AECM-84-0251, Forwards Outstanding Tech Spec Problem Sheets,Per 840420 & 25 Requests.Info Includes Revs 23 Through 28,completing 840409 Submittal Incorporating All Changes Through Rev 22. Rev 28 New Problem Sheets Provide Tracking Mechanism
| ML20084F342 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/01/1984 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AECM-84-0251, AECM-84-251, NUDOCS 8405040091 | |
| Download: ML20084F342 (277) | |
Text
MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B OX 1640. J AC K S O N, MIS SIS SlP PI 3 9 2 05 NUCLEAR PRODUCTION DEPARTMENT May 1, 1984 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-13 File 0260/L-860.0 Transmittal of Outstanding Technical Specification Problem Sheets AECM-84/0251 In a meeting held between members of your staff and Mississippi Power & Light Company (MP&L) representatives on April 20, 1984, MP&L was requested to provide all outstanding Technical Specification Problem Sheets (TSPS). This request was formalized in an April 25, 1984, letter to MP&L from Elinor Adensam of your staff and was clarified during the followup meeting of April 27, 1984. In response to your request, MP&L is providing the attached TSPS for your review. This information is in the form of revisions to the TSPS and includes Revisions 23 through 28. These problem sheets along with those previously submitted in the April 9, 1984 MP&L letter AECM-84/0217 (which incorporated all changes through Revision 22) provide a complete and updated set of problem sheets.
At the April 27, 1984 meeting, the NRC requested and MP&L agreed to provide eleven new problem sheets. These new problem sheets (which are included in Revision 28) have been generated to provide a convenient tracking mechanism for certain NRC initiated items. MP&L is committed to work with the NRC to satisfactorily resolve these issues simultaneously with the problem sheets generated during the Technical Specification Review Program (TSRP). However, since these problem sheets were generated outside the TSRP, the matrix of TSRP results and the delineation of identified discrepancies which were provided in MP&L letters AECM-84/0217 and AECM-84/0229 of April 9, 1984 and April 29, 1984 will not be revised to reflect the content of these new problem sheets.
8405040091 840501 PDR ADOCK 05000416 P PDR Member Middle South Utilities System
MIMISSIPPI POWER Q LIGHT COMPANY AECM-84/0251 May 1, 1984 Page 2 Please advise if additional information is required.
Yours truly,
,bY L. F. Dale 3c,
'/ Manager of Nuclear Services SHH/mm Attachment cc: Mr. J. B. Richard, (w/a)
Mr. R. B. McGehee (w/o)
Mr. N. S. Reynolds (w/o)
Mr. G. B. Taylor (w/o)
Mr. ' Richard C. DeYoung, Director (w/a)
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. P. O'Reilly, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission-Region II 101 Marietta Street, N.W. , Suite 2900 Atlanta, Georgia 30303 Lm .
MISSISSIPPI POWER & LIGHT COMPANY
[d Helping Build Mississippi -
D P. O. BOX 1640. J ACKSON MISSIS SIPPI 3 9205 NUCLE AR PRODUCf.ON DI PARTMENT May 1, 1984 1
Office of Nuclear Reactor Regulat. ion j U. S. Nuclear Reg'. latory Commission ,
Washington, D. C. 20555 ,
s Attention: Mr. Harold R. Denton, Director f l .
Dear Mr. Ilenton:
SUBJECI': Gr.and Gulf Nuclear Station- .
- / Units 1.and 2 Docket Nos. < 50-416 and 50-417 License No. NPF-13 j .
File 0260/L-860.0 l Transmittal of Outstanding Technical Specification Problem Sheets
~
.c _
AF,CM-84/0251 In a meeting held betweer. members of your staff and Mississippi Power & Light Company (MP&L) rdpresentatives on April'20, 1984, MP&L was requested to provide all outstanding Technical Specification Problem Sheets (TSPS). This request was< formalized in a.1 Apri,125,1984, letter to MP&L from Elinor Adensam of'your staff and was crarified during the followup meeting of April '
27, 1984. In response to your request, HP&L<is.providing the attached TSPS for your review. This information is in the form of revisions to the TSPS and '
includes Revisions 23 through 28. These problem ' sheets along with those previously submitted in the April 9,1984 MP&L letter ALCM-84/0217 (which .
incorporated all changes through Revision 22) prodde i complete and updated '"
set of problem sheets. *
,/
~
At the April 27, 1984 meeting,theNRCrequestedand4fP&Lagreedto3rovide '
eleven new problem sheets. These new problem sh'eets (which are included'in Revision 28) have been generated to provide a' convenient.trackincj mechanism' e' for 'certain URC initiated items. MP&L is committed to work with the NRC to
- satisfactorily resolve these issues simultaneously with the problem sheets .. ,
generated during the lechnical Specification Review Program (TSRP). However, "
since these problem sheets were generated outside the TSRP, the matrix of TSRP:
results and the delineation of ide:ntifie(. discrepancies which were provided in.~
MP&L letter's AECM-84/0217 and:AECM-84/0229 of April 9,1984 -an'd April 29, .
1984 will not be revised to reflect the content of these new prob!em sheets.S.
,- e, - w u .n l- Y 'N 3 / ' .; t:
4 ,
j.
, . ') ; .Q .
,aa
~
Member Middle South Util,ities'Syste'm
- ._ _% ,_ J._. La. ,. _ _ ._ _ %~.
MISSISSIPPI POWER & LIGHT COMPANY AECM-84/0251 May 1, 1984 Page 2 Please advise if additional information is required.
