2-58 6.2-58 6.2-54 6.2-58 16 17 14 14 14 14 2, 19 19 18 18 Contafnment Alr Saxple Out Containment Air Sarpf e Inlet Containment Alr Sa=ple Postaccident Fire Service Mater Service Mater to h Fan Cooler Nini-Purge Supply Service Air to Containment 305a (bottom)305b (top}305C 307 308 309 310a (bottcm)1596 1597 1598 1599 1554 1556 1557 1559 1560 1562 9227 9229 4629 7445 7474 7141 7226 Globe Diaphragm Diaphragm Diaphragm Diaphragm Die ph rage Diaphragm Diaphragm Diaphragm Diaphragm Cate Check Butterfly Butterfly Butterfly Cata Check Manual Air Air Alr Manual Manual Manual Hanual Manual Manual Afr NA Manual hir Alr Manual Nh No Both Both Both No No No No No No Both Nh Both Both No Nh Outside Outside Outsfde Outside Outside Outside Outside Outside Outside Outside Outside Insfde Outside Outsfde Inside Outside Inside OIC OIC 0/C 0/C OIC NA Tes Tes Tes Tes Nh Yes Tes 60 60 60 Nh 6~2 61 6.2 61 6.2 61 6.2-61 6.2 61 6.2 61 6.2 62$.2-62 6.2 63 6,2 64 6.2 64 6~2-65 6.2 65 6.2 59 6~2 59 6.2 60 6'60 2 2 3A 3h 3A 3A Safety Analysis E-NSL-0000-SA024 Page 14e Revision Date 10 3 90 CONTAINNEN AND I-13 PENETRATIONS ON PIPING~Sat em Instrument Air to Contafnmnnt Service Mater from B Fan Cooler Penetration No.310b (top)311 Valve Mo, 5392 5393 4630 Valve Globe Check Butterfly Valve Operator Manual Both NA Outside Inside Outside 0 0 Position Indicatfon Position In Cont rol Relative to Normal Room Contain>nant OEeratfon 0/C C C Posftfon ht Cold irradiate Shutdovn Postaccfdent'over Failure Trip on CI8 Yes NA Hex f sum Isolation Time 60 IR VFSAR~Ff re 6.2 66 6.2-66 6.2-63 3A 3A Notes 16 Service Mater to D Fan Cooler Leakage Test Depressurira-t ion 312 313 4642 NA 7444 Butterfly Blind Flange Butterfly Hanual Nh Hotor NA Sta'tus Outside Inside Outsfde 0/C.C C NA Al NA Yes NA 6.2-63~Q 6.2-67 5 Q 6~2 67 5 17 19 Service Mater From C I'an Cooler 315 4643 Butterfly Hanuel Outside 0/C>NA NA NA 6.2-63 4 16 Service Mater to B Fan Cooler Leakage Test Supply Deadveight Tes'ter Service Mater from A Fan Cooler 316 317 31d 319 4628 NA 7443 NA 4627 Butterfly Blind Flange Butterfly Butterfly Hanual NA Hotor Hanual No NA Sta'cus No Outside Inside Outside Outside 0/C 0/C NA AI Q Yes NA 6.2-63 4 6.2 68 5 6.2"68 5 lR NA 6~2-63 4 17 19 20 16 Service Mater to C Fan Cooler A Steam Generator Blovdovn 320 321 46li 5701 5738 Butter fly Globe Globe Manual Hanua1 Air No No Status Outside Outside Outside 0 0 0/C.'0/C 0 C NA 6.2-63 NA Q Q 6.2-6S FC Yes 60 6~2 69 17 B Steam Generator Blovdovn Servfca Mater fran D I'an Cooler Demineralized Mater to Contafment 322 323 324 5702 5737 4644 4 l 1 d 8l 1 9 Globe Globe Butterfly Globe Check Manual hir Hanual Air NA No Status No Both NA Outside Outside Outside Outside Inside C C 0 0/C 0/C 0/C 0/C C C NA Yes Yes NA Q 6.2-70 60 6270 Q 6.2-63 60 6.2-71 5 lVL 6~2-71 5 16 Containment Pressure Transmitters PT944, F2949>and PT950 332a PT944 PTS49 PT950 1819E 1419F 18190 NA NA Q Globe Globe Globe NA NA Nh Hanual Manual Manual NA NA NA No No No Outside Outside Outside Outside Outside Outside IVL IR NA 0 0 0 Nh NA NA 0 0 0 Q NA NA 0 0 0 6.2-72 6.2-72 6.2-72 6.2-72 6'-72 6.2-72 NA NA NA 2 Nh Nh IVL 2 N1L NA IR 2 NA.NA NA 2 NA NA NA 2 NA Nh Nh 2 13 13 13 Safety Analysis.NSL-0000-SA024 Page 14f Revision 1 Date 10 3 90 CONTAI AND IS 2 13'C PENETRATIONS ION PIPING~Sstem Penetration No.Valve No.Valve Position Valve Indication Position Operator In Control Relatfve to Room Contafnvent Position At Normal Cold Ismedfate OBeratfon Shutdovn Postaccfdent'oser Failure Trip on CIS Maxi sans Isolation Time CFSAR~Ff re Classv Notes See<<nd ot table s Hydrocen Monitor Instrumentatfon Lines Main Steam from A Steam Generator Main Steam Iron B Steam Generator 332c 401 402 921 922 923 924 3505A 3507 3517 3519 3521 3504A 3506 3516 3518 3520 Cate Cate Cate Cate Cate Cate Swine Check Check Cate Cate Cate Suing Check Check Cate Solenoid Solenoid Solenoid Solenoid Motor Manual Air NA Manual Motor Manual Air NA Manual Both Both Both Both R/0 No R/C NA No R/0 No R/0 NA No Outside Outside Outside 0 teide Outside Outsfde Outside Outside Outside Outside Outside Outside Outside Outsfde C C C C C 0 0 0 0 C C C C C C C C 0 C C C C 0 C C C C 0 0 C C 0 0 0 C C 0 AI NA AI NA NA AI NA AI NA NA yes yes yss Tes No NA No NA NA No NA No NA NA 6.2 74 6.2 74 6.2 74 6.2 74 6.2 75 6.2 75 6.2 75 6'75 6.2 75 6.2 75 6.2 75 6.2 75 6'75 6.2"75 21 21 21 21 11 11 ll ll ll ll ll 11 ll ll Fcedvater Line 403 to A Steam Generator 3993 3995 4008C 4083 4885 4011 Check Clohe Check Check Globe Globe NA Manual NA NA Manual Manual NA No NA NA No No Outside Outside Outside Outside Outside Outside 0 0 C C 0 0 C 0 C C 0 0 C 0 0 0 0 0 NA NA NA NA NA NA NA NA NA NA NA NA 6.2 76 6.2-76 6.2 76 6.2-76 6.2-76 6.2-76 11 11 11 11 11 11 1'eedvater line to B Steam Generator Personnel Hatch Equfpcent Hatch 404 1080 2000 3992 3994 40000 4084 4806 4012 Check Clohe Check Check Globe Clohe NA Manual NA NA Manual Manual NA No NA NA No No Outside Outside Outside Outside Outside Outside Both 0 0 C C 0 0 C 0 C C 0 0 0/C 0/C C 0 0 0 0 0 NA NA NA NA NA'NA NA 6.2-76 6.2-76 6.2-76 6.2-76 6.2-76 6.2-76 3.8-31 3.8-30 11 11 ll 11 11 11 Safety Analysis NSL-0000-SA024 Page 14c4 Revision 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. | |||
(2) | (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. | ||
(3) | 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. | |||
(4) | (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 IOCFR50, Appendix J lea'kage testing, nor does ft require a maximum isolation tfme.(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.(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).I k (13)(14)(15)(16)(18)The pressure transmitter assexbly, by its design, provides a containment pressure boundary.The fntegrity of this boundary is verified by annual leakage tests.Operations fs instructed to manually close AOV 745 following a Containment Isolation Signal until an automatic signal 1s installed through the necessary modfficatfon. | ||
Verification | Sump]ines are fn operation and filled with Ifufd foffowfng an accident)therefore. | ||
(6) | 10CFR50, Appendix J leakage testing is not required for this penetratfon. | ||
Therefore, | See L.D.Nhfte Jr.letter to D.L.Ziemann, USNRC, dated September 21, 1978.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.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 NSL-0000-SA024 Page 14h Revision 1 t t'I y 0 Attachment B Safety Analysis NSL-0000-SA024 Page 15 Revision 0 Date 09 24 90 The blanks or"-" within columns were replaced with"NA".Typographical clarification only.No technical change.2.(1)The blanks or"-" for the Position At columns were replaced with the representative position;(2)The"No" listed under Position Indication in Control Room was replaced with"NA".(1)(2)The valve position and"NA" are more representative of the penetration configuration. | |||
Sump] | In addition, consistency is maintained within the table.No technical change.3.The"AI" or blank for the Power Failure column for manual valves was replaced with"NA".The"NA" is more representative of the penetration configuration since a manual valve does not receive any motive power.No technical change..4.was replaced with"NA".The"NA" is more representative of the penetration configuration. | ||
10CFR50, | In addition, consistency is maintained within the table.No technical change.5.The blank or"No" for Maximum Isolation Time was replaced with"NA".The"NA" is more representative of the penetration configuration. | ||
In addition, consistency is maintained within the table.No technical change.Safety Analysis NSL-0000-SA024 Page 16 Revision 0 Date 09 24 90 | |||
Therefore, | |||
~~J~ | ~~J~ | ||
Added"Cold" | Added"Cold" to Position At Shutdown column heading.Minor clarification for consistency with Technical Specifications. | ||
No technical change.2.(1)Added"Immediate" to Position At Postaccident column heading;(2)Added Note"a" (1)(2)Clarification of column since valve position can be potentially changed during post accident recovery operations. | |||
Column now provides clear definition of penetration configuration following receipt of a CIS.3.table;(2)Deleted definitions for"W" and"G" from table Legend.(1)(2)Column did not provide any information relevant to table.Fluid type can be inferred from~S stem column.4 associated Note"c" from table.Column did not provide any information relevant to table.5.Added definitions for"AOV","CV","MOV","MV", and"SOV" to table Legend.Correction of typographical omission.No technical change.6.(1)Modified Position Indication in Control Room column to reflect type of indication instead of"Yes" and"No";(2)Added definition for"R/G" and"Status" to table Legend."Both" indicates that a red/green light and status light exists.(1)(2)The type of control room indication is more representative of the system configuration. | |||
This is a clarification only.No technical change.7.Moved Table Heading Notes"a","b","c", and"d" to first page of table.Minor format change only.No technical change.Safety Analysis NSL-0000-SA024 Page 17 Revision 0 | |||
~c 8.(1)Renamed Note"a" to"b";(2)Added"nor instrument delay time" to end of note.(1)(2)Minor clarification-only.Note is now consistent with Standard Review Plan Section 6.2.4.No technical change.9.Renamed Note"b" to"c".No technical change.10.Deleted"Line" from~S stem column heading.No technical change.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. | |||
~c 8.(1) | No technical change.=Safety Analysis NSL-0000-SA024 Page 18 Revision 0 Date 09 24 90 | ||
~l I~ | |||
~ | Penetration 2-Added penetration and necessary information to the table.This spare penetration was modified to provide access for steam generator inspection and maintenance cabling during refueling outages to enhance containment closure during midloop operations. | ||
Penetration 2- | No new valves were added.2.Penetration 29-(1)Global Note 1;(2)Added Note 2.(1)(2)No technical change.3.Penetration 100-(1)Global Notes 1, 2, and 4;(2)Added Note 4;(3)Changed Position At Immediate Postaccident from"0/C" to"C".(1)(2)No technical change.(3)Update for better representation of system configuration since the Charging System is isolated upon receipt of a SI signal.4~Penetration 101-(1)Global Notes 1, 2, 4, and 5;(2)Added Note 4;(3)Added"3B" under Class for valve 889B;(4)Reordered penetration valves.(1)(2)No technical change.(3)Correction of typographical omission.No technical change.(4)Valves now in numeric order.No technical change.5.Penetration 102-(1)Global Notes 1, 2, 4, and 5;(2)Added Note 4.(1)(2)No technical change.6.Penetration 103-Deleted valve 5129 (entire line in table)and replaced with Blind Flange.Replaced Note of"No longer in use" to reflect accurate configuration status of Blind Flange.The use of the Blind Flange is consistent with the previously listed locked-closed manual valve.Safety Analysis NSL-0000-SA024 Page 19 Revision 0 | ||
~c>~ | ~c>~ | ||
7.Penetration 105-(1) | 7.Penetration 105-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.8.9.10.Penetration 106-(1)Global Notes 1, 2, and 4;(2)Added Note 4;(3)Changed"supply" to"Inlet" under~S stem.Penetration 107-(1)Changed Position Indication In Control Room from"Yes" to"Status" for both valves;(2)Changed Position At Cold Shutdown from"0" to"0/C" for both valves.Penetration 108-(1)Added"and Excess Letdown to VCT" under~Sstem;(2)Changed Position Indication In Control Room from"Yes" to"Both";(3)Changed'osition At Cold Shutdown from"0" to"0/C";(4)Added Note 4;(5)Added Note 6.(1)(2)No technical change.(3)Minor clarification only.No technical change.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration. | ||
(1)Consistency | (1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration since this line may or may not be used during cold shutdown conditions. | ||
(4)(5) | (4)(5)No technical change.Penetration 109-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.12.Penetration 110a-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.Safety Analysis NSL-0000-SA024 Page 20 Revision 0 Date 09 24 90 | ||
~4~ | ~4~ | ||
13.Penetration 110b-(1) | 13.Penetration 110b-(1)Global Notes 3 and 4;(2)Added Note 4;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to nLCss (1)(2)No technical change.(3)Consistency with Ginna Administrative Control.14.Penetration 111-(1)Added Note 7 to both valves;(2)Added Note 8 to valve 720;(3)Added Note 4 to both valves;(4)Changed Position Indication In Control Room from"Yes" to"R/G" for MOV 720;(5)Added valve 959 and necessary information. | ||
(1)Consistency | (1)Consistency with Technical Specifications. | ||
(2)(3) | (2)(3)No technical change.(4)Minor clarification only.No technical change.(5)Valve receives containment isolation signal and was previously missing from the table.15.Penetration 112-(1)Deleted valves 204A and 821 (entire line in table)and replaced with valves 200A, 200B, and 202;(2)Added valve 427 and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"Both" for valve 371;(4)Changed Position At Immediate Postaccident from"0" to"C" for valve 371.(1)(2)Present configuration status;the three new valves enable explicit compliance with GDC 55 vs.the use of redundant outboard isolation valves.The 200A, 200B, 202, and 427 valves have been successfully tested.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration since letdown is isolated upon receipt of a SI signal.Penetration 113-(1)Global Notes 1, 2, and 4;(2)Added Note 4 to both valves;(3)Reordered penetration valves.(1)(2)No technical change.(3)Valves now in numeric order.No technical change.1 Safety Analysis NSL-0000-SA024 Page 21 Revision 0 Date 09 24 90 17.Penetration 119-(1)Global Notes 1, 2, 4, and 5;(2)Changed Position Indication In Control Room from"No"-to"R/G" for valve 9704A;(3)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical change.(3)Valves now in numeric order.No technical change.18.Penetration 120a-(1)Global Notes 1, 2, and 4 for valve 8623;(2)Changed valve 846 from"Gate" to"Globe";(3)Changed Position Indication In Control Room from"Yes" to"Both" for valve 846;(4)Changed Position At Normal 0 eration from"0/C" to"C" for valve 846;(5)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration. | ||
This valve remains closed unless the accumulator nitrogen blanket pressure decreases. | |||
(5) | (5)Valves now in numeric order.No technical change.19.Penetration 120b-(1)Changed Position Indication In Control Room from"Yes" to"Status" for valve 539;(2)Changed Position At Normal 0 eration from"0/C" to"C" for valve 539;(3)Global Notes 3&4 for valve 546.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration. | ||
(3) | (3)No technical change.20.Penetration 121a-(1)Global Notes 1, 2, and 4 for valve 528;(2)Changed valve 547 from"Diaphragm" to"Globe";(3)Changed Position At Immediate Postaccident from"0" to"LC" for valve 547;(4)Changed Position At Normal (5)Global Notes 3 and 4 for valve 547;(6)Deleted reference to"old" Note 9;(7)Added Note 12 to valve 547.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Consistency with Ginna Administrative Control.(4)Update for better representation of system configuration. | ||
No technical change.(5)No technical change.(6)Correction of typographical error.No technical change.(7)No technical change.Safety Analysis NSL-0000-SA024 Page 22 Revision 0 21.Penetration 121b-(1)Changed Position Indication In Control Room from"Yes" to"Both" for valve 508;(2)Changed Position At Normal 0 eration from"0/C" to"C" for valve 508;(3)Changed Position At Normal 0 eration from"C" to"0/C" for valve 529;(4)Global Notes 1, 2, and 4 for valve 529;(5)Reordered penetration valves.(1)Minor clarification only.No technical change.(2)(3)Update for better representation of system configuration. | |||
(4) | (4)No technical change.(5)Valves now in numeric order.No technical change.22.Penetration 121c-(1)Global Note 1 for PT945;(2)Global Notes 3 and 4 for valve 1819A;(3)Added"Gate" under 8 9 (1)(2)No technical change.(3)Correction of typographical omission.No technical change.23.Penetration 121d-(1)Global Note 1 for PT946;(2)Global Notes 3 and 4 for valve 1819B.(1)(2)No technical change.24.Penetration 123 (bottom)-(1)Added"to" before"Gas Analyzer Line" under~sstem;(2)Global Notes 3 and 4 for 1655;(3)Changed valve 1789 from"Globe" to"Diaphragm"; | ||
(4)Changed Position Indication In Control Room from"Yes" to"Status" for valve 1789;(5)Changed Position At Normal 0 eration from"0/C" to"0" for valve 1789;(6)Added valve 1600A;(7)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)No technical change.(3)Correction of typographical error.No technical change.(4)Minor clarification only.No technical change.(5)Update for better representation of system configuration since this line remains open.(6)Valve receives containment isolation signal and was previously missing from the table.(7)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 23 Revision 0 Date 09 24 90 25.Penetration 123 (top)-(1)Global Notes 1, 2, 4, and 5;(2)Changed Position Indication In Control Room from"No" to"R/G" for valve 9704B.(1)No technical change.(2)Minor clarification only.No technical change.26.Penetration 124a-(1)Global Notes 1, 2, and 4 for valve 743;(2)Changed Position At Immediate Postaccident from"0" to"C" for valve 743;(3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 745;(4)for valve 745;(5)Changed Maximum Isolation Time from"60" to"NA" for valve 745;(6)Changed Position At Cold Shutdown from"0" to"C" for valve 745.(1)No technical change.(2)Update for better representation of system configuration. | |||
(4) | Operations is instructed to manually isolate this line following receipt of a containment isolation signal.(3)Minor clarification only.No technical change.(4)(5)Correction of typographical error.See letter from R.Mecredy, RG&E, to A.Johnson, NRC, dated July 9, 1990.(6)Update for'etter representation of system configuration since excess letdown is not operational during cold shutdown conditions. | ||
Operations | 27.Penetration 124b-(1)Added"to" before"C Fan" under~astern;(2)Added four valves;(3)Changed Position At Cold Shutdown from"C" to"LC" for all four valves;(4)Changed Position At Immediate Postaccident from"0/C" to"LC" for all four valves;(5)Global Notes 3 and 4.(1)Minor clarification. | ||
27.Penetration 124b-(1)Added"to"before" | No technical change.(2)Correction of typographical omission.No technical change.(3)(4)Consistency with Ginna Administrative Control.(5)No technical change.Safety Analysis NSL-0000-SA024 Page 24 Revision 0 Date 09 24 90 28.Penetration 125-(1)Changed Position Indication In Control Room from"Yes" to"R/G";(2)Changed Position At Cold Shutdown from"0" to"C";(3)Added Note 4.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions. | ||
(3)No technical change.29.Penetration 126-(1)Changed Position Indication In Control Room from"Yes" to"R/G";(2)Changed Position At Cold Shutdown from"0" to"C";(3)Added Note 4.(1)Minor clarification only.No technical change;(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions. | |||
(3)No technical change.30.Penetration 127-(1)Changed Position Indication In Control Room from"Yes" to"R/B" for valve 749A;(2)Changed Position At Cold Shutdown from"0" to"C" for valve 749A;(3)Global Notes 1, 2, and 4 for valve 750A;(4)Changed Maximum Isolation Time from"60" to"NA" for valve 749A.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions.. | |||
(3) | (3)No technical change.(4)Correction of typographical error.No technical change.31.Penetration 128-(1)Changed Position Indication In Control Room from"Yes" to"R/B" for valve 749B;(2)Changed Position At Cold Shutdown from"0" to"C" for valve 749B;(3)Global Notes 1, 2, and 4 for valve 750B;(4)Changed Maximum Isolation Time from"60" to"NA" for valve 749B.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions. | ||
(3) | (3)No technical change.(4)Correction of typographical error.No technical change.Safety Analysis NSL-0000-SA024 Page 25 Revision.0 32.Penetration 129-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 1787;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valves 1786 and 1787;(3)Changed Position at Cold Shutdown from"0" to"C" for valves 1786 and 1787.(4)Global Notes 1, 2, and 4 for valve 1713;(5)Global Notes 2, 3, and 4 for valve 1793;(6)Deleted"MOV 1793 used for long-term isolation" under Notes and replaced with Note 12;(7)Added"NA">>93: Added"Outside" under Position Relative To Containment for valve 1793;(9)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration. | ||
(3) | (4)(5)No technical change.(6)Minor clarification. | ||
(3) | No technical change.(7)Correction of typographical omission.No technical change.(8)Correction of typographical omission.No technical change.(9)Valves now in numeric order.No technical change.33.Penetration 130-(1)Changed Position Indication In Control Room from"Yes" to"Both";(2)Corrected associated valve number to 814.(1)Minor clarification only.No technical change.(2)Correction of typographical error.No technical change.34.Penetration 131-(1)Changed Position Indication In Control Room from"Yes" to"Both";(2)Corrected associated valve number to 813.(1)Minor clarification only.No technical change.(2)Correction of typographical error.No technical change.Safety Analysis NSL-0000-SA024 Page 26 Revision 0 | ||
0 32.Penetration 129-(1) | ~'I 0 0 35.Penetration 132-(1)Changed Maximum Isolation Time from"2" to"3" for both valves;(2)Changed Position At Normal"/'971;(3)Changed Position At Cold Shutdown from"C" to"0/C" for both valves;(4)Changed Position Indication In Control Room from"Yes" to"Both" for both valves.(1)Consistency with Technical Specifications. | ||
(4)(5) | Valve design allows closure as rapid as 2 (two)seconds.Minimum closure time required by Technical Specifications is 5 (five)seconds with instrument delay.(2)(3)Update for better representation of system configuration. | ||
Mini-Purge system only designed for use during shutdown conditions. | |||
(4)Minor clarification only.No technical change.36.Penetration 140-(1)Added Note 6;(2)Added Note 7;(3)Changed Position Indication in Control Room from"Yes" to IIR/Gll (1)Consistency with Technical Specification Table 3.6-1 Note 20.(2)No technical change.(3)Minor clarification only.No technical change.37.Penetration 141-(1)Deleted valve 851A (entire line in table);(2)Added valve 1813A and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 850A;(4)Added Note 8 to valve 1813A.(1)Valve 851A does not meet the selection criteria of lOCFR50 Appendix J, Section IIH, items.1 through 4.Therefore, valve was deleted from table.(2)Valve 1813A was previously missing from table.(3)Minor clarification only.No technical change.(4)No technical change.Safety Analysis NSL-0000-SA024 Page 27 Revision 0 l | |||
38.Penetration 142-(1)Deleted valve 851B (entire line in table);(2)Added valve 1813B and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 850B;(4)Added Note 8 to valve 1813B.(1)Valve 851B does not meet the selection criteria of 10CFR50 Appendix Jg Section IIH, items 1 through 4.Therefore, valve was deleted from table.(2)Valve 1813B was previously missing from table.(3)Minor clarification only.No technical change.(4)No technical change.39.Penetration 143-(1)Changed Position Indication In Control Room from"Yes" to"Status" for all three valves;(2)Changed Position At Normal 0 eration from"0/C" to"0" for valves 1003A and 1003B;(3)Reordered penetration valves.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration. | |||
~' | (3)Valves now in numeric order.No technical change.40.Penetration 201top-Global Notes 3 and 4.No technical change.41.Penetration 20lbottom-Global Notes 3 and 4.No technical change.Safety Analysis NSL-0000-SA024 Page 28 Revision 0 42.Penetration 202-(1)Changed valves 1076B and 1084B from"Globe" to"Diaphragm"; | ||
(2)Changed Position At Normal 0 eration Cold Shutdown Immediate Postaccident from"C" to"LC" for valves 1076B and 1084B;(3)Global Notes 3 and 4 for valves 1076B and 1084B;(4)Added"No" under Position Indication in Control Room for valves 1076B and 1084B;(5)Changed Valve No.for IV-3B and IV-5B to 10211S1 and 10213S1, respectively; (6)Added"Status" under Position Indication in Control Room for valves 10211S1&10213S1;(7)Changed Position At Power Failure from"-" to"FC" for valves 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.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.(4)Correction of typographical omission.No technical change.(5)Update to new valve number only.No technical change.(6)Correction of typographical omission.No technical change.(7)(8)Update for better representation of system configuration. | |||
Mini-Purge | Valves receive containment isolation signal.(9)Correction of typographical error.No technical change.(10)Valves now in numeric order.No technical change.43.Penetration 203a-(1)Included separate lines in table for valves 1819C and 1819D;(2)Added"Outside" to Position Relative to Containment for PT947 and PT948;(3)Added"Globe" under Valve~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.(1)Minor clarification | ||
(4) | -there are two valves.No technical change.(2)(3)Correction of typographical omission.No technical change.(4)(5)No technical change.Safety Analysis NSL-0000-SA024 Page 29 Revision 0 jÃo+g)44.Penetration 203b-(1)Global Notes 3 and 4;(2)Added"Diaphragm" under Valve~T e for all four valves;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to"LC" for all four valves.(1)No technical change.(2)Correction of typographical omission.No technical change.(3)Consistency with Ginna Administrative Control.45.Penetration 204-(1)Added Note 2 to Blind Flange;(2)Global Note 1 for Blind Flange;(3)Changed Position Indication in Control Room from"Yes" to"Both" for valve 5869;(4)Changed position At Normal 0 eration from"0/C" to"C" for valve 5869;(5)Changed Position At Cold Shutdown from"0" to"0/C" for 5869;(6)Changed Maximum Isolation Time from"5" to"NA" for valve 5869;(7)Added Note 19.(1)(2)No technical change.(3)Minor clarification only.No technical change.(4)(5)Update for better representation of system configuration. | ||
38.Penetration 142-(1) | Penetration only used during cold shutdown conditions. | ||
(3) | Mini-purge system now used in place of purge system.(6)The Blind Flange acts as the isolation boundary.Therefore, no isolation'time is required for the valve.(7)No technical change.46.Penetration 205-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 966C;(2)Added valve 955 and necessary information; (3)Changed Position Indication in Control Room from"Yes" to"Status" for valve 966C;(4)Changed Position At Normal 0 eration and Position At Cold Shutdown from"0/C" to"C" for valve 966C;(5)Global Notes 3 and 4 for valve 956D;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Valve receives containment isolation signal and was previously missing from the table.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration. | ||
- | Sampling system normally isolated.(5)No technical change.(6)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 30 Revision 0 Date 09 24 90 | ||
(2) | |||
- | |||
Penetration | |||
Mini-purge | |||
Therefore, | |||
(5) | |||
49 Penetration 207a-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 966A;(2)Added valve 951 and necessary information; (3)Changed Position Indication in Control Room from"Yes" to"Status" for valve 966A;(4)Changed Position At Normal 0 eration and Position At Cold Shutdown from"0/C" to"C" for valve 966A;(5)Global Notes 3 and 4 for valve 956F;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Valve receives containment isolation signal and was previously missing from the table.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration. | |||