Yours truly,
) p IMk L. F. Dale Manager of Nuclear Services SHH/mm Attachment cc: Mr. J. B. Richard, (w/a)
Mr. R. B. McGehee (w/o)
Mr. N. S. Reynolds (w/o)
Mr. G. B. Taylor (w/o)
Mr. Richard C. DeYoung, Director (w/a)
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ,
Mr. J. P. O'Reilly, Regional Administrator (w/a)
U. S. f4uclear Regulatory Conrnission Region II ,
lanta Ge r a 35303 1
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D MEMO TO: Tech Spec Review Personnel
" TECH SPEC PRIORITY" TROM: C. L. Tyrone
SUBJECT:
Rev. n to Technical Specification Problem Sheet TSRT: 84/ 09 a6 DATE: S sn', \ 10.19 34 6
The following changes / additions are to be incorporated into the Tech Spec Problem Sheets:
ITEM NUMBER CHANGES / ADDITION 34lo Mamous s v S lj IkepcI bv23 Ria h, Rg 0QTam+ b, 23 SIlp Trumsleu - 1w<seYMev.43 SI9 lsenvt t v- .Tw smet hv.23 SIS ln enJe Mav. IN spek VMS EI9 Mewvs Mav T u s e: e+ Mvv03 9An hnv e Lv -- L,e ct hv 2 3
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I s
C. L. Tyronet CLT: sad Attachment
- s cc: S. H. Hobbs (w/1)
. File (Tech Spec Records) (w/1)
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TSRT-84/09a(o 1
PROBLEM SHEET LISTING AS OF kno,i 1019N Data REVIEVED BY RPD PRIORITY REVISION, DATE ITEM NUMBER I IB 15, 3/29/84 001 I 2E 15, 3/29/84 002 003 1 2D 17, 4/01/84 I 2E 22, 4/09/84
! 004 I 1B 15, 3/29/84 005 I 2D 21, 4/08/84 006 007 I 2F 15, 3/29/84 008 I 2H 17, 4/01/84 009 I 2D 17, 4/01/84 010 I 2B 15, 3/29/84 011 I 2B 15, 3/29/84 -
012 I 2D 18, 4/02/84 I 3A 21, 4/08/84 013 I 2B 21, 4/08/84 014 015 I IB 17, 4/01/84 016 I 1B 15, 3/29/84 -
I 2D 15, 3/29/84 017 018 I 3B 15, 3/29/84 I 2B 15, 3/29/84 019 020 I 2B 17, 4/01/84 021 I IC 15, 3/29/84 022 I 2A 17, 4/01/84 23 15, 3/29/84 023 I 024 I 2B 18, 4/02/84 025 1 2D 17, 4/01/84 026 I 2D 15, 3/29/84 027 I 2E 15, 3/29/84 028 I 2B 15, 3/29/84 I 3B 17, 4/01/84 029 I 2D 17, 4/01/84 030 031 I 2D 17, 4/01/84 I 2B 21, 4/08/84 032 I 1B 18, 4/02/84 033 I IC 18, 4/02/84 034 035 I 2C 15, 3/29/84 L26sd1
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PROBLEM SHEET LISTING ITIM NUMBER REVIIVED ET RPD 7110RITT REVISION, DATE
^
036 I 2E . 20, 4/06/84 037 I 1C 15, 3/29/84 ,
1 038 I IC 15, 3/29/84-039 I 2G 17, 4/01/84 040 I 2F 17, 4/01/84 041 I 23 21, 4/08/84 042 I 2B 15, 3/29/84 043 1 2D 15, 3/29/84 044 I 3B 17, 4/01/84 045 I 23 17, 4/01/84 046 I 2F 15, 3/29/84 047 I 2B 15, 3/29/84 048 I 2H 15, 3/29/84 049 I 2B 18, 4/02/84 050 1 2B 17, 4/01/84 051 I 2D 15, 3/29/84 052 I 2E 15, 3/29/84 l
l , 053 I 2E 17, 4/01/84 054 I IB 21, 4/08/84 055 I ZD 15, 3/29/84 056 I 3B 21, 4/08/84 057 I 2B 17, 4/01/84 058 I 2D 17, 4/01/84 059 I 2D 17, 4/01/84 060 I 2B 15, 3/29/84 061 I 2D 15, 3/29/84 062 I 2E 18, 4/02/84
[ 063 I 2E 17, 4/01/84 064 I 2E 15, 3/29/84 l
065 I 2E 15, 3/29/84 '
066 I 2D 22, 4/09/84 !
067 I 2D 15, 3/29/84 068 I 3B 15, 3/29/84 069 I 21 17, 4/01/84 070 I 35 18, 4/02/84 071 I 2D 17, 4/01/84 j 072 I 2D 17, 4/01/84 L26sd2
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! PROBLEM SHILT LISTING l
ITIM NUMBER RE7IEVED BY IPD PRICHITT RT71SION, DATE
~
j 073 I 25 18, 4/02/84 074 I 2D 17, 4/01/84 075 1 23 17, 4/01/84
. 076 I 13 18, 4/02/84 077 I 23 21, 4/08/84 078 I IB 15, 3/29/84 j 079 I 2E 15, 3/29/84 080 I N/A (Rasolved) 15, 3/29/84 081 I 3A 15, 3/29/84 j 082 I 3A 15, 3/29/84 I 083 I 2B 22, 4/09/84 l
084 I 3A 15, 3/29/84 085 I 2D 20, 4/06/84 086 I 2D 18, 4/02/84 087 I 2D 17, 4/01/84 088 I 2D 17, 4/01/84 089 I 2D 15, 3/29/84 090 I 2D 17, 4/01/84 g
091 I 2D 15, 3/29/84 0- 092 I 2D 18, 4/02/84 093 I 2E 22, 4/09/84 094 I 2D 21, 4/08/84 095 1 2E 22, 4/09/84 i
096 'I 2E 15, 3/29/84 097 I 2E 15, 3/29/84 098 I 2G 15, 3/29/84 099 I 2G 21, 4/08/84 100 I 35 18, 4/02/84 101 I 2E 15, 3/29/84 l 102 I 2B 15, 3/29/84 103 I 1B 18, 4/02/84 104 I 2E 17, 4/01/84 105 I 2E 15, 3/29/84 106 I 2E 18, 4/02/84 107 I 2E 18, 4/02/84 108 x 2C 15, 3/29/84 N 109 I 2D 15, 3/29/84 l l l L26sd3
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4- , ,
PROBLZM SHZZT LISTING