Sampling system normally isolated.(5)No technical change.(6)Valves now in numeric order.No technical change.50.Penetration 207b-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 5736;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5736;(3)Changed Position At Normal 0 eration from"0/C" to"0" for valve 5736;(4)Changed Position At Cold Shutdown from"0/C" to"C" for valve 5736;(5)Global Notes 3 and 4 for 5734;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)(4)Update for better representation of system configuration. | |||
(5) | (5)No technical change.(6)Valves now in numeric order.No technical change.51.Penetration 209top-(1)Global Notes 3 and 4;(2)Reordered penetration valves.(1)No technical change.(2)Valve order now consistent with other penetrations. | ||
(5) | No technical change.52.Penetration 209bottom-(1)Global Notes 3 and 4;(2)Reordered penetration valves.(1)No technical change.(2)Valve order now consistent with other penetrations. | ||
No technical change.Safety Analysis NSL-0000-SA024 Page 32 Revision 1 53.Penetration 210-(1)Added"A&B" before"Reoombiners" under~3 stem;(2)Added Position Indication in Control Room to"Status" for all solenoid valves;(3)Added"Yes" under~Tri on CIS for all solenoid valves;(4)Added valves 10214S1 and 10215S and necessary information; (5)Changed Position At Power Failure from"-" to"FC" for all solenoid valves;(6)Changed Position At Normal 0 eration Cold Shutdown Immediate Postaccident from"C" to"LC" for 1080A;(7)Global Notes 3 and 4 for valve 1080A;(8)Changed Valve No.for IV-2A and IV-2B to 10214S and 10215S1, respectively; (9)Added Note 18 to solenoid valves;(10)Changed Maximum Isolation Time from"NA" to"3" for all solenoid valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Correction of typographical omission.No technical change.(4)Valve receive containment isolation signal and was previously missing from the table.(5)Update for better representation of system configuration. | |||
-(1) | Valves receive containment isolation signal.(6)Consistency with Ginna Administrative Control.(7)No technical change.(8)Update to new valve number only.No technical change.(9)No technical change.(10)Correction of typographical error.No technical change.-54.Penetration 300-(1)Added Note 19 for both valve and flange;(2)Added Note 2 to Blind Flange;(3)Global Note 1 for Blind Flange;(4)Changed Position At Normal 0 eration from"0/C" to"C" for valve 5879;(5)Changed Position At Cold Shutdown from"0" to"0/C" for valve 5879;(1)No technical change.(2)Consistency with Technical Specifications. | ||
No technical change.(3)(4)Update for better representation of system configuration. | |||
Penetration only used during cold shutdown conditions. | |||
Mini-purge system now used in place of purge system.Safety Analysis NSL-0000-SA024 Page 33 Revision 0 Date 09 24 90 55.Penetration 301-(1)Global Notes 3 and 4;(2)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"0" to"LC" for both valves;(3)Added Note 5 to both valves.(1)No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.56.Penetration 303-(1)Global Notes 3 and 4;(2)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"0" to"LC" for both valves;(3)Added Note 5 to both valves;(4)Changed both valves from"Diaphragm" to"Globe";(5)Reordered penetration valves.(1)No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.(4)Correction of typographical error.No technical change.(5)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 34 Revision 0 Date 09 24 90 57.Penetration 304-(1)Changed valves 1076A and 1084A from"Solenoid" to"Diaphragm"; | |||
(2)Changed Position At Normal 0 eration Cold Shutdown and Immediate Postaccident from"C" to"LC" for valves 1076A and 1084A;(3)Added"No" under Position Indication In Control Room for valves 1076A and 1084A;(4)Global Notes 3 and 4 for valves 1076A and 1084A;(5)Changed Valve No.for IV-3A and IV-5A to 10205S1 and 10209S1, respectively; (6)Added"Status" under Position Indication in Control Room for valves 10205Sl&10209S1;(7)Changed Position At Power Failure from"-" to"FC" for valves 10205Sl and 10209S1;(8)Changed~Tri'n CIS from"No" to"Yes" for valve 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.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)Correction of typographical omission.No technical change.(4)No technical change.(5)Update to new valve number only.No technical change.(6)Minor clarification only.No technical change.(7)(8)Update for better representation of system configuration. | |||
Penetration | Valves receive containment isolation signal.(9)No technical change.(10)Correction of typographical error.No technical change.(11)Valves now in numeric order.No technical change.58.Penetration 305a (bottom)-(1)Changed~Sstem to"Containment Air Sample Out";(2)Changed Maximum Isolation Time from"NA" to"60" for valve 1597;(3)Changed valve 1596 from"Diaphragm" to"Globe";(4)Global Notes 3 and 4 for valve 1597;(5)Changed Position Indication in Control Room from"Yes" to"Both" for valve 1597;(6)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.No technical change.(2)Consistency with Technical Specification Table 3.6-1.(3)Correction of typographical error.No technical change.(4)No technical change.(5)Minor clarification only.No technical change.(6)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 35 Revision 0 59.Penetration 305b (top)-(1)Changed~S stem to"Containment Air Sample Inlet";(2)Changed Maximum Isolation Time from"NA" to"60" for valve 1599;(3)Changed Position Indication in Control Room from"Yes" to"Both" for valves 1598 and 1599;(4)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.(2)Consistency with Technical Specification Table 3.6-1.(3)Minor clarification only.No technical change.(4)Valves now in numeric order.No technical change.60.Penetration 305c-<1)Changed~S stem to"Containment Air Sample Postaccident"; | ||
Mini-purge | for all six valves;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to"LC" for all six valves;(4)Global Notes 3 and 4;(5)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.(2)Correction of typographical omission.No technical change.(3)Consistency with Ginna Administrative Control.(4)No technical change.(5)Valves now in numeric order.No technical change.61.Penetration 307-(1)Switched Valve No.for valves 9227 and 9229;(2)Added"Gate"-under Valve 0 erator T e for valve 9227;(3)Global Notes 1, 2, and 4 for valve 9229;(4)Changed Position Indication in Control Room from"Yes" to"Both" for valve 9227.(1)Correction of typographical error.No technical change.(2)Correction of typographical omission.No technical change.(3)No technical change.(4)Minor clarification only.No technical change.62.Penetration 308-(1)Changed Valve No.to 4629;(2)Global Notes 3 and 4;(3)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(4)Changed Position At Cold Shutdown from"0" to"0/C" (5)Added Note 17.(1)Correction of typographical error.No technical change.(2)No technical change.(3)Consistency with Ginna Administrative Control.(4)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown.(5)No technical change.Safety Analysis NSL-0000-SA024 Page 36 Revision 0 | ||
(2) | |||
(5) | |||
:,P><><~!~ | :,P><><~!~ | ||
A.,gyes-.gory | A.,gyes-.gory | ||
~gg,~:>FQKQ<,.4idsi, 63.Penetration 309-(1) | ~gg,~:>FQKQ<,.4idsi, 63.Penetration 309-(1)Changed Maximum Isolation Time from"2" to"3" for both valves;(2)Changed Position Indication in Control Room from"Yes" to"Both" for both valves;(3)Reordered penetration valves.(1)Consistency with Technical Specifications. | ||
Valve design allows closure as rapid as 2 (two)seconds.Minimum closure time required by Technical Specifications is 5 (five)seconds.(2)Minor clarification only.No technical change.(3)Valves now in numeric order.No technical change.64.Penetration 310a-(1)Changed valve 7141 from"Diaphragm" to"Gate";(2)Changed Position At Immediate Postaccident from"C" to"LC" for valve 7141;(3)Global Notes 3 and 4 for valve 7141;(4)Global Notes 1, 2, and 4 for valve 7226;(5)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)(4)No technical change.(5)Valves now in numeric order.No technical change.65.Penetration 310b-(1)Changed valve 5392 from"Diaphragm" to"Globe";(2)Changed Position Indication in Control Room from"Yes" to"Both" for valve 5392;(3)Changed Position At Cold Shutdown from"C" to"0" for valve 5393;(4)Global Notes 1, 2, and 4 for 5393;(5)Added"0" under Position At Cold Shutdown for valve 5392;(6)Added"C" under Position At Immediate Postaccident for valve 5392;(7)Changed Position at Power Failure from"-" to"FC" for valve 5392;(8)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration since IA is used during cold shutdown conditions. | |||
(4) | (4)No technical change.(5)(6)(7)Update for better representation of system configuration. | ||
Valve receives containment isolation signal.(8)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 37 Revision 0 Date 09 24 90 | |||
'I~ | 'I~ | ||
Penetration 311-(1) | Penetration 311-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4.(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions. | ||
(2)Consistency | (2)Consistency with Ginna Administrative Control.(3)No technical change.67.Penetration 312-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4~(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions. | ||
(2)Consistency | (2)Consistency with Ginna Administrative Control.(3)No technical change.68.Penetration 313-(1)Added"Blind" Global Notes 1, 2, and 4 for Blind Flange;(3)Changed Position Indication in Control Room from"Yes" to"Status" from"No" to"Yes" for valve 7444;(5)Added Note 19.(1)Correction of typographical omission.No technical change.(2)No technical change.(3)Minor clarification only.No technical change.(4)Correction of typographical error.No technical change.(5)No technical change.69.Penetration 315-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4.(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions. | ||
(2)Consistency with Ginna Administrative Control.(3)No technical change.Safety Analysis NSL-0000-SA024 Page 38 Revision 0 Date 09 24 90 | |||
(2)Consistency | |||
74.Penetration 320-(1) | 74.Penetration 320-(1)Global Notes 3 and 4;(2)Changed Position At Normal Postaccident from"0" to"LO";(3)Changed Position At Cold Shutdown from f!Off to nO/Ctt (1)No technical change.(2)Consistency with Ginna Administrative Control.(3)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions. | ||
75.Penetration 321-(1) | 75.Penetration 321-(1)Global Notes 3 and 4 for valve 5701;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5738;(3)Changed Position At Cold Shutdown from"C" to"0/C" for valve 5738;(4)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical. | ||
change.(3) | change.(3)Update for better representation of system configuration. | ||
(4) | (4)Valves now in numeric order.No technical change.76.Penetration 322-(1)Global Notes 3 and 4 for valve 5702.(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5737;(3)Changed Position At Cold Shutdown from"C" to"0/C" for valve 5737;(4)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration. | ||
(4) | (4)Valves now in numeric order.No technical change.77.Penetration 323-(1)Global Notes 3 and 4;(2)Changed Position At Normal Postaccident from"0" to"LO";(3)Changed Position At Cold Shutdown from"0" to"0/C" (1)No technical'change.(2)Consistency with Ginna Administrative Control.(3)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions. | ||
'change.(2)Consistency | Safety Analysis NSL-0000-SA024 Page 40 Revision 1 Date 10 3 90 78.Penetration 324-(1)Changed valve 8418 from"Diaphragm" to"Globe";(2)Changed Position At Cold Shutdown from"0" to"0/C" for valve 8418;(3)Changed Position Indication in Control from"Yes" to"Both" for valve 8418;(4)Global Notes 1, 2, and 4;(5)Changed Maximum Isolation Time from"NA" to"60" for valve 8418;(6)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Update for better representation of system configuration. | ||
(3)Minor clarification only.No technical change.(4)No technical change.(5)Correction of typographical error.No technical change.(6)Valves now in numeric order.No technical change.79.Penetration 332a-(1)Global Note 1 for pressure transmitters; (2)Added"Globe" h valves;(3)Global Note 3 for the manual valves;(4)Reordered penetration valves.(1)No technical change.(2)Correction of typographical omission.No technical change.(3)No technical change.(4)Valves now in numeric order.No technical change.80.Penetration 332b-Deleted entire penetration from table.Penetration has double isolation and meets the criteria, for a test connection. | |||
(3) | 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" under UFSAR Fi ure for all valves other than 922.(2)Changed Position Indication in Control Room from"Yes" to"Both" for all four valves;(3)Changed Position At Immediate Postaccident from"0/C" to"C" for all valves.(1)Correction of typographical omission.No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration. | ||
System isolated upon receipt of containment isolation signal.Safety Analysis NSL-0000-SA024 Page 41 Revision 0 Date 09 24 90 82.Penetration 401-(1)Added Note 11 to all valves other than 3517;(2)Changed 3517;(3)Changed Position Indication in Control Room from"Yes" to"R/G" for valves 3505A and 3517;(4)Global Notes 1, 2, 3, 4, and 5;(5)Reordered penetration valves.(1)Correction of typographical omission.No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)No technical change.(5)Valves now in numeric order.No technical change.83.Penetration 402-(1)Added Note 11 to all valves other than 3516 and 3518;(2)valve 3516;(3)Changed Position Indication in Control Room from"Yes" to"R/G" for valves 3504A and 3516;(4)Global Notes 1, 2, 3, 4, and 5;(5)Reordered penetration valves.(1)Correction of typographical omission.No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)No technical change..(5)Valves now in numeric order.No technical change.84.Penetration 403-(1)Global Notes 1, 2, 3.from"6.2-75" to"6.2-76" for valve 3995;(3)Added"6.2-76" under UFSAR Ficiure for all valves after valve 3995;(4)Added Note 11 to all valves other than valve 3995;(5)Added"4" under Class for all valves other than 3995;(6)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)(4)(5)Correction of typographical omission.No technical change.(6)Valves now in numeric order.No technical change.85.Penetration 404-(1)Global Notes 1, 2, from"6.2-75" to"6.2-76" for valve 3994;(3)Added Note 9 to all valves other than 4000D;(4)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Correction of typographical omission.No technical change.(4)Valves now in numeric order.No technical change;Safety Analysis NSL-0000-SA024 Page 42 Revision 0 86.Penetration 1000-(1)Global Notes 1, 2, 4, and 5;(2)Added"Both" to Position Relative to Containment; (3)(1)No technical change.(2)(3)Correction of typographical omission.No technical change.87.Penetration 2000-(1)Global Notes 1, 2, 4, and 5;(2)Added"Both" to Position Relative to Containment; (3)"3.8-3 IV'1)No technical change.(2)(3)Correction of typographical omission.No technical change.Safety Analysis NSL-0000-SA024 Page 43 Revision 0 (1)Deleted last sentence of"old" Note 1 and moved it to"new" Note 2;(2)Renumbered remaining"old" Note 1 as Note 3.(1)(2)The deleted sentence of the note is still applied to necessary penetrations. | |||
Therefore, | No technical change.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" Note 4;(2)Modified last sentence to reflect system configuration; (3)Renumbered"old" Note 4 as Note 6.(1)These two sentences only duplicated UFSAR text.No technical change.(2)Sentence now accurately reflects 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 NSL-0000-SA024 Page 44 Revision 0 Date 09 24 90 9.(1)Modified"old" Note 9;(2)Renumbered"old" Note 9 as Note 13.(1)(2)Minor clarification only.Note 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)Renumbered to"new" Note 15.Minor clarification only.change.No technical 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" Note 14 and moved it to"new" Note 16;(2)Modified remaining"old" Note 14;(3)Renumbered"old" Note 14 as Note 17.(1)The deleted sentence of the note is still applied to necessary penetrations. | ||
No technical change.(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)Renumbered"old" note 17 as Note 21.(1)(2)Minor clarification of note only.No technical change.Safety Analysis NSL-0000-SA024 Page 45 Revision 0 4 | |||
32.Added Note 20.Minor clarification only.Note provides additional information related to penetration's use.No technical change.Safety Analysis NSL-0000-SA024 Page 48 Revision 0 Date 09 24 90 18.(1)Modified"old" Note 18;(2)Renumbered"old" Note 10 as Note 11.(1)(2)Minor clarification of note 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 NSL-0000-SA024 Page 46 Revision 0 k | |||
25.Added Note 9.%RP)>h~r..'".'~>Y&Q<<>.vÃF>N4!jFrvca44AYY+cPc>'~>>@48<44~AAC NK+AA~>~>Y4s.."4%gggg 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 NSL-0000-SA024 Page 47 Revision 0 Chanches Table 1 Technical Specification Changes Effect Section 3.6.3.1 references UFSAR Table 6.2-13 instead of Technical Specification Table 3.6-1.No technical change.2.Table 3.6-1 removed from Technical Specifications and information placed in UFSAR Table 6.2-13.Valve listing remains in a licensee controlled document under 10CFR50.59 program.3.4.Revised inoperable definition of Section 3.6.3.1.Removed note associated with Technical Specification 3.6.5.No technical change.Clarification only consistent with 10CFR50 Appendix J.Mini-purge valves have been installed so the Technical Specification can be considered effective. | |||
No technical change.5.Added"Pt" and necessary~~~~definitions to Technical Specification 4.4.1.4 section a.Addition of"Pt" provides clarification of testing type consistent with 10CFR50, Appendix J.All terms in 4.4.1.4, section a now fully defined.No technical change.7.8.Added to the definition of"Lt" in Technical Specification 4.4.1.4 section b.Added definition of"Pa" and"Lam" in Technical Specification 4.4.1.4 section c.Added steam generator inspection/maintenance penetration to Technical Specification 4.4.1.5 section a (ii).Added definition"Lt" provides clarification consistent with 10CFR50, Appendix J.All terms in 4.4.1.4, section b now fully defined.No technical change.Addition of"Pa" and"La" provides clarification consistent with 10 CFR 50, Appendix J.All terms in 4.4.1.4, section c now fully defined.No technical change.Addition of this penetration provides testing criteria similar to the equipment hatch and containment air locks.9.Revised first line of Technical Specification 4.4.1.5, section a (ii).Minor clarification only.No technical change. | |||
Removed notes associated with Technical Specification 4.4.2.4 section a.Deleted reference to section d.Mini-purge valves have been installed so the Technical Specification can be considered effective. | |||
Section d will be removed from Technical Specifications. | |||
No technical change.11.Added steam generator inspection/maintenance penetration to Technical Specification 4.4.2.4 section b.Addition of this penetration provides testing criteria similar to the equipment hatch and containment air locks.12.Removed Technical Specification 4.4.2.4 section d and associated note.Blind flanges have been installed so the Technical Specification can be considered effective. | |||
17.(1)Modified"old" | No technical change.1 3.Changed Reference from Table 3.6-1 to UFSAR 6.2-13 in section 4.4.5.1.14.Changed Reference from Table 3.6-1 to UFSAR 6.2-13 in section 4.4.6.2.Valve listing remains in a licensee controlled document under 10CFR50.59 program.Valve listing remains in a licensee controlled document under 10CFR50.59 program. | ||
32. | |||
25. | |||
~~~~definitions | |||
~~0}} | ~~0}} | ||
Revision as of 14:22, 7 July 2018
| 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: Nu lear Engineer K)-z.-'9Q Date Reviewed by: Nucle r Engine r Date Approved by: anag r, Nuclear S fety&Licensing Date Page i 90i0240i'i9 90iOi5 PDR ADOCK 05000244 P PDC I Revision Status Sheet Page Latest Revision Latest Page'evision Page Latest Revision 7 8 9 ,10 14h 15 16 17 18 19 20 21 22 23 24 25 0 37 38 39 40 41 42 43 44 45 46 47 48 12 13 14 14a 14b 14c 14d 14e 14f 14g 27 28 29 30 31 32 33 34 35 36 0 Safety Analysis NSL-0000-SA024 Page ii Revision 1 Date 10 3 90 Safet Anal sis 1.0 2.0 f Descri tion and Sco e The purpose of this evaluation is to determine if there are any unreviewed safety questions related to updating 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.References 2.1 2.1.1 2.1.2 Updated Final Safety Analysis Report, Revision 5.Section 6.2.4, Containment Isolation System.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~~2.2.2 2.2.3 2.3 2.4 Section 3.6.3, Containment Isolation Valves.Table 3.6-1, Containment Isolation Valves.Section 3.8.1, Refueling.
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.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 2.6 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.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 NSL-0000-SA024 Page 1 Revision 0 2.8 2.9 2.10 2.11 2.12 2.13 2.14 2.15 2.16 2.17 2.18 2.19 2.19.1 2.20 Letter from J.E.Maier, RG&E, to D.M.Crutchfield, NRC,
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,
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,
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,
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,
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,
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,
Subject:
Modification of Containment Penetration
$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 Page 2 Revision 0 Date 9 24 90 I 4 II 3.0 Safet Anal sis 3~1 3.2 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.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.(2)(3)(4)The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy.
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 only been changed, 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:
(2)(3)clarifications or corrections of typographical errors and omissions,.
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 Page 3 Revision 0
~~s~3.3.1 3.3.1.1 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.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 3.3.2.1 The updates to the UFSAR table to better represent actual plant conditions are described below.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.Safety Analysis NSL-0000-SA024 Page 4 Revision 0 Date 9 24 90
~~~~3.3.2.2 3.3.2.3 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 (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 it was open since this was the most conservative position.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 NSL-0000-SA024 Page 5 Revision 0 Date 9 24 90
~~~~'3.3.2.4 3.3.2.5 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.Also, during Refueling Operations, Technical 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 negatively'mpact the penetration or the containment 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).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 NSL-0000-SA024 Page 6 Revision 0
~~(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.Safety Analysis NSL-0000-SA024 Page 7 Revision 0 Date 9 24 90
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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.3.3.2.8 (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.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 3.3.3.1 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.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 Page 8 Revision 0
~I~~3.3.3.2 3.3.3.3 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).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: Safety Analysis NSL-0000-SA024 Page 9 Revision 0
~~3.4.1 3.4.2 3.4.3,~~3.4.4 (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 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.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.
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.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.Safety Analysis NSL-0000-SA024 Page 10 Revision 0 Date 9 24 90 P
4~~k~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 4.2 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.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 Page 11 Revision 0 Date 9 24 90
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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.Safety Analysis NSL-0000-SA024 Page 12 Revision 9 24 90 k
~~4.7 4.8 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.Based on the above analysis, it has been determined that: (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.Safety Analysis NSL-0000-SA024 Page 13 Revision 0 Date 9 24 90 l~/
Attachment A Safety Analysis NSL-0000-SA024 Page 14 Revision 0 Date 9 24 90 CONTAI AND I 2-13 PENETRATIONS PIPINC~Sstea Penetration No.Valve No.Valve Position Valve Indi cation Position Operator In Control Relative to Normal Position At Cold Ixaedf ate Shutdovn Postaccfdent~
Maxi sans Isolation UFSAR Notes Steam Cenerator Inspection/
Maintenance Blind Flanges Both 0/C C (add)5 I~2 Fuel Transfer Tube Charging Line to B Loop Safety Infection Pury IB Discharge Alternate Charging to A Cold Leg 29 100 101 102 370B 870B 889B 3838 Blind Flange Check Check Check Check Inside Inside Outside Outside Inside 0/C 0 0 C 6'-13 5 6.2-18 3B 6'-15 3B 6'-15 3B 6.2-16 3B 2I 3 Construction Ffre Service Water 103 NA Blind Flange NA NA Inside C C NA 6'-17 5 Containment Spray Pusy IA Reactor Coolant Puxy h Seal Water Inlet 105 106 8 62A 306k Check Check NA Outside C Nh Inside 0 0 NA 6'-18 3B 6'-19 3B Susy h Dfs charge to Waste Holdup Tank Reactor Coolant Pump Seal Water Return Lfne and Excess Letdovn to VCT 107 108 1723 1728 313 Diaphraga Dfaphraga Afr hir Motor Status Status Both Outside Outside Outside 0 0 0/C 0/C 0/C C C FC Yes FC Yes AI Yes 60 6.2 20 2 60 6'"20 2 60 F 2-21 8, 6 Containment Spray Pury IB 109 862B Check Nh NA Outside C Nh 6.2 22 3B end AI Falls As Is AOV Air Operated Valve C~Closed CIS~Contafnment Isolation Signal CV Check Valve FC~Falls Closed FO Fails Open LC~Locked Closed MQV MV 0 0/C R/C Status SOV Moto~rated Valve~Manual Valve~Open Open or Closed~Red/Creen Light on Main Control Board White Status Light, Solenoid Operated Valve Refers to position fsuediately follovfng receipt of containment isolation signal and containment ventilation fsolation signal.s The maxfxaa isolation time does not include diesel start time nor instrument delay tfme.'efers to classes defined in 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 Page 14a Revision 1