,- ITIM NUMBER RZvIZUED BT IFD FRIORITT EETISIOtt, DATI 110 1 21 17, 4/01/84 111 I 2D 18, 4/02/84
, 112 I 2A 15, 3/29/84
' 113 I N/A (Rasolved) 15, 3/29/84 l 114 I 2B 18, 4/02/84 115 2 2D 17, 4/01/84 116 I 2B 15, 3/29/84 117 I N/A (Resolved) 18, 4/02/84 118 I 2D 16, 3/31/84 119 I 2B 15, 3/29/84 120 I 2D 18, 4/02/84 121 I N/A (Resolved) 15, 3/29/84 122 I 2D 17, 4/01/84 123 1 2D 18, 4/02/84
}, 124 I 2C 18, 4/02/84 125 I N/A (Rasolved) 18, 4/02/84 i 126 I 2D 15, 3/29/84 p 127 1 2C 17, 4/01/84
, 128 I 2D 17, 4/01/84 129 I 1B 15, 3/29/84 130 I N/A (Resolved) 15, 3/29/84 131 I 2C 15, 3/29/84 132 I 2B 15, 3/29/84 133 I 2D 18, 4/02/84
- 134 I 2D 17, 4/01/84
- 135 I N/A (lasolved) 18, A/02/84 4
136 I 2D 15, 3/29/84 137 I 23 15, 3/29/84 138 I ZD 15, 3/29/84 139 I IC 15, 3/29/34 l 140 I 2D 18, 4/02/84 141 I ~27 17, 4/01/84 i 142 I 27 15, 3/29/84 j ,
143 1 2C 15, 3/29/84 i
144 I 23 15, 3/29/84
- 145 1 27 17, 4/01/84 3
5 146 x :I 15, 3/29/SA L26sde l
1
. PEDBLEM SEIZI I.ISTING
,_ m x w ets u u mvrD n wD nior m nZvis2cs, DAXI l
l 147 I 3 16, 3/31/84 148 I 3A 17, 4/01/84 149 I 35 18, 4/02/84 150 I 2C 17, 4/01/84 151 I 33 17, 4/01/84
, 152 I 2I 16, 3/31/84 153 1 25 17, 4/01/84 154 I 2D 16, 3/31/84
)~ 155 I 2D 18, 4/02/84 i 156 -
I 2D 17, 4/01/84 157 I 2D 17, 4/01/84
- 158 I 2D 17, 4/01/84 159 I ZD 16, 3/31/84 160 I 2I 21, 4/08/84
,, 161 I 2I 18, 4/02/84 162 I 2D 16, 3/31/84 l
163 I 2D 16, 3/31/84 !
. dr 164 I 2B 18, 4/02/84 4
165 I 2D 17, 4/01/84 166 I 38 17, 4/01/84 167 f I 2B 17, 4/01/84 168 I 23 21, 4/08/84 169 I ,
2D 18, 4/02/84 170 I 22 16, 3/31/84
! 171 I 2D 16, 3/31/84 i
E2 I 23 17, 4/01/84 173 1 2D 21, 4/08/84 174 I 2I 17, 4/01/84 175 I 38 21, 4/08/84
, 176 I 23 17, 4/01/84 177 I 2D 17, 4/01/84 178 I 2D 17, 4/01/84 179 I 2D 16, 3/31/84 180 I 2A 17, 4/01/84 181 I 2F 17, 4/01/84 s 182 I 2D 17, 4/01/84 133 % 2D 18, a/02'84 O,
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PROBLEM SHEET LISTING i ITEM NUMBER RITIEVED IT IFD FRIORITY BRISI0tt, DATE
~~
184 I 2D 16, 3/31/84 185 I 2B 18, 4/02/84 186 I N/A (Rasolved) 18, 4/02/84 i
187 I 2C 18, 4/02/84 i 188 I 33 (Resolved) 15, 3/29/84 189 I 25 18, 4/02/84 i 190 I 2D 20, 4/06/84 191 I 2D 18, 4/02/84 192 I 2D 16, 3/31/84 193 I 2D 16, 3/31/84 194 I 2D 18, 4/02/84 195 I 3A 18, 4/02/84 l 196 I 23 16, 3/31/84 197 I 3A _
21, 4/08/84 198 I IC 16, 3/31/84 i 199 I 3B 13, 4/02/84 i 200 I 2G 18, 4/02/84 i p 201 1 2B 22, 4/09/84 202 I 3B 18, 4/02/84 203 I 2D 22, 4/09/84 I '204 1 2B 18, 4/02/84 l
205 I 25 16, 3/31/84 206 I 2G 16, 3/31/84 207 I 2H 18, 4/02/84 208 I 2B
- 18, 4/02/84 209 I 2H 15, 3/29/84
~
210 2 2G 18, 4/02/84 211 I 2B 18, 4/02/84
! 212 I 2D 18, 4/02/84
, 213 I IC 16, 3/31/84 i
l 214 1 35 21, 4/08/84 215 I 35 16, 3/31/84 216 I 35 18, 4/02/84 217 1 3B 21, 4/08/84 218 I 3A 21, 4/08/84 g 219 I 2I 16, 3/31/84 l 220 I 3A 18, 4/02/84 i
L26sd6 i
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FBOBLEM SHEET LISTING i
ITEM NtMBER REVIEVE BY RFD FRIORITY IZYISION. DATE
~~
221 I 2D 16, 3/31/84 222 I 3B 16. 3/31/84 223 I 2B 18, 4/02/84
- 224 I 35 16, 3/31/84 l 225 1 2D 20. 4/06/84 226 I 34 18. 4/02/84 227 I 3B 21, 4/08/84 j 228 I 33 17, 4/01/84 '
! 229 I 25 21, 4/08/84 l l 230 1 2B (Resolved) 15, 3/29/84 l I 231 I 35 17, 4/01/84 232 I 38 17, 4/01/84 233 I IB 20, 4/06/84 l 234 I 3A 18, 4/02/84 235 I 2B 18, 4/02/84 4
=
236 I 25 17, 4/01/84 j 237 I 2D 18, 4/02/84 l p 238 I 2D 18. 4/02/84 l 239 I 2D 18. 4/02/64 240 I 2D 17. 4/01/84 l 241 I 2D 17, 4/01/84 242 1 3B 18. 4/02/84 f 243 1 3B 18. 4/02/84 244 1 2B 18, 4/02/84 245 1 25 17, 4/01/84
] 246 I 2B 18. 4/02/84 247 I 2B 18, 4/02/84 l
248 I 2D 18, 4/02/84 249 I 2D 22. 4/09/84 250 1 2B 18, 4/02/84 251 1 27 18. 4/02/84
. 252 I *3B 18, 4/02/84 l ,,
! 253 1 2C 18. 4/02/84 254 I 35 18, 4/02/84 l g
- Priority changed from 1A per J. C. Roberts 3/27/84 f
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FROBLZM SHEET LISTING ITIM NUMBER BZYIEVED BT RFD FRIORITY RETISION, DATE 255 I 2E 18, 4/02/84 D. ' 256 I 2E 18, 4/02/84 i
, 256-1 I Sub, 2E 18, 4/02/84 ;