-13 CONTAI PENETRATIONS AND I PIPING~Satan Reactor Coolant Purp B Seal Nater Inlet Penetratfon No.110a (topi Valve No.304B Valve Check Position Valve Indication Position Operator In Control Relative to Homal Roon Contafnnent OHeratfon NA Nh InsMe 0 Position At Cold lxxaadf ate Paver Trip on Shutdovn Postaccfdentv Failure CIS 0~C NA Nh Maxi xixa Isolation Tfxe DFSAR Notes 6.2-23 3B Safety Inlectfon Test Lfne 110b<bottoni 879 Globe Manual No Outside LC LC NA 6~2-15 1 Residual Hea't Renoval to B Cold Leg 720 959 Gate Globe Motor Alr R/C Status Inside Outs fde 0 0/C AI FC 6.2-24 6.2-24 3B 3B 4~7g 8 I 4, 1 Letdown to Nonregenerative Heat Exchanger Safety In)ection Puxp IA Discharge Standby Auxf I-fary Feedwater Line to Stean Generator lh 112 113 119 200A 200B 202 371 421 810A 889A 9104A 9105A Globe Globo Clobe Globe Globe Check Check Stop-Check Check Afr Alr Air Air Alr Motor NA R/G R/G R/G Both R/C NA NA R/G Nh Inside Inside Inside Outside Inside Outside Outside OutsMe Inside 0/C 0/C C 0 0 C C C C C 0 0/C C C C C C AI NA Yes Tes Yes Yes Yes No Nh 60$0 60$0 3B 3B 6.2-15 6.2 15 6.2 26 6.2-26 6~225 I$e2 25 I 6~225 1 6.2-25 I$.2-25 I 10 10 10 Nitrogen to hccuxaIlators Pressurlxer Relief Tank to Gas Analyxer Nitrogen to Pressurixer Relief Tank Makeup Rater to Pressurixer Relief Tank Conte funest Pressure Transnftt@r PT945 120a 120b 121a 121b 121c 846 4623 539 546 528 547 504 529 PT945 1819A Globe Check Globe Globe Check Globe Dfaphragn Check NA Globe Air NA Air Manual NA lanual Air NA NA Manual Both NA Sta'xus No NA No Both NA Outside Inside Outside Outside Inside Outside Outside Inside Outside Outs Me C 0/C C 0/C 0/C'/C , 0/C 0 0/C OIC OIC OIC C C C 0 C C FC Yes NA FC Yes Nh Nh FC Yes NA Nh 60 Nh 60 NA 6~2 21 3A$.2-27 3A 6~2-28 2 F 2-24 2 6.2-29 3A$.2 29 3A 6~2-30 3A$.2-30 3A 6 2-31 2 6.2 31 2 12 13 Contafnnent Pressure TransxLit'tox'T946 121d F2946 Nh NA NA Outside Nh NA 1819B Globe Manual No Outside 0 0 6.2-31 2 6 2-31 2 13 Standby Auxfl-fary I'eedvater Line to Stean Generator IB 123 ltopl 9104 B 91058 Stop-Check Check Motor Nh Outside Inside C C C C AI Nh NA 6.2-26 Nh 6.2-26 4 Safety Analysis NSL-,OOOO-SA024 Page 14b Revision 1 Date 10 3 90
)
CONTAI AND~2-13~PENETRATION~a PIPIhG~Sat cmc Penetration Valve No.Valve Position Valve Indication Position Operator In Control Relative to Homal~T Rocvm, Contafnacent OEeratfon Posftfon At Cold Iacaediate Pover Trip on Shutdovn postaccfdcntr Failure CI8 Max f aaxa Isolation Ti lac UFSAR~Fi re Notes Reactor Coolant Drain Tank to Gas Analyzer Line Excess Letdovn Beat Exchanger Cooling Water Supply 4 Return Postaccfdcnt Afr Sag>le to C Fan Component Cooling Water fraa Reactor Coolant Pump 1B 123 (button)124a 124b 125 1600A 1655 1789 743 745 1569 1571 1572 1574 7598 Globe Globe Diaphragca Check Globe Dfaphragca Dfsphragca Dfaphragrc Dfaphragal Cate Solenoid Manual hfr Q hi r Manual Manual Manual Manual Hotor No No Status Q RIG R/C Outsfde Outside Outside Inside Outside Outs fde OutsMe Outside Outsfde Outside 0 0 0 0 0 0/C 0 0/C C C LC IC, LC LC r C r C 0 C C C 0 AI Ycls NA Yes NA No No NA 60 6.2-32 6.2-32 6'-32 6.2-33.6.2-33 6'-34 5 6.2 34 5 6.2-34 5 6.2-34 5 6.2-35 4 14 Ccxcponent Cooling Water frees Reactor Coolant Pump IA 126 759A Gate Motor R/C Outside 0 AI No Nh 6.2<<36 Componen't Cooling Nater to Reactor Coolant Pump lh 127 749A 750A Cate Check Hotor NA Outside Inside 0 0 C C 0 0 AI NA Q 6.2-37 4 Q 6.2-37 Cccmponeat Cooling Water to Reactor Coolant~1B Reactor Coolant Drain Tank and Pressurizer Relist Tank to Containnent Vent Reader 128 129 7498 7508 1713 1786 1787 1793 Cate Check Check Dfaphragal Dfaphragca Dfaphragal Motor NA NA hir Air Manual NA Sta'tus S'ta'tua No OutsMe Inside Outside Outsfde Outside Outside 0 0 C 0 0 LC C C 0/C C C 0/C 0 0 C C C LC AI NA No NA Q 6'-38 Q 6'-38 4 NA NA NA 6.2-39 3A FC Yes 60 6'-39 3A FC Yes 60 6.2-39 3A Nh NA NA 6~2-3S 3A 12 Component Cooling Water f rcxa Reactor Support Cooling 130-814 Gate Motor Both Outside 0 AI Yes 60 6.2-40 4 Cc~nent Cooling Nater to Ream'tor Support Cooling Containment Nfnf-Purge Exhaust 131 813 Cate Hotor Both Outside 0 0 132 7970 Butterfly hir Both Inside 0/C OIC 7971 Buttertly Alr Both OutsMe C 0/C C C AI Yes FC Yes FC Yes 60 6.2-40 4 3 6.2-41 5 3 6.2-41 5',Safety Anal'ysis r NSL-0000-SA024 Page 14c Revision 1
~,
2 13 CONTAI PENETRATION<
AND I~PIPING~zs ten Residual Beat Removal Pump Suctfon from A Hot, Leg Penetration No.140 Valve No.701 Valve Valve Operator Gate Hotor Position Indication Posftfon In Control Relative to Room Containment R/C Inside Position At Normal Cold Imnediate Fever OHeratfon Shutdovn Postaccidcnt'ailure 0 C AI Trip on CIS Kaxfmsus I moist f on Time OFSAR Notes~Ff re Classs See end of table~7i 8 6.2-42 1 Residual Heat Removal No.1 Pump Suction from Sump B 141 85th 1813A Cate Cate Hotor Hotor R/0 Outside C C R/C Outside C 0/C 0 C AI No Nh 6.2-42 5 AI No NA 6.2-42 5 15 8 Residual Heat Removal No.2 Pump Suction from Su~B 142 SSOB Gate Hotor R/C Outside C C 1813B Gate Hotor R/0 Outside C 0/C AI AI NA 6~2-42 5 NA 6.2-42 5 15 8 Reactor Coolant Drain Tant Discharge Lfne Reactor Compartment Cooling Onits h and B 143 201 (top)201 (bottom)1003A 1003B 1721 4757 4636 DI a phragn Diaphragm Diaphragm Butterfly Butterfly Air Afr Alr Hanual Hanual Status Status Status No No Outside Outside Outside Outside Outside 0 0 0 0 0 0/C 0/C 0 C C C 0 0 Yes Yes Yes 60 60 60'.2-43 2 6~2-43 2 6.2-42 2 6.2-44 4 6.2-45 4 16 17 B Hydrogen Recombiner (Pilot and Hafn)Containment Pressure Transmitter PT947 and PT948 PostaccMent Air 8~le to B Fan Purge Supply Duct Hot Leg Loop Sample Pressurizer Liquid Space~le A Stean Cenerator Sample 202 2Q3a 203b 204 205 206a (top)206b (bottom)1076B 1084B 1021181 1021351 F2947 PT948 1819C 1819D 1563 1565 1566 1568 5869 955 956D 966C 953 956E 966B 5733 5735 Diaphragm Diaphragm Globe Clobe NA NA Clobe Globe Diaphragm Diaphragm Diaphragm Diaphragm Blind Flange Butterfly Clobe Globe Globe Globe Clobe Globe Globe Globe Hanuaf Nanuel Solenoid Solenoid NA Nh Hanua 1 , Hanual Hanual Hanual Hanuel Hanual Afr Air Hanual Air Alr Manual Alr Hanual Alr No No Status Status NA Nh No No No No No No NA Both St&'tus No Status Status No S'ta'tus No Status Outside Outside Outside Outside Outside Outside Outs Me Outs I de Outside Outside OutsMe Outside Inside Outside Inside Outside Outside Inside Outside Outside Outside Outsfde LC LC C C NA NA 0 0 C C C 0 C C 0 C LC LC C C NA Nh 0 0 0 0/C C 0 C C 0 C LC LC C C NA NA 0 0 C 0 C C 0 C 0 C Nh FC Nh FC Nh NA Yes Yes Yes NA Yes Yes Nh Yes NA NA 3 3 NA NA 60 NA NA 60 NA 60 6.2-46 F 2-46 6.2-46 6.2-46 6.2-47 6.2 47 6,2 47 6~2 47 6.2 48 6.2-48 6.2 48 6.2 48 6.2 49 6.2 49 6'50 6~2 50 6.2-50 6.2 51 6.2-51 6~2 Sl 6~2 52 6.2 52 2 2 2 2 18 18 13 13 2, 19 19 Pressurizer Steam Space Sample 207a (top)951 956F 966A Globe Globe Globe Alr Hanuel Air Status No Status Inside Outside Outside C 0 C C 0 C C 0 C FC Yes Nh 6.2 S3 1 NA NA NA 6.2-53 I FC Yes 60 6~253 1 ss 3'Safety Analysis'SL-0000-SA024 Page 14d Revise.on 1 l
2-13 CONTAIN PENETRA TIGHT AND I N PIPING Penetration Mo.Valve No.Valve Valve Operator Position Indication Position In Control Relative to Normal Roon Containment OBeratfon Posftfon At Cold irumdfate Power Shutdovn Postaccfdent'aflur*
Trip on CIS Maxi sum Isolation Time UFSAR~F(re Cla ass Notes See end of table a B Steam Generator Sample Reactor Cocpartment Cooling Units h and B Oxygen Makeup to h 4 B Reconbiners Purge Exhaust Duct Auxiliary Steam Supply to Containment Auxiliary Steam Condensate Return A Hydrogen Recoebiner (Pilot and Nein)207b (bottom)209 (top)209 (bottom)210 300 301 303 304 5734 5736 4635 4758 1080A 102145 1021481 102158 1021531 Nh 5479 6151 6165 6152 6175 1076A 108(A 1020551 1020951 Globe Globe Butterfly Butterfly Globe Clobe Globe Globe Globe Blind Flange Butterfly Globe Globe Globe Globe Diaphragm Diaphragm Globe Globe Manual Air Manual Manual Manual Solenoid Solenoid Solenoid Solenoid NA Air Manual Manual Manual Manual Hanual Manual Solenoid Solenoid No Status No No No S'tatus Sta'kus Status S'tatus NA Both No No No No Status S'ta'tus Outside Outside Outside Outside Outside Outside Outs fde Outside Outside Insfde Outs ide Outs ide Outside Outside Ou'teide Outside Outside Outside Outside LC C C C C LC LC C C C C LC C C C C 0 OIC LC LC C C LC C~C C C LC LC C C NA NA Nh Tes Tes Tes Yes NA Yes Nh Nh Tes Yes Nh 60 3 3 3 3 6.2-54 6.2-54 6.2-44 6.2-45 6.2-55 6.2-55 6.2 55 6.2-55 6'-55 6'-56 F 2-56 6.2-57 6.2-57 6.2-57 6.2-57 6.2-58 6.2-58 6.2-54 6.2-58 16 17 14 14 14 14 2, 19 19 18 18 Contafnment Alr Saxple Out Containment Air Sarpf e Inlet Containment Alr Sa=ple Postaccident Fire Service Mater Service Mater to h Fan Cooler Nini-Purge Supply Service Air to Containment 305a (bottom)305b (top}305C 307 308 309 310a (bottcm)1596 1597 1598 1599 1554 1556 1557 1559 1560 1562 9227 9229 4629 7445 7474 7141 7226 Globe Diaphragm Diaphragm Diaphragm Diaphragm Die ph rage Diaphragm Diaphragm Diaphragm Diaphragm Cate Check Butterfly Butterfly Butterfly Cata Check Manual Air Air Alr Manual Manual Manual Hanual Manual Manual Afr NA Manual hir Alr Manual Nh No Both Both Both No No No No No No Both Nh Both Both No Nh Outside Outside Outsfde Outside Outside Outside Outside Outside Outside Outside Outside Insfde Outside Outsfde Inside Outside Inside OIC OIC 0/C 0/C OIC NA Tes Tes Tes Tes Nh Yes Tes 60 60 60 Nh 6~2 61 6.2 61 6.2 61 6.2-61 6.2 61 6.2 61 6.2 62$.2-62 6.2 63 6,2 64 6.2 64 6~2-65 6.2 65 6.2 59 6~2 59 6.2 60 6'60 2 2 3A 3h 3A 3A Safety Analysis E-NSL-0000-SA024 Page 14e Revision Date 10 3 90 CONTAINNEN AND I-13 PENETRATIONS ON PIPING~Sat em Instrument Air to Contafnmnnt Service Mater from B Fan Cooler Penetration No.310b (top)311 Valve Mo, 5392 5393 4630 Valve Globe Check Butterfly Valve Operator Manual Both NA Outside Inside Outside 0 0 Position Indicatfon Position In Cont rol Relative to Normal Room Contain>nant OEeratfon 0/C C C Posftfon ht Cold irradiate Shutdovn Postaccfdent'over Failure Trip on CI8 Yes NA Hex f sum Isolation Time 60 IR VFSAR~Ff re 6.2 66 6.2-66 6.2-63 3A 3A Notes 16 Service Mater to D Fan Cooler Leakage Test Depressurira-t ion 312 313 4642 NA 7444 Butterfly Blind Flange Butterfly Hanual Nh Hotor NA Sta'tus Outside Inside Outsfde 0/C.C C NA Al NA Yes NA 6.2-63~Q 6.2-67 5 Q 6~2 67 5 17 19 Service Mater From C I'an Cooler 315 4643 Butterfly Hanuel Outside 0/C>NA NA NA 6.2-63 4 16 Service Mater to B Fan Cooler Leakage Test Supply Deadveight Tes'ter Service Mater from A Fan Cooler 316 317 31d 319 4628 NA 7443 NA 4627 Butterfly Blind Flange Butterfly Butterfly Hanual NA Hotor Hanual No NA Sta'cus No Outside Inside Outside Outside 0/C 0/C NA AI Q Yes NA 6.2-63 4 6.2 68 5 6.2"68 5 lR NA 6~2-63 4 17 19 20 16 Service Mater to C Fan Cooler A Steam Generator Blovdovn 320 321 46li 5701 5738 Butter fly Globe Globe Manual Hanua1 Air No No Status Outside Outside Outside 0 0 0/C.'0/C 0 C NA 6.2-63 NA Q Q 6.2-6S FC Yes 60 6~2 69 17 B Steam Generator Blovdovn Servfca Mater fran D I'an Cooler Demineralized Mater to Contafment 322 323 324 5702 5737 4644 4 l 1 d 8l 1 9 Globe Globe Butterfly Globe Check Manual hir Hanual Air NA No Status No Both NA Outside Outside Outside Outside Inside C C 0 0/C 0/C 0/C 0/C C C NA Yes Yes NA Q 6.2-70 60 6270 Q 6.2-63 60 6.2-71 5 lVL 6~2-71 5 16 Containment Pressure Transmitters PT944, F2949>and PT950 332a PT944 PTS49 PT950 1819E 1419F 18190 NA NA Q Globe Globe Globe NA NA Nh Hanual Manual Manual NA NA NA No No No Outside Outside Outside Outside Outside Outside IVL IR NA 0 0 0 Nh NA NA 0 0 0 Q NA NA 0 0 0 6.2-72 6.2-72 6.2-72 6.2-72 6'-72 6.2-72 NA NA NA 2 Nh Nh IVL 2 N1L NA IR 2 NA.NA NA 2 NA NA NA 2 NA Nh Nh 2 13 13 13 Safety Analysis.NSL-0000-SA024 Page 14f Revision 1 Date 10 3 90 CONTAI AND IS 2 13'C PENETRATIONS ION PIPING~Sstem Penetration No.Valve No.Valve Position Valve Indication Position Operator In Control Relatfve to Room Contafnvent Position At Normal Cold Ismedfate OBeratfon Shutdovn Postaccfdent'oser Failure Trip on CIS Maxi sans Isolation Time CFSAR~Ff re Classv Notes See<<nd ot table s Hydrocen Monitor Instrumentatfon Lines Main Steam from A Steam Generator Main Steam Iron B Steam Generator 332c 401 402 921 922 923 924 3505A 3507 3517 3519 3521 3504A 3506 3516 3518 3520 Cate Cate Cate Cate Cate Cate Swine Check Check Cate Cate Cate Suing Check Check Cate Solenoid Solenoid Solenoid Solenoid Motor Manual Air NA Manual Motor Manual Air NA Manual Both Both Both Both R/0 No R/C NA No R/0 No R/0 NA No Outside Outside Outside 0 teide Outside Outsfde Outside Outside Outside Outside Outside Outside Outside Outsfde C C C C C 0 0 0 0 C C C C C C C C 0 C C C C 0 C C C C 0 0 C C 0 0 0 C C 0 AI NA AI NA NA AI NA AI NA NA yes yes yss Tes No NA No NA NA No NA No NA NA 6.2 74 6.2 74 6.2 74 6.2 74 6.2 75 6.2 75 6.2 75 6'75 6.2 75 6.2 75 6.2 75 6.2 75 6'75 6.2"75 21 21 21 21 11 11 ll ll ll ll ll 11 ll ll Fcedvater Line 403 to A Steam Generator 3993 3995 4008C 4083 4885 4011 Check Clohe Check Check Globe Globe NA Manual NA NA Manual Manual NA No NA NA No No Outside Outside Outside Outside Outside Outside 0 0 C C 0 0 C 0 C C 0 0 C 0 0 0 0 0 NA NA NA NA NA NA NA NA NA NA NA NA 6.2 76 6.2-76 6.2 76 6.2-76 6.2-76 6.2-76 11 11 11 11 11 11 1'eedvater line to B Steam Generator Personnel Hatch Equfpcent Hatch 404 1080 2000 3992 3994 40000 4084 4806 4012 Check Clohe Check Check Globe Clohe NA Manual NA NA Manual Manual NA No NA NA No No Outside Outside Outside Outside Outside Outside Both 0 0 C C 0 0 C 0 C C 0 0 0/C 0/C C 0 0 0 0 0 NA NA NA NA NA'NA NA 6.2-76 6.2-76 6.2-76 6.2-76 6.2-76 6.2-76 3.8-31 3.8-30 11 11 ll 11 11 11 Safety Analysis NSL-0000-SA024 Page 14c4 Revision 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 IOCFR50, Appendix J lea'kage testing, nor does ft require a maximum isolation tfme.(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.(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).I k (13)(14)(15)(16)(18)The pressure transmitter assexbly, by its design, provides a containment pressure boundary.The fntegrity of this boundary is verified by annual leakage tests.Operations fs instructed to manually close AOV 745 following a Containment Isolation Signal until an automatic signal 1s installed through the necessary modfficatfon.
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.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.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 NSL-0000-SA024 Page 14h Revision 1 t t'I y 0 Attachment B Safety Analysis NSL-0000-SA024 Page 15 Revision 0 Date 09 24 90 The blanks or"-" within columns were replaced with"NA".Typographical clarification only.No technical change.2.(1)The blanks or"-" for the Position At columns were replaced with the representative position;(2)The"No" listed under Position Indication in Control Room was replaced with"NA".(1)(2)The valve position and"NA" are more representative of the penetration configuration.
In addition, consistency is maintained within the table.No technical change.3.The"AI" or blank for the Power Failure column for manual valves was replaced with"NA".The"NA" is more representative of the penetration configuration since a manual valve does not receive any motive power.No technical change..4.was replaced with"NA".The"NA" is more representative of the penetration configuration.
In addition, consistency is maintained within the table.No technical change.5.The blank or"No" for Maximum Isolation Time was replaced with"NA".The"NA" is more representative of the penetration configuration.
In addition, consistency is maintained within the table.No technical change.Safety Analysis NSL-0000-SA024 Page 16 Revision 0 Date 09 24 90
~~J~
Added"Cold" to Position At Shutdown column heading.Minor clarification for consistency with Technical Specifications.
No technical change.2.(1)Added"Immediate" to Position At Postaccident column heading;(2)Added Note"a" (1)(2)Clarification of column since valve position can be potentially changed during post accident recovery operations.
Column now provides clear definition of penetration configuration following receipt of a CIS.3.table;(2)Deleted definitions for"W" and"G" from table Legend.(1)(2)Column did not provide any information relevant to table.Fluid type can be inferred from~S stem column.4 associated Note"c" from table.Column did not provide any information relevant to table.5.Added definitions for"AOV","CV","MOV","MV", and"SOV" to table Legend.Correction of typographical omission.No technical change.6.(1)Modified Position Indication in Control Room column to reflect type of indication instead of"Yes" and"No";(2)Added definition for"R/G" and"Status" to table Legend."Both" indicates that a red/green light and status light exists.(1)(2)The type of control room indication is more representative of the system configuration.
This is a clarification only.No technical change.7.Moved Table Heading Notes"a","b","c", and"d" to first page of table.Minor format change only.No technical change.Safety Analysis NSL-0000-SA024 Page 17 Revision 0
~c 8.(1)Renamed Note"a" to"b";(2)Added"nor instrument delay time" to end of note.(1)(2)Minor clarification-only.Note is now consistent with Standard Review Plan Section 6.2.4.No technical change.9.Renamed Note"b" to"c".No technical change.10.Deleted"Line" from~S stem column heading.No technical change.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 NSL-0000-SA024 Page 18 Revision 0 Date 09 24 90
~l I~
Penetration 2-Added penetration and necessary information to the table.This spare penetration was modified to 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)Added Note 2.(1)(2)No technical change.3.Penetration 100-(1)Global Notes 1, 2, and 4;(2)Added Note 4;(3)Changed Position At Immediate Postaccident from"0/C" to"C".(1)(2)No technical change.(3)Update for better representation of system configuration since the Charging System is isolated upon receipt of a SI signal.4~Penetration 101-(1)Global Notes 1, 2, 4, and 5;(2)Added Note 4;(3)Added"3B" under Class for valve 889B;(4)Reordered penetration valves.(1)(2)No technical change.(3)Correction of typographical omission.No technical change.(4)Valves now in numeric order.No technical change.5.Penetration 102-(1)Global Notes 1, 2, 4, and 5;(2)Added Note 4.(1)(2)No technical change.6.Penetration 103-Deleted valve 5129 (entire line in table)and replaced with Blind Flange.Replaced Note of"No longer in use" to reflect accurate configuration status of Blind Flange.The use of the Blind Flange is consistent with the previously listed locked-closed manual valve.Safety Analysis NSL-0000-SA024 Page 19 Revision 0
~c>~
7.Penetration 105-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.8.9.10.Penetration 106-(1)Global Notes 1, 2, and 4;(2)Added Note 4;(3)Changed"supply" to"Inlet" under~S stem.Penetration 107-(1)Changed Position Indication In Control Room from"Yes" to"Status" for both valves;(2)Changed Position At Cold Shutdown from"0" to"0/C" for both valves.Penetration 108-(1)Added"and Excess Letdown to VCT" under~Sstem;(2)Changed Position Indication In Control Room from"Yes" to"Both";(3)Changed'osition At Cold Shutdown from"0" to"0/C";(4)Added Note 4;(5)Added Note 6.(1)(2)No technical change.(3)Minor clarification only.No technical change.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration.
(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration since this line may or may not be used during cold shutdown conditions.
(4)(5)No technical change.Penetration 109-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.12.Penetration 110a-(1)Global Notes 1, 2, and 4;(2)Added Note 4.(1)(2)No technical change.Safety Analysis NSL-0000-SA024 Page 20 Revision 0 Date 09 24 90
~4~
13.Penetration 110b-(1)Global Notes 3 and 4;(2)Added Note 4;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to nLCss (1)(2)No technical change.(3)Consistency with Ginna Administrative Control.14.Penetration 111-(1)Added Note 7 to both valves;(2)Added Note 8 to valve 720;(3)Added Note 4 to both valves;(4)Changed Position Indication In Control Room from"Yes" to"R/G" for MOV 720;(5)Added valve 959 and necessary information.
(1)Consistency with Technical Specifications.
(2)(3)No technical change.(4)Minor clarification only.No technical change.(5)Valve receives containment isolation signal and was previously missing from the table.15.Penetration 112-(1)Deleted valves 204A and 821 (entire line in table)and replaced with valves 200A, 200B, and 202;(2)Added valve 427 and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"Both" for valve 371;(4)Changed Position At Immediate Postaccident from"0" to"C" for valve 371.(1)(2)Present configuration status;the three new valves enable explicit compliance with GDC 55 vs.the use of redundant outboard isolation valves.The 200A, 200B, 202, and 427 valves have been successfully tested.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration since letdown is isolated upon receipt of a SI signal.Penetration 113-(1)Global Notes 1, 2, and 4;(2)Added Note 4 to both valves;(3)Reordered penetration valves.(1)(2)No technical change.(3)Valves now in numeric order.No technical change.1 Safety Analysis NSL-0000-SA024 Page 21 Revision 0 Date 09 24 90 17.Penetration 119-(1)Global Notes 1, 2, 4, and 5;(2)Changed Position Indication In Control Room from"No"-to"R/G" for valve 9704A;(3)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical change.(3)Valves now in numeric order.No technical change.18.Penetration 120a-(1)Global Notes 1, 2, and 4 for valve 8623;(2)Changed valve 846 from"Gate" to"Globe";(3)Changed Position Indication In Control Room from"Yes" to"Both" for valve 846;(4)Changed Position At Normal 0 eration from"0/C" to"C" for valve 846;(5)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration.
This valve remains closed unless the accumulator nitrogen blanket pressure decreases.
(5)Valves now in numeric order.No technical change.19.Penetration 120b-(1)Changed Position Indication In Control Room from"Yes" to"Status" for valve 539;(2)Changed Position At Normal 0 eration from"0/C" to"C" for valve 539;(3)Global Notes 3&4 for valve 546.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration.
(3)No technical change.20.Penetration 121a-(1)Global Notes 1, 2, and 4 for valve 528;(2)Changed valve 547 from"Diaphragm" to"Globe";(3)Changed Position At Immediate Postaccident from"0" to"LC" for valve 547;(4)Changed Position At Normal (5)Global Notes 3 and 4 for valve 547;(6)Deleted reference to"old" Note 9;(7)Added Note 12 to valve 547.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Consistency with Ginna Administrative Control.(4)Update for better representation of system configuration.
No technical change.(5)No technical change.(6)Correction of typographical error.No technical change.(7)No technical change.Safety Analysis NSL-0000-SA024 Page 22 Revision 0 21.Penetration 121b-(1)Changed Position Indication In Control Room from"Yes" to"Both" for valve 508;(2)Changed Position At Normal 0 eration from"0/C" to"C" for valve 508;(3)Changed Position At Normal 0 eration from"C" to"0/C" for valve 529;(4)Global Notes 1, 2, and 4 for valve 529;(5)Reordered penetration valves.(1)Minor clarification only.No technical change.(2)(3)Update for better representation of system configuration.
(4)No technical change.(5)Valves now in numeric order.No technical change.22.Penetration 121c-(1)Global Note 1 for PT945;(2)Global Notes 3 and 4 for valve 1819A;(3)Added"Gate" under 8 9 (1)(2)No technical change.(3)Correction of typographical omission.No technical change.23.Penetration 121d-(1)Global Note 1 for PT946;(2)Global Notes 3 and 4 for valve 1819B.(1)(2)No technical change.24.Penetration 123 (bottom)-(1)Added"to" before"Gas Analyzer Line" under~sstem;(2)Global Notes 3 and 4 for 1655;(3)Changed valve 1789 from"Globe" to"Diaphragm";
(4)Changed Position Indication In Control Room from"Yes" to"Status" for valve 1789;(5)Changed Position At Normal 0 eration from"0/C" to"0" for valve 1789;(6)Added valve 1600A;(7)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)No technical change.(3)Correction of typographical error.No technical change.(4)Minor clarification only.No technical change.(5)Update for better representation of system configuration since this line remains open.(6)Valve receives containment isolation signal and was previously missing from the table.(7)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 23 Revision 0 Date 09 24 90 25.Penetration 123 (top)-(1)Global Notes 1, 2, 4, and 5;(2)Changed Position Indication In Control Room from"No" to"R/G" for valve 9704B.(1)No technical change.(2)Minor clarification only.No technical change.26.Penetration 124a-(1)Global Notes 1, 2, and 4 for valve 743;(2)Changed Position At Immediate Postaccident from"0" to"C" for valve 743;(3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 745;(4)for valve 745;(5)Changed Maximum Isolation Time from"60" to"NA" for valve 745;(6)Changed Position At Cold Shutdown from"0" to"C" for valve 745.(1)No technical change.(2)Update for better representation of system configuration.
Operations is instructed to manually isolate this line following receipt of a containment isolation signal.(3)Minor clarification only.No technical change.(4)(5)Correction of typographical error.See letter from R.Mecredy, RG&E, to A.Johnson, NRC, dated July 9, 1990.(6)Update for'etter representation of system configuration since excess letdown is not operational during cold shutdown conditions.