257 I 2B 17, 4/01/84 !
258 I 35 18, 4/02/84 259 2 23 18, 4/02/84 260 I 3B 18, 4/02/84 l 261 I 3A 18, 4/02/84 I- 262 I IC 16, 3/31/84 263 I ZD 17, 4/01/84 264 I 25 17, 4/01/84 265 I 2D 18, 4/02/84 266 I 2B 17, 4/01/84 267 I 2B 18, 4/02/84
, , 268 I 2F 18, 4/02/84 269 I 2D 18, 4/02/84 270 1 2E 22, 4/09/84 l p 271 I 2B 18, 4/02/84 l 272 I 2D 22, 4/09/84 l 273 I 2B 18, 4/02/84 274 I 2D 18, 4/02/84 i 275 I 25 18, 4/02/84 276 I 2D 18, 4/02/84 277 I 2B 18, 4/02/84 278 I 2D 18, 4/02/84 279 I 2D 17, 4/01/84 l 280 I 2D 18, 4/02/84 l 281 I 2E 18, 4/02/84 282 I 2E 17, 4/01/84 283 I 2E 17, 4/01/84 e 284 I 2B 18, 4/02/84 285 I IC 18, 4/02/84 l 286 I 2D 18, 4/02/84 l
287 I 2D 18, 4/02/84 l 288 I 2D 18, 4/02/84 A 289 I 2E 18, 4/02/84 s 290 I 2E 18, 4/02/84 L26ed8 ee .
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PBDBLEM SHEEI LISTIBC
- - ITEM ltUMBER REVIIVE BY RFD FRIORITT REVISI0tt, DATE
'~'
291 1 *3B 18, 4/02/84 292 I 13 18, 4/02/84 293 I IB 18, 4/02/84
- 294 I 2B 18, 4/02/84 295 I 2E 18, 4/02/84 296 I 21 18, 4/02/84 297 I 23 18, 4/02/84 298 I 2E 18, 4/02/84 l
i- 299 I 2B 18, 4/02/84 300 1 3A 18, 4/02/84 i 301 I 2E 18, 4/02/84 i 302 I 2D 18, 4/02/84 i 303 1 2B 18, 4/02/84 304 I 2D 21, 4/08/84 305 I 2I 18, 4/02/84 1 306 I 1B 18, 4/02/84 307 I 2B 18, 4/02/84
{ p 308 I 15 18, 4/02/84 l 309 I 2A 18, 4/02/84 310 I 2A 18, 4/02/84 311 1 2E 18, 4/02/84
'l 312 I 25 22, 4/09/84 l, 313 I 25 18, 4/02/84.
314 I 23 18, 4/02/84 j 315 I 2B 18, 4/02/84 I
316 1 25 18, 4/02/84 317 1 2E 18, 4/02/84 318 I 35 18, 4/02/84 i 319 I 2E 21, 4/08/84 320 I 21 18, 4/02/84 321 I 2B 18, 4/02/84 322 I 21 18, 4/02/84 l 323 1 23 18, 4/02/84
!- 324 I 2E 18, 4/02/84
! 325 1 2I 18, 4/02/84
-'
- Petoriev chansed from 1A per J. C. Roberts 3/27/84.
L26ed9
. , . . .: . . . . . , , . . . 9- . . _ .
l PkOBLEM SHEET LISTING ITEM NUMBER REVIEWED BT RFD PRIORITY REVISION, DATE 7 '
O 326 327 I
I 2I 3B 18, 4/02/84 18, 4/02/84
- 328 I 38 18, 4/02/84 .
329 I IC 18, 4/02/84 330 I 2B 18, 4/02/84 l
331 1 2B 18, 4/02/84
{ 332 I 3B *21, 4/08/84 333 I 25 18, 4/02/84 i 334 I 2D 18, 4/02/84 335 I 2B 18, 4/02/84 336 I 2D 18, 4/02/84 337 I 2D 18, 4/02/84 .
j 338 I 2B 18, 4/02/84 l 18, 4/02/84 339 I 2I 340 I 2I 18, 4/02/84 341 1 3B 18, 4/02/84 342 I 2B 19, 4/05/84 Q 4 I I':5I 9 4/
21, 4/08/84 4 345 I 25 1
i 346 I 2B 23, 4/10/84 347 I 28 21, 4/08/84 348 I 2E 21, 4/08/84 349 I 2D 21, 4/08/84
- 350 I 2B 21, 4/08/84 j 351 I 2D 21, 4/08/84 l 352 I 2D 21, 4/08/84
- 353 I 2D 21, 4/08/84 354 I 2D 21, 4/08/84 355 I 2D 21, 4/08/84 l
! 356 1 2D 21, 4/08/84 357 I 28 21, 4/08/84 358 I 2D 21, 4/08/84 359 I 25 21, 4/08/84 360 I 25 21, 4/08/84 361 I 2D 21, 4/08/84 f s i 362 1 2D 21, 4/08/84 363 1 2D 21, 4/08/84 L26sd10 1 ~,. . _ _ ..,. _ - = . _ . - .. .
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE i
. l 364 X 2B 21, 4/08/84 800 X 38 18, 4/02/84 801 X 3B 18, 4/02/84 802 X 38 18, 4/02/84 803 X 3B 18, 4/02/84 804 X 35 18, 4/02/84 805 I 3B 18, 4/02/84 806 I 3B 18, 4/02/84 807 X 38 18, 4/02/84 808 I 3B 18, 4/02/84 809 X 3B 18, 4/02/84 810 X 38 18, 4/02/84 811 X 3B 18, 4/02/84 812 X 3B 23, 4/10/84 813 x 3B 22, 4/09/84 0 814 815 X
X 35 3B 22, 4/09/84 22, 4/09/84 816 X 35 23, 4/10/84 817 I 3B 23, 4/10/84 818 I 35 23, 4/10/84 819 x 3B 23, 4/10/84 820 X 38 23, 4/10/84 1
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4 TECHNICAL SPECITICATION FROBLEM SHEET Item Number: 346 Priority: 2B i Looper /4/5/84 5 Identified By Date Responsible Supervisor I j Tech Spec
Reference:
3.3.7.8 Tech Spec Page: 3/4 3-75 Problem
Title:
Chlorine Detection System
f Technical Specification 3.3.7.8 requires two independent chlorine detection j systems to be operable in all Operational Conditions. The GCNS design for the
) chlorine detection system includes a sensor with output contacts providing i
- signals to the control roca emergency filtration system isolation logic. The specification should be revised to replace " chlorine detection systems" with j " chlorine detection channels" for consistency with the GCNS instrumentation definitions. ;
1 ,
Action Statements (a) and (b) require at least one control room emergency filtration system subsystem to be operating in the isolation mode when there i are inoperable chlorine detection channel (s). The Action Statements should require that the control room emergency filtration subsystem which is 1 associated with the Control Room HVAC subsystem that is in operation be i initiated and maintained in the isolation mode of operation..