27.Penetration 124b-(1)Added"to" before"C Fan" under~astern;(2)Added four valves;(3)Changed Position At Cold Shutdown from"C" to"LC" for all four valves;(4)Changed Position At Immediate Postaccident from"0/C" to"LC" for all four valves;(5)Global Notes 3 and 4.(1)Minor clarification.
No technical change.(2)Correction of typographical omission.No technical change.(3)(4)Consistency with Ginna Administrative Control.(5)No technical change.Safety Analysis NSL-0000-SA024 Page 24 Revision 0 Date 09 24 90 28.Penetration 125-(1)Changed Position Indication In Control Room from"Yes" to"R/G";(2)Changed Position At Cold Shutdown from"0" to"C";(3)Added Note 4.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions.
(3)No technical change.29.Penetration 126-(1)Changed Position Indication In Control Room from"Yes" to"R/G";(2)Changed Position At Cold Shutdown from"0" to"C";(3)Added Note 4.(1)Minor clarification only.No technical change;(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions.
(3)No technical change.30.Penetration 127-(1)Changed Position Indication In Control Room from"Yes" to"R/B" for valve 749A;(2)Changed Position At Cold Shutdown from"0" to"C" for valve 749A;(3)Global Notes 1, 2, and 4 for valve 750A;(4)Changed Maximum Isolation Time from"60" to"NA" for valve 749A.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions..
(3)No technical change.(4)Correction of typographical error.No technical change.31.Penetration 128-(1)Changed Position Indication In Control Room from"Yes" to"R/B" for valve 749B;(2)Changed Position At Cold Shutdown from"0" to"C" for valve 749B;(3)Global Notes 1, 2, and 4 for valve 750B;(4)Changed Maximum Isolation Time from"60" to"NA" for valve 749B.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration since RCPs are not operating during cold shutdown conditions.
(3)No technical change.(4)Correction of typographical error.No technical change.Safety Analysis NSL-0000-SA024 Page 25 Revision.0 32.Penetration 129-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 1787;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valves 1786 and 1787;(3)Changed Position at Cold Shutdown from"0" to"C" for valves 1786 and 1787.(4)Global Notes 1, 2, and 4 for valve 1713;(5)Global Notes 2, 3, and 4 for valve 1793;(6)Deleted"MOV 1793 used for long-term isolation" under Notes and replaced with Note 12;(7)Added"NA">>93: Added"Outside" under Position Relative To Containment for valve 1793;(9)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration.
(4)(5)No technical change.(6)Minor clarification.
No technical change.(7)Correction of typographical omission.No technical change.(8)Correction of typographical omission.No technical change.(9)Valves now in numeric order.No technical change.33.Penetration 130-(1)Changed Position Indication In Control Room from"Yes" to"Both";(2)Corrected associated valve number to 814.(1)Minor clarification only.No technical change.(2)Correction of typographical error.No technical change.34.Penetration 131-(1)Changed Position Indication In Control Room from"Yes" to"Both";(2)Corrected associated valve number to 813.(1)Minor clarification only.No technical change.(2)Correction of typographical error.No technical change.Safety Analysis NSL-0000-SA024 Page 26 Revision 0
~'I 0 0 35.Penetration 132-(1)Changed Maximum Isolation Time from"2" to"3" for both valves;(2)Changed Position At Normal"/'971;(3)Changed Position At Cold Shutdown from"C" to"0/C" for both valves;(4)Changed Position Indication In Control Room from"Yes" to"Both" for both valves.(1)Consistency with Technical Specifications.
Valve design allows closure as rapid as 2 (two)seconds.Minimum closure time required by Technical Specifications is 5 (five)seconds with instrument delay.(2)(3)Update for better representation of system configuration.
Mini-Purge system only designed for use during shutdown conditions.
(4)Minor clarification only.No technical change.36.Penetration 140-(1)Added Note 6;(2)Added Note 7;(3)Changed Position Indication in Control Room from"Yes" to IIR/Gll (1)Consistency with Technical Specification Table 3.6-1 Note 20.(2)No technical change.(3)Minor clarification only.No technical change.37.Penetration 141-(1)Deleted valve 851A (entire line in table);(2)Added valve 1813A and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 850A;(4)Added Note 8 to valve 1813A.(1)Valve 851A does not meet the selection criteria of lOCFR50 Appendix J, Section IIH, items.1 through 4.Therefore, valve was deleted from table.(2)Valve 1813A was previously missing from table.(3)Minor clarification only.No technical change.(4)No technical change.Safety Analysis NSL-0000-SA024 Page 27 Revision 0 l
38.Penetration 142-(1)Deleted valve 851B (entire line in table);(2)Added valve 1813B and necessary information; (3)Changed Position Indication In Control Room from"Yes" to"R/G" for valve 850B;(4)Added Note 8 to valve 1813B.(1)Valve 851B does not meet the selection criteria of 10CFR50 Appendix Jg Section IIH, items 1 through 4.Therefore, valve was deleted from table.(2)Valve 1813B was previously missing from table.(3)Minor clarification only.No technical change.(4)No technical change.39.Penetration 143-(1)Changed Position Indication In Control Room from"Yes" to"Status" for all three valves;(2)Changed Position At Normal 0 eration from"0/C" to"0" for valves 1003A and 1003B;(3)Reordered penetration valves.(1)Minor clarification only.No technical change.(2)Update for better representation of system configuration.
(3)Valves now in numeric order.No technical change.40.Penetration 201top-Global Notes 3 and 4.No technical change.41.Penetration 20lbottom-Global Notes 3 and 4.No technical change.Safety Analysis NSL-0000-SA024 Page 28 Revision 0 42.Penetration 202-(1)Changed valves 1076B and 1084B from"Globe" to"Diaphragm";
(2)Changed Position At Normal 0 eration Cold Shutdown Immediate Postaccident from"C" to"LC" for valves 1076B and 1084B;(3)Global Notes 3 and 4 for valves 1076B and 1084B;(4)Added"No" under Position Indication in Control Room for valves 1076B and 1084B;(5)Changed Valve No.for IV-3B and IV-5B to 10211S1 and 10213S1, respectively; (6)Added"Status" under Position Indication in Control Room for valves 10211S1&10213S1;(7)Changed Position At Power Failure from"-" to"FC" for valves 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.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.(4)Correction of typographical omission.No technical change.(5)Update to new valve number only.No technical change.(6)Correction of typographical omission.No technical change.(7)(8)Update for better representation of system configuration.
Valves receive containment isolation signal.(9)Correction of typographical error.No technical change.(10)Valves now in numeric order.No technical change.43.Penetration 203a-(1)Included separate lines in table for valves 1819C and 1819D;(2)Added"Outside" to Position Relative to Containment for PT947 and PT948;(3)Added"Globe" under Valve~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.(1)Minor clarification
-there are two valves.No technical change.(2)(3)Correction of typographical omission.No technical change.(4)(5)No technical change.Safety Analysis NSL-0000-SA024 Page 29 Revision 0 jÃo+g)44.Penetration 203b-(1)Global Notes 3 and 4;(2)Added"Diaphragm" under Valve~T e for all four valves;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to"LC" for all four valves.(1)No technical change.(2)Correction of typographical omission.No technical change.(3)Consistency with Ginna Administrative Control.45.Penetration 204-(1)Added Note 2 to Blind Flange;(2)Global Note 1 for Blind Flange;(3)Changed Position Indication in Control Room from"Yes" to"Both" for valve 5869;(4)Changed position At Normal 0 eration from"0/C" to"C" for valve 5869;(5)Changed Position At Cold Shutdown from"0" to"0/C" for 5869;(6)Changed Maximum Isolation Time from"5" to"NA" for valve 5869;(7)Added Note 19.(1)(2)No technical change.(3)Minor clarification only.No technical change.(4)(5)Update for better representation of system configuration.
Penetration only used during cold shutdown conditions.
Mini-purge system now used in place of purge system.(6)The Blind Flange acts as the isolation boundary.Therefore, no isolation'time is required for the valve.(7)No technical change.46.Penetration 205-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 966C;(2)Added valve 955 and necessary information; (3)Changed Position Indication in Control Room from"Yes" to"Status" for valve 966C;(4)Changed Position At Normal 0 eration and Position At Cold Shutdown from"0/C" to"C" for valve 966C;(5)Global Notes 3 and 4 for valve 956D;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Valve receives containment isolation signal and was previously missing from the table.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration.
Sampling system normally isolated.(5)No technical change.(6)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 30 Revision 0 Date 09 24 90
49 Penetration 207a-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 966A;(2)Added valve 951 and necessary information; (3)Changed Position Indication in Control Room from"Yes" to"Status" for valve 966A;(4)Changed Position At Normal 0 eration and Position At Cold Shutdown from"0/C" to"C" for valve 966A;(5)Global Notes 3 and 4 for valve 956F;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Valve receives containment isolation signal and was previously missing from the table.(3)Minor clarification only.No technical change.(4)Update for better representation of system configuration.
Sampling system normally isolated.(5)No technical change.(6)Valves now in numeric order.No technical change.50.Penetration 207b-(1)Changed Maximum Isolation Time from"NA" to"60" for valve 5736;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5736;(3)Changed Position At Normal 0 eration from"0/C" to"0" for valve 5736;(4)Changed Position At Cold Shutdown from"0/C" to"C" for valve 5736;(5)Global Notes 3 and 4 for 5734;(6)Reordered penetration valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)(4)Update for better representation of system configuration.
(5)No technical change.(6)Valves now in numeric order.No technical change.51.Penetration 209top-(1)Global Notes 3 and 4;(2)Reordered penetration valves.(1)No technical change.(2)Valve order now consistent with other penetrations.
No technical change.52.Penetration 209bottom-(1)Global Notes 3 and 4;(2)Reordered penetration valves.(1)No technical change.(2)Valve order now consistent with other penetrations.
No technical change.Safety Analysis NSL-0000-SA024 Page 32 Revision 1 53.Penetration 210-(1)Added"A&B" before"Reoombiners" under~3 stem;(2)Added Position Indication in Control Room to"Status" for all solenoid valves;(3)Added"Yes" under~Tri on CIS for all solenoid valves;(4)Added valves 10214S1 and 10215S and necessary information; (5)Changed Position At Power Failure from"-" to"FC" for all solenoid valves;(6)Changed Position At Normal 0 eration Cold Shutdown Immediate Postaccident from"C" to"LC" for 1080A;(7)Global Notes 3 and 4 for valve 1080A;(8)Changed Valve No.for IV-2A and IV-2B to 10214S and 10215S1, respectively; (9)Added Note 18 to solenoid valves;(10)Changed Maximum Isolation Time from"NA" to"3" for all solenoid valves.(1)Consistency with Technical Specification Table 3.6-1.(2)Minor clarification only.No technical change.(3)Correction of typographical omission.No technical change.(4)Valve receive containment isolation signal and was previously missing from the table.(5)Update for better representation of system configuration.
Valves receive containment isolation signal.(6)Consistency with Ginna Administrative Control.(7)No technical change.(8)Update to new valve number only.No technical change.(9)No technical change.(10)Correction of typographical error.No technical change.-54.Penetration 300-(1)Added Note 19 for both valve and flange;(2)Added Note 2 to Blind Flange;(3)Global Note 1 for Blind Flange;(4)Changed Position At Normal 0 eration from"0/C" to"C" for valve 5879;(5)Changed Position At Cold Shutdown from"0" to"0/C" for valve 5879;(1)No technical change.(2)Consistency with Technical Specifications.
No technical change.(3)(4)Update for better representation of system configuration.
Penetration only used during cold shutdown conditions.
Mini-purge system now used in place of purge system.Safety Analysis NSL-0000-SA024 Page 33 Revision 0 Date 09 24 90 55.Penetration 301-(1)Global Notes 3 and 4;(2)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"0" to"LC" for both valves;(3)Added Note 5 to both valves.(1)No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.56.Penetration 303-(1)Global Notes 3 and 4;(2)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"0" to"LC" for both valves;(3)Added Note 5 to both valves;(4)Changed both valves from"Diaphragm" to"Globe";(5)Reordered penetration valves.(1)No technical change.(2)Consistency with Ginna Administrative Control.(3)No technical change.(4)Correction of typographical error.No technical change.(5)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 34 Revision 0 Date 09 24 90 57.Penetration 304-(1)Changed valves 1076A and 1084A from"Solenoid" to"Diaphragm";
(2)Changed Position At Normal 0 eration Cold Shutdown and Immediate Postaccident from"C" to"LC" for valves 1076A and 1084A;(3)Added"No" under Position Indication In Control Room for valves 1076A and 1084A;(4)Global Notes 3 and 4 for valves 1076A and 1084A;(5)Changed Valve No.for IV-3A and IV-5A to 10205S1 and 10209S1, respectively; (6)Added"Status" under Position Indication in Control Room for valves 10205Sl&10209S1;(7)Changed Position At Power Failure from"-" to"FC" for valves 10205Sl and 10209S1;(8)Changed~Tri'n CIS from"No" to"Yes" for valve 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.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)Correction of typographical omission.No technical change.(4)No technical change.(5)Update to new valve number only.No technical change.(6)Minor clarification only.No technical change.(7)(8)Update for better representation of system configuration.