l 2. Safety Significance:
1 j None. Replacing " systems" with " channels" for the chlorine detection j instrumentation is for clarification of terminology and does not affect compliance with the intent of the Technical Specification.
i None. This is an enhancement ites for operations. As presently worded,
, Action Statements (a) and (b) would permit initiating and maintaining the ,
control room emergency filtration subsystem which is associated with the
~
control room ETAC subsystem that is not in operation in the isolation mode.
3 The operating control roca RVAC subsystem in this event would only be i recirculating air through its normal filter and would not be circulating air 1 '
4 1
Rev. 23, 4/10/s4 I l l
i
! P 1sd 2I.9. 6 i
I i
J v . . -.% 4..-- ,. _ , . . .
--.-,,-,.--,,...--,---...-,----,.-,-.n
_ , . ~ - . . - _ . , , , - . - - - - - . ,,-,,-.,,.--n.~.,_,-. . , ~ - . . , - - . - . - n -- ~~ .
~
, Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 346 'Prioriry: 2B
. through the filters of the emergency filtration subsystem. This is not a concern for an outside accidental chlorine release since the common intake for both control roca HVAC subsystems would be isolated. !
- 3. Anticipated Resolution:
Ivaluate the necessity of changing Technical Specification 3.3.7.8 to provide the proper terminology and provide consistency with the GCNS instrumentation channel definitions.
Evaluate Action Statements (a) and (b) with respect to the design intent of the control room emergency filtration subsystems and their associated chlorine detection channels. Propose appropriate Technical Specification changes as necessary. -
- 4. NRC Response to Ites (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Itess Closed (How)
/
Date Time cct J. E. Cross R. F. Rogers
Rev. 23, 4/10/84 P1sd49.7
-- . .-. . . . - - - _ . . - - - . _ - . . - ~ - - - . _ - - - _ _ . . - . - _ . - -
h TECHNICAL SPECIFICATION PROBLEM SHIET j Iten Number: 812 Priority: 38 l
Identified By Data Responsible Supervisor j Tech Spec
Reference:
Table 3.3.2-1. Itea 5.h: YEAR Yinure 7.6-17
} FSAR Section 7.3.1 Tech Spec Page: 3/4 3-12; FSAR tF p,7.3-29 Probles
Title:
FSAR/ Main Steam Tunnel Temperature Timer l
l Technical Specification Table 3.3.2-1 Item 5.h identifies a " Main Steam Line l Tunnel Temperature Timer", whose function is to delay RCIC isolation for 30 I minutes (to allow the operator time to establish an alternate means of Reactor f Vessel Level Control.) A timer is identified in FSAR Figure 7.6-17 for the j Leak Detection System, but is not included in the discussion on Main Steam 1
] Line Leak Detection presented in FSAR Section 7.3.1.1.2.4.1.3.
l l
- 2. Safety Significance
Not Applicable.
- 3. Anticipated Resolutions j Evaluate the need to revise FSAR Section 7.3.1 to include a discussion of the i
Main Steen Line Tunnel Temperature Timer and if necessary, include appropriate -
changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
t
) 4. NRC Response to Ites (NRR/IE):
I NRC Notified: /
i l Individual Notified Date Time 1
)
i I
i I
! l Rev. 23, 4/10/84 {
l 71sd292 l
i j + .- 8- + + - - . . - ,. -+ - . - -
- - , - - , - - , --....,n_----,-, , ,n,-----.-.. - ~ ., . . - , . - - - - - , . - - - - , - - - . - - - - -
f - ..
l i
i 1
i
- . 'Page 2 TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D)
I Item Number: 812 Priority: 35 i
!, 5. Dispositions Items Closed: (How)
/
Date Time l
.f
Reference:
INTEL, item 3B I
cc: J. E. Cross t
i R. F. Rogers i
i i
i
)
i i
lP Rev. 23, 4/10/s4
) Plad293
~w - - . . ~ . .
.-r-,n,,,--.. - - - - . - - - , , , . . - - . - - - - - - - . - _ . . . . , , - - - - , - - - . - - , , , - - - , - - - - , . - . - - , . .
TECHNICAL SPECITICATION PROBLEM SHEET O Item Number: 816 Priority: 3B
. /
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.2-2; TSAR Table 7.3-10 Tech Spec Page: 3/4 3-15; FSAR Table 7.3-10 Problem
Title:
FSAR/ Main Steam Line Flow-High Instrumentation
TSAR Table 7.3-10 contains specifications for the containment and reactor vessel isolation control instrumentation. The maximum allowable setpoint for the main steam line flow-high instrumentation is given as 133.5 paid. The ,
trip setpoint for this instrumentation in Technical Specification Table 3.3.2-2 is 169 psid. A 169 paid signal corresponds to a main steam line flow of 140% which is the value used in the FSAR analysis for a main steam line break.
The range for the main steam line flow-high instrument given in FSAR Table 7.3-10 is -15/0/150 paid. As discussed above, a trip setpoint of 169 psid would necessitate revising this instrument range to accomodate the setpoint.
FSAR Table 7.3-10 should be revised to correct the main steam line flow-high instrumentation valves.
- 2. Safety Significance:
Not Applicable.
- 3. Anticipated Resolution:
Revise FSAR Table 7.3-10 to correct the main steam line flow-high instrumentation valves in the next autual FSAR update per 10 CFR 50.71(e)(4).
1
! 4. NRC Response to Ites (NRR/IE):
f NRC Notified: /
! Individual Notified Date Time 1
I Rev. 23, 4/10/84 Plsd298 s.--_. -.--~.
- . _ - - - - - - - - - . - - - - - - . - ~ . . -- - - - - - , - - - - .-- - - - - , --.
^~
, ~,.
l l
l P 2 .
i l
TECHNICAL SPECIFICATION PROBLEM SEEET (CONT'D) l t
i l
! Item Number: 816 Priority: 3B i
i
- 5. Disposition:
1 Items Closed (How) i .
j
/
Date Time l 4
) cc: J. E. Cross !
i R. F. Rogers i
I l
1 i
t 1
1 i
j 1
I i ,- ,
4
~
Ray, 23, 4/10/84 1
i
- Pisd299 i
+
[
TECHNICAL SPECIFICATION PROBLEM SHEET Iten Number: 817 Friority: 3B i
. / ;
Identified By Date Responsible Supervisor Tech Spec
Reference:
N/A: TSAR Section 6.2.3.2 Tech Spec Page: N/A; FSAR Pages 6.2-52, 6.2-52a Probles
Title:
FSAR/ Standby Gas Treatment System Design Criteria
FSAR Section 6.2.3.2 needs to be revised to indicate that the Standby Gas Treatment System (SGTS) has sufficient capacity to overcome the additional ,
inleakage (i.e., maintain secondary containment negative pressure) from a single 4 inch line penetration or failure of all non-Q lines 2 inches and smaller.
- 2. Safety Significance:
Not applicable.
( ,
- 3. Anticipated Resolution:
O Evaluate FSAR Section 6.2.3.2 with respect to the need for indicating the capacity criterion of the SGTS and, if necessary, include appropriate changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE): .
NRC Notified: /
Individual Notified Date Time
- 5. Disposition
, Items Closed (How) i i
/ ,
Date Ties
! cc: J. E. Cross ,
i i I,', R. F. Rogers l
Rev. 23, 4/10/84 Fled 300 l f
i i
! 4 l
l eS.
u_,.__._._.-__._.._ _ . _ _ _ . _ . . _ . _ . _ _ _ . _ _ . _ _ _ _ . _ . _ . - _ _ _ . . _ . _
^
(
t i
i -
TECHNICAL SPECITICATION FROBI.IM SHEET
- O l _
Item Number: 818 Priority: 35 l l . /
1 l Identified By Date Responsible Supervisor l
- Tech Spec
Reference:
N/A: TSAR Section 6.2.3.2 l Tech Spec Page N/A; FSAR 6.2-50 throush 53a Frobles
Title:
FSAR/ Secondary Containment Isolation i 1. Probles Description (Tech Spec, FSAR SER, GE Design, Other):
, rupture discs are also used to italste secondary containment.
i
- 2. Safety Significance
j
=
Not applicable.
i
- 3. Anticipated Resolution: .
t Evaluate FSAR Section 6.2.3.2 with respect to the need for indicating that !
,. blind flanges and rupture discs are also used to isolate secondary containment i
'I and, if necessary, include appropriate changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
}
- 4. NRC Response to Item (NRR/IR):
l NRC Notified: /
i l Individual Notified Date Tian i
i 5. Disposition: i j Items Closed: (How) i 1
l l Date Time i
l cc: J. R. Cross
{ R. F. Rogers l '
l Rev. 23, 4/10/84 F1sd301
- . - ,~,_ - - - _ _ - - _ , - _ . . . _ _ _ . . - _ . . . . . . , , - . . , . _ _ . . . . . . _ . _ _ . _ - . _ . . - . . . _ . _ _ . . - . - - - - - - . _ _ - . _ , , , - - - . . ._
r I- TECHNICAL SPECITICATION PROBLEM SHEET O Item Number: 819 Priority: 3B
. /
Identified By Date Responsible Supervisor Tech Spec Esference: N/A; TSAR Table 3.7-17 Tech Spec Page: N/A; FSAR Table 3.7-17 Problem
Title:
FSAR/ Seismic Instrumentation Nomenclaure
FSAR Section 3.7 describes the seismic design and seismic monitoring for GGNS.
Section 3.7.4.2 discusses the location and description of seismic monitoring instrumentation, which is consolidated in Table 3.7-17. The response spectrum analyzer identified in Section 3.7.4.2.5 is incorrectly labeled in Table 3.7-17 as a " Triaxial Response Spectrum Recorder."
- 2. Safety Significance: l Not applicable.
- 3. Anticipated Resolution:
Evaluate the need to relabel the response spectrum analyser in Table 3.7-17 and, if necessary, include the appropriate changes in the next annual FSAR update per 10 CTR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time cc J. E. Cross l
/ R. F. Rogers Rev. 23, 4/10/84 I Fled 302 1
l
- _ - _ , . _ , . . , . _ _ _ . . - - _ - _ . _ . ____,.___.-...___.-e,- . . _ _ . . - - _ . _ . _ ..-.,._,,_._. . . . _ _ . _ . _ , . . . . _ _ , . _- . , _ . . . - - - - _ . -
i . :
! TECHNICAL SPECITICATION FROBLEM SHEET Item Number: 820 Priority: 3B
. /
Identified By Data Baaponsible Supervisor Tech Spec
Reference:
Table 3.3.2-2 Table 3.3.5-2; TSAR Table 7.4-1 Tech Spec Page: 3/4 3-17, 3/4 3-47; FSAR Table 7.4-1 Problem
Title:
FSAR/RCIC Instrument Specifications
FSAR Table 7.4-1 lists the Reactor Core Isolation Cooling instrument specifications. The values provided in this FSAR table are not consistent with the associated instrument specifications in the GGNS Technical l Specifications.
The following inconsistencies have been identified between the FSAR Table l
7.4-1 and Technical Specif ication Table 3.3.2-2:
Function FSAR Value GGNS-TS Value i ,. a) RCIC system steam supply greater than or equal i
low pressure 65 peig to' 60 pois b) RCIC turbine exhaust less than or equal to high pressure 25 peig 10 psig 4
The following inconsistencies have been identified between the FSAR Table 7.4-1 and Technical Specification Table 3.3.5-2:
Function FSAR Value GCNS-TS Value a) reactor vessel low water less than or equal greater than or equal level to -41.8" to -41.6" b) reactor vessel high water greater than or equal less than or equal to level to 54.9" 53.5" l l
c) condensate storage tank. l'2" greater than or equal to 0" level d) suppression pool level 5" less than or equal to 5.9"
~
l
,t Rev. 23, 4/10/84 l
F1sd303
- _. - - - . . - -_, .~.