Valves receive containment isolation signal.(9)No technical change.(10)Correction of typographical error.No technical change.(11)Valves now in numeric order.No technical change.58.Penetration 305a (bottom)-(1)Changed~Sstem to"Containment Air Sample Out";(2)Changed Maximum Isolation Time from"NA" to"60" for valve 1597;(3)Changed valve 1596 from"Diaphragm" to"Globe";(4)Global Notes 3 and 4 for valve 1597;(5)Changed Position Indication in Control Room from"Yes" to"Both" for valve 1597;(6)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.No technical change.(2)Consistency with Technical Specification Table 3.6-1.(3)Correction of typographical error.No technical change.(4)No technical change.(5)Minor clarification only.No technical change.(6)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 35 Revision 0 59.Penetration 305b (top)-(1)Changed~S stem to"Containment Air Sample Inlet";(2)Changed Maximum Isolation Time from"NA" to"60" for valve 1599;(3)Changed Position Indication in Control Room from"Yes" to"Both" for valves 1598 and 1599;(4)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.(2)Consistency with Technical Specification Table 3.6-1.(3)Minor clarification only.No technical change.(4)Valves now in numeric order.No technical change.60.Penetration 305c-<1)Changed~S stem to"Containment Air Sample Postaccident";
for all six valves;(3)Changed Position At Cold Shutdown and Position At Immediate Postaccident from"C" to"LC" for all six valves;(4)Global Notes 3 and 4;(5)Reordered penetration valves.(1)Consistency with UFSAR Drawing Title.(2)Correction of typographical omission.No technical change.(3)Consistency with Ginna Administrative Control.(4)No technical change.(5)Valves now in numeric order.No technical change.61.Penetration 307-(1)Switched Valve No.for valves 9227 and 9229;(2)Added"Gate"-under Valve 0 erator T e for valve 9227;(3)Global Notes 1, 2, and 4 for valve 9229;(4)Changed Position Indication in Control Room from"Yes" to"Both" for valve 9227.(1)Correction of typographical error.No technical change.(2)Correction of typographical omission.No technical change.(3)No technical change.(4)Minor clarification only.No technical change.62.Penetration 308-(1)Changed Valve No.to 4629;(2)Global Notes 3 and 4;(3)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(4)Changed Position At Cold Shutdown from"0" to"0/C" (5)Added Note 17.(1)Correction of typographical error.No technical change.(2)No technical change.(3)Consistency with Ginna Administrative Control.(4)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown.(5)No technical change.Safety Analysis NSL-0000-SA024 Page 36 Revision 0
- ,P><><~!~
A.,gyes-.gory
~gg,~:>FQKQ<,.4idsi, 63.Penetration 309-(1)Changed Maximum Isolation Time from"2" to"3" for both valves;(2)Changed Position Indication in Control Room from"Yes" to"Both" for both valves;(3)Reordered penetration valves.(1)Consistency with Technical Specifications.
Valve design allows closure as rapid as 2 (two)seconds.Minimum closure time required by Technical Specifications is 5 (five)seconds.(2)Minor clarification only.No technical change.(3)Valves now in numeric order.No technical change.64.Penetration 310a-(1)Changed valve 7141 from"Diaphragm" to"Gate";(2)Changed Position At Immediate Postaccident from"C" to"LC" for valve 7141;(3)Global Notes 3 and 4 for valve 7141;(4)Global Notes 1, 2, and 4 for valve 7226;(5)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Consistency with Ginna Administrative Control.(3)(4)No technical change.(5)Valves now in numeric order.No technical change.65.Penetration 310b-(1)Changed valve 5392 from"Diaphragm" to"Globe";(2)Changed Position Indication in Control Room from"Yes" to"Both" for valve 5392;(3)Changed Position At Cold Shutdown from"C" to"0" for valve 5393;(4)Global Notes 1, 2, and 4 for 5393;(5)Added"0" under Position At Cold Shutdown for valve 5392;(6)Added"C" under Position At Immediate Postaccident for valve 5392;(7)Changed Position at Power Failure from"-" to"FC" for valve 5392;(8)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration since IA is used during cold shutdown conditions.
(4)No technical change.(5)(6)(7)Update for better representation of system configuration.
Valve receives containment isolation signal.(8)Valves now in numeric order.No technical change.Safety Analysis NSL-0000-SA024 Page 37 Revision 0 Date 09 24 90
'I~
Penetration 311-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4.(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions.
(2)Consistency with Ginna Administrative Control.(3)No technical change.67.Penetration 312-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4~(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions.
(2)Consistency with Ginna Administrative Control.(3)No technical change.68.Penetration 313-(1)Added"Blind" Global Notes 1, 2, and 4 for Blind Flange;(3)Changed Position Indication in Control Room from"Yes" to"Status" from"No" to"Yes" for valve 7444;(5)Added Note 19.(1)Correction of typographical omission.No technical change.(2)No technical change.(3)Minor clarification only.No technical change.(4)Correction of typographical error.No technical change.(5)No technical change.69.Penetration 315-(1)Changed Position At Cold Shutdown from"0" to"0/C";(2)Changed Position At Normal 0 eration and Position At Immediate Postaccident from"0" to"LO";(3)Global Notes 3 and 4.(1)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions.
(2)Consistency with Ginna Administrative Control.(3)No technical change.Safety Analysis NSL-0000-SA024 Page 38 Revision 0 Date 09 24 90
74.Penetration 320-(1)Global Notes 3 and 4;(2)Changed Position At Normal Postaccident from"0" to"LO";(3)Changed Position At Cold Shutdown from f!Off to nO/Ctt (1)No technical change.(2)Consistency with Ginna Administrative Control.(3)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions.
75.Penetration 321-(1)Global Notes 3 and 4 for valve 5701;(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5738;(3)Changed Position At Cold Shutdown from"C" to"0/C" for valve 5738;(4)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical.
change.(3)Update for better representation of system configuration.
(4)Valves now in numeric order.No technical change.76.Penetration 322-(1)Global Notes 3 and 4 for valve 5702.(2)Changed Position Indication in Control Room from"Yes" to"Status" for valve 5737;(3)Changed Position At Cold Shutdown from"C" to"0/C" for valve 5737;(4)Reordered penetration valves.(1)No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration.
(4)Valves now in numeric order.No technical change.77.Penetration 323-(1)Global Notes 3 and 4;(2)Changed Position At Normal Postaccident from"0" to"LO";(3)Changed Position At Cold Shutdown from"0" to"0/C" (1)No technical'change.(2)Consistency with Ginna Administrative Control.(3)Update for better representation of system configuration since fan coolers may be isolated for maintenance during cold shutdown conditions.
Safety Analysis NSL-0000-SA024 Page 40 Revision 1 Date 10 3 90 78.Penetration 324-(1)Changed valve 8418 from"Diaphragm" to"Globe";(2)Changed Position At Cold Shutdown from"0" to"0/C" for valve 8418;(3)Changed Position Indication in Control from"Yes" to"Both" for valve 8418;(4)Global Notes 1, 2, and 4;(5)Changed Maximum Isolation Time from"NA" to"60" for valve 8418;(6)Reordered penetration valves.(1)Correction of typographical error.No technical change.(2)Update for better representation of system configuration.
(3)Minor clarification only.No technical change.(4)No technical change.(5)Correction of typographical error.No technical change.(6)Valves now in numeric order.No technical change.79.Penetration 332a-(1)Global Note 1 for pressure transmitters; (2)Added"Globe" h valves;(3)Global Note 3 for the manual valves;(4)Reordered penetration valves.(1)No technical change.(2)Correction of typographical omission.No technical change.(3)No technical change.(4)Valves now in numeric order.No technical change.80.Penetration 332b-Deleted entire penetration from table.Penetration has double isolation and 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" under UFSAR Fi ure for all valves other than 922.(2)Changed Position Indication in Control Room from"Yes" to"Both" for all four valves;(3)Changed Position At Immediate Postaccident from"0/C" to"C" for all valves.(1)Correction of typographical omission.No technical change.(2)Minor clarification only.No technical change.(3)Update for better representation of system configuration.
System isolated upon receipt of containment isolation signal.Safety Analysis NSL-0000-SA024 Page 41 Revision 0 Date 09 24 90 82.Penetration 401-(1)Added Note 11 to all valves other than 3517;(2)Changed 3517;(3)Changed Position Indication in Control Room from"Yes" to"R/G" for valves 3505A and 3517;(4)Global Notes 1, 2, 3, 4, and 5;(5)Reordered penetration valves.(1)Correction of typographical omission.No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)No technical change.(5)Valves now in numeric order.No technical change.83.Penetration 402-(1)Added Note 11 to all valves other than 3516 and 3518;(2)valve 3516;(3)Changed Position Indication in Control Room from"Yes" to"R/G" for valves 3504A and 3516;(4)Global Notes 1, 2, 3, 4, and 5;(5)Reordered penetration valves.(1)Correction of typographical omission.No technical change.(2)Correction of typographical error.No technical change.(3)Minor clarification only.No technical change.(4)No technical change..(5)Valves now in numeric order.No technical change.84.Penetration 403-(1)Global Notes 1, 2, 3.from"6.2-75" to"6.2-76" for valve 3995;(3)Added"6.2-76" under UFSAR Ficiure for all valves after valve 3995;(4)Added Note 11 to all valves other than valve 3995;(5)Added"4" under Class for all valves other than 3995;(6)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)(4)(5)Correction of typographical omission.No technical change.(6)Valves now in numeric order.No technical change.85.Penetration 404-(1)Global Notes 1, 2, from"6.2-75" to"6.2-76" for valve 3994;(3)Added Note 9 to all valves other than 4000D;(4)Reordered penetration valves.(1)No technical change.(2)Correction of typographical error.No technical change.(3)Correction of typographical omission.No technical change.(4)Valves now in numeric order.No technical change;Safety Analysis NSL-0000-SA024 Page 42 Revision 0 86.Penetration 1000-(1)Global Notes 1, 2, 4, and 5;(2)Added"Both" to Position Relative to Containment; (3)(1)No technical change.(2)(3)Correction of typographical omission.No technical change.87.Penetration 2000-(1)Global Notes 1, 2, 4, and 5;(2)Added"Both" to Position Relative to Containment; (3)"3.8-3 IV'1)No technical change.(2)(3)Correction of typographical omission.No technical change.Safety Analysis NSL-0000-SA024 Page 43 Revision 0 (1)Deleted last sentence of"old" Note 1 and moved it to"new" Note 2;(2)Renumbered remaining"old" Note 1 as Note 3.(1)(2)The deleted sentence of the note is still applied to necessary penetrations.
No technical change.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" Note 4;(2)Modified last sentence to reflect system configuration; (3)Renumbered"old" Note 4 as Note 6.(1)These two sentences only duplicated UFSAR text.No technical change.(2)Sentence now accurately reflects 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 NSL-0000-SA024 Page 44 Revision 0 Date 09 24 90 9.(1)Modified"old" Note 9;(2)Renumbered"old" Note 9 as Note 13.(1)(2)Minor clarification only.Note 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)Renumbered to"new" Note 15.Minor clarification only.change.No technical 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" Note 14 and moved it to"new" Note 16;(2)Modified remaining"old" Note 14;(3)Renumbered"old" Note 14 as Note 17.(1)The deleted sentence of the note is still applied to necessary penetrations.
No technical change.(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)Renumbered"old" note 17 as Note 21.(1)(2)Minor clarification of note only.No technical change.Safety Analysis NSL-0000-SA024 Page 45 Revision 0 4
32.Added Note 20.Minor clarification only.Note provides additional information related to penetration's use.No technical change.Safety Analysis NSL-0000-SA024 Page 48 Revision 0 Date 09 24 90 18.(1)Modified"old" Note 18;(2)Renumbered"old" Note 10 as Note 11.(1)(2)Minor clarification of note 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 NSL-0000-SA024 Page 46 Revision 0 k
25.Added Note 9.%RP)>h~r..'".'~>Y&Q<<>.vÃF>N4!jFrvca44AYY+cPc>'~>>@48<44~AAC NK+AA~>~>Y4s.."4%gggg 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 NSL-0000-SA024 Page 47 Revision 0 Chanches Table 1 Technical Specification Changes Effect Section 3.6.3.1 references UFSAR Table 6.2-13 instead of Technical Specification Table 3.6-1.No technical change.2.Table 3.6-1 removed from Technical Specifications and information placed in UFSAR Table 6.2-13.Valve listing remains in a licensee controlled document under 10CFR50.59 program.3.4.Revised inoperable definition of Section 3.6.3.1.Removed note associated with Technical Specification 3.6.5.No technical change.Clarification only consistent with 10CFR50 Appendix J.Mini-purge valves have been installed so the Technical Specification can be considered effective.
No technical change.5.Added"Pt" and necessary~~~~definitions to Technical Specification 4.4.1.4 section a.Addition of"Pt" provides clarification of testing type consistent with 10CFR50, Appendix J.All terms in 4.4.1.4, section a now fully defined.No technical change.7.8.Added to the definition of"Lt" in Technical Specification 4.4.1.4 section b.Added definition of"Pa" and"Lam" in Technical Specification 4.4.1.4 section c.Added steam generator inspection/maintenance penetration to Technical Specification 4.4.1.5 section a (ii).Added definition"Lt" provides clarification consistent with 10CFR50, Appendix J.All terms in 4.4.1.4, section b now fully defined.No technical change.Addition of"Pa" and"La" provides clarification consistent with 10 CFR 50, Appendix J.All terms in 4.4.1.4, section c now fully defined.No technical change.Addition of this penetration provides testing criteria similar to the equipment hatch and containment air locks.9.Revised first line of Technical Specification 4.4.1.5, section a (ii).Minor clarification only.No technical change.
Removed notes associated with Technical Specification 4.4.2.4 section a.Deleted reference to section d.Mini-purge valves have been installed so the Technical Specification can be considered effective.
Section d will be removed from Technical Specifications.
No technical change.11.Added steam generator inspection/maintenance penetration to Technical Specification 4.4.2.4 section b.Addition of this penetration provides testing criteria similar to the equipment hatch and containment air locks.12.Removed Technical Specification 4.4.2.4 section d and associated note.Blind flanges have been installed so the Technical Specification can be considered effective.
No technical change.1 3.Changed Reference from Table 3.6-1 to UFSAR 6.2-13 in section 4.4.5.1.14.Changed Reference from Table 3.6-1 to UFSAR 6.2-13 in section 4.4.6.2.Valve listing remains in a licensee controlled document under 10CFR50.59 program.Valve listing remains in a licensee controlled document under 10CFR50.59 program.
~~0