.. .~
s Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Ites Number: 820 Priority: 3B
- 2. Safety Significance:
l Not applicable.
- 3. Anticipated Resolution:
Evaluate the RCIC instrument specifications in FSAR Table 7.4-1 to determine the correct values. Revise the table as necessary following this review and include the appropriate changes in the next annual FSAR update per 10 CFR 50.17(e)(4).
- 4. NRC Response to kten (NRR/IE):
NRC Notified: /
, Individual Notified Date Time
- 5. Disposition:
l Items Closed (Hov)
/
Date Time tct J. E. Cross R. F. Rogers ,
I w Rev. 23, 4/10/84
( Plad304 l
l eum l
e -
l . P 1
" TECH SPEC PRIORITY" MEMO TO: Tech Spec Review Personnel FROM: C. L. Tyrone
SUBJECT:
Rev. dA to Technical Specification Problem Sheet TSRT: 84/ Q) h h O DATE: b R sh. W9A The following changes / additions are te be incorporated into the Tech Spec Problem Sheets:
ITEM NUMBER CHN'GES/ ADDITION
'b\A h e.nE\ Remove Rev. . Insert Rev. A 4
'W
%\e W Remove Rev. . Insert Rev. A g ANA Remove Rev.-- , Insert Rev. gg Au6 Remove Rev. , Insert Rev. g g S so 4 (g Remove Rev. , Insert Rev. p b%D Remove Rev. ~. Insert Rev. % 4 b S \ lACAO Remove Rev.- . Insert Rev. AN 6 O A (';LQ Remove Rev.gg Insert Rev. g 4 t
l 6 %\ (A Remove Rev. , Insert Rev. g g B 'AB b Remove Rev.~, Insert Rev. @q 8 AS (A Remove Rev. . Insert Rev. A N bAA Remove Rev. ~ Insert Rev. 1 4 tb M (h] Remove Rev. . Insert Rev. q q
' s A
C. L. Tyrone i
CLT: sad Attachment cct S. H. Hobbs (w/1)
File (Tech Spec Ra' cords) (w/1) ,,
M2sd1
~~,. -
TSRT-84/0 9 A O O PROBLDi SHIET LISTING AS OF b', } l11929 Data' ITEM NUMBER REVIEWED BT RPD PRIORITT RIVISION, DATE o
001 I 1B 15, 3/29/84 002 I 2E 15, 3/29/84 003 I 2D 17, 4/01/84 004 I 2E 22, 4/09/84 ,
005 I 1B 15, 3/29/84 !.
l I 21, 4/08/84 006 I 2D 007 I 2F 15, 3/29/84 ,
008 I 2H 17, 4/01/84 ,
009 I 2D 17, 4/01/84
!i 010 I 2B 15, 3/29/84 t
! 011 I 2B 15, 3/29/84 012 I 2D 18, 4/02/84
!* 013 I 3A 21, 4/08/84
! 014 I 2B 21, 4/08/84
! 015 I 1B 17, 4/01/84 j O. . 016 I 1B 15, 3/29/54 15, 3/29/84 017 I 2D 018 I 33 15, 3/29/84 l
019 I 25 15, 3/29/84 020 I 2B 17, 4/01/84
! 021 I 1C 15, 3/29/84 022 I 2A 17, 4/01/84 023 I 2B 15, 3/29/84 024 I 25 18, 4/02/84 1'
025 I 2D 17, 4/01/84 026 I ZD 15, 3/29/84 027 I 2E 15, 3/29/84 l ;
028 I 2B 15, 3/29/84 ,
I 029 I 35 17, 4/01/84 030 I ZD 17, 4/01/84 1
031 I 2D 17, 4/01/84 l
032 I 23 21, 4/08/84
)
033 I 15 18, 4/02/84 034 I IC 18, 4/02/84
- 035 1 2C 15, 3/29/84
! 1,26sd L
- - - . . - . .- . . . i . . - . . . - .. .,,
1
l . . .
FROBLIM SIZZ LISTING 1
RZYIIVED BY IFD PRIORITT RE7ISION, DATE 6
IT1M NCNBER 036 I 2E - 20, 4/06/84
~
i 037 I 1C 15, 3/29/84 038 I IC 15,-3/29/84 039 I 2C 17, 4/01/84 040 1 27 17, 4/01/84 041 I 23 21, 4/08/84 042 I 23 15, 3/29/84 043 1 2D 15, 3/29/84 044 I 33 17, 4/01/84 045 -
I 23 17, 4/01/84 046 I 2F 15, 3/29/84 l
047 I 13 15, 3/29/84 048 1 25 15, 3/29/84 049 I 23 18, 4/02/84 i 050 1 23 17, 4/01/84
! 051 1 2D 15, 3/29/84 052 1 21 15, 3/29/84 i
. 053 I 2E 17, 4/01/84
- , 054 I 13 21, 4/08/84 055 I 2D 15, 3/29/84 056 I 33 21, 4/08/84 057 I 23 17, 4/01/84 I 058 I 2D ' 17, 4/01/84 059 I ZD 17, 4/01/84 060 I 23 15, 3/29/84 t
061 I 2D 15, 3/29/84 l
i 062 I 2E 18, 4/02/84 j 063 I 2E 17, 4/01/84 064 I 22 15, 3/29/84
! 065 I 2E 15, 3/29/84 066 2 2D 22, 4/09/84
' 15, 3/29/84 067 I 2D I 33 15, 3/29/84 '
! 068
! 069 I 21 17, 4/01/84 070 I 33 18, &/02/84 l
1 3 23 17, A/01/Sa 071 j g 2 23 17, 4/01/84 L26ed2 l ,,
!_.__.__.__________..,-____._.__._,-~, .____.. _ . _.__._-.__..., _.-__ _ __-..__ ._ _ . . _ _ _ _ _ _ _ . - _ - _ . - - -
1103LEM SHIZI LISTING IIEM NDCBER RE7II'JED BT 11"? PRICRITT II7ISICN, DAIZ 073 I 23 12, 4/02/84 074 I 17,' 4/01/34
_ __ 2D _
075 1 23 17r 4/01/84 y,
. 076 I 13- ___
18, 4/02/84 077 I 23 21, 4/08/64 078 I 13 15, 3/29/94 079 I 2E 15, 3/29/84 080 I N/A (Lsolved) 15, 3/29/t4
. 081 I 3A 15, 3/29/84 082 I 3A 15, 3/29/84 023 I 23 22, 4/09/84 084 I 3A 15, 3/29/84 085 I 2D 20, 4/06/84 086 I 2D 18, 4/02/84 087 I 2D 17, 4/01/84
~~
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~ '
096 'I 22 15, 3/29/84 097 I 2E 15, 3/29/84 098 I 2c 15, 3/29/84 099 I 20 21, 4/08/84 100 I 33 Ig, 4/02/g4 101 I- 2E 15, 3/20/84 102 I 23 15, 3/29/84 103 1 13 18, 4/02/84
- 104 I 2E 17, 4/01/84 .
f-105 I 22 15, 3/29/84 106 I 2E 18, 4/02/84 107 I 2E 18, 4/02/84 9 2D / 9/
L26sd3
. 5 N E
Ptott.IM SEZEI LI3fING .
I m NUMBER RE7IIWID 3T IFD PR201ITT RITISION, DAIX j 110 1 23 17, 4/01/84 111 2 2D 18, 4/02/84
'e 112 1 2A 15, $29/84 113 I N/A (laselved) 15, 3/29/84 114 I 23 18, 4/02/84 115 1 2D 17, A/01/84 116 I 23 15, 3/29/84 117 I N/A (Resolved) 18, 4/02/84 118 I 2D 16, 3/31/84 119 I 25 15, 3/29/84 120 I ZD 18, 4/02/84 121 I N/A (Rasolvedi 15, 3/29/84 122 I 2D 17, 4/01/84 123 I ZD 18, 4/02/84 124 I 2C 18, A/02/84 125 I N/A (Easolved) 18, 4/02/84 126 I . 2D 15, 3/29/84 y 127 I 2C 17, 4/01/84 128 I 2D ;_. 17, 4/01/84
{ .
129 I 23 15, 3/29/84 130 _
I N/A (Rasolved) 15, 3/29/84 ,
131 2 2C 15, 3/29/84 132 I 23 15, 3/29/84 ,
133 I 2D 18, 4/02/84 134 I ZD 17, 4/01/84 135 I N/A (laselved) 18, 4/02/94 136 I 2D 15, 3/29/84 ,
137 I 23 15, 3/29/84 138 I 2D 15, 3/29/SA 139 I IC 15, 3 /29 /Q 140 I 2D 18, 4/02/8s
' ' 17, A/01/84 141 I 2F 142 I 27 15, 3/29/54 143 I 2C 15, 3/29/8A I 23 15, 3/29/8' 1&&
27 17, 4/01/34 I'3 I t 15, 3129134 l's I lI L26sda
l i
Ftc8L2X SEIIT LISTDC l .
ITIM NtM8II IZ7TDTID IT IFD FRIORITT RITIS2CN, DATI 147 I 33 16, 3/31/84 148 I 1A 17, 4/01/84
'" 149 I 33 18, 4/02/84 r .
150 I 2G 17, 4/01/84 151 I 3B _
17, 4/01/84 152 I 21 16, 3/31/84 r 153 I ZH 17, 4/01/84 16, 3/31/84 154 I 2D (
155 I :D 18, 4/02/84 156 -
I ZD 17, &/01/84 157 1 2D 17, 4/01/84 158 I 2D 17, 4/01/84 159 I ZD 16, 3/31/84 160 1 21 21, 4/08/84 161 I 21 18, 4/02/84 162 I 2D 16, 3/31/84 163 I 2D 16, 3/31/84 4 164 1 23 18, 4/02/84
- 17, 4/01/84 165 I 2D 166 I 33 17, 4/01/84 167 I 3 17, 4/01/84 168 1 23 21, 4/08/84 169 I - 2D 18, 4/02/84 170 I 21 16, 3/31/84 171 I 2D 16, 3/31/84 172 I 23 17, 4/01/84 173 1 2D 21, 4/08/84 174 2 21 17, 4/01/84 175 I 33 21, 4/08/84
, 176 I 23 17, 4/01/84 177 I 2D 17, A/01/84 I 2D 17, 4/01/84 178 25 16, 3/31/84 179 I 180 I 2A 17, 4/01/84 2? 17, 4/01/94 181 I I *D 17, 4/01/34 g 182 .
!!3 I :D 18. A!02/S4 L25sd5 ,
l
- - - - - - - - - - . , + . , - ,- - -,-
- -- :--~-- . . .
~
PROBLIM SHEZ: LISTING ITE( NtT!(BZ1 RIVI!v D BY RFD FRIORITT RETISION, D4TI 184 I ZD 16, 3/31/84 l l
185 I 23 18, 4/02/84 '
e 186 I N/A (Rasolved) 18,*4/02/84 187 I 2G 18, 4/02/84 188 I 35 (Resolved) 15, 3/29/84 189 I 2B 18, 4/02/84 190 I 2D 20, 4/06/84 191 I ZD 18, 4/02/84 192 I 2D 16, 3/31/84
! 193 I 2D 16, 3/31/84 194 1 2D 18, 4/02/84 195 I 3A 18, 4/02/84 196 I 23 16, 3/31/84 197 I 3A _
21, 4/08/84 198 I IC 16, 3/31/84 199 I 3B 18, 4/02/84 200 I 2G 18, 4/02/84
. ,, 201 I 2B 22, 4/09/84
), 202 I 3B 18, 4/02/64 203 I 2D 22, 4/09/84 204 I 2B 18, 4/02/84 205 I 25 16, 3/31/84 206 I 2G 16, 3/31/84 207 I 2B 18, 4/02/84 208 I 2E 18, 4/02/84 t
209 I 25 15, 3/29/84 210 I 2G 18, 4/02/84 211 I 23 18, 4/02/84 212 I 2D 18, 4/02/84 213 I IC 16, 3/31/S4 214 I 33 21, 4/08/84 215 I 33 16, 3/31/84 216 I 33 18, 4/02/84 217 I 33 21, 4/08/84 218 I 3A 21, 4/08/84 g 219 I 2:
16, 3/31/84 220 I 3A 18, 4/02/84 L26sd6 ,
l
F303 LIE SEZZT LISTING ITIM NUMBER XZVIZL'D BT IFD P1.IORITT RZ71SION, DATE 221 I 2D 16, 3/31/84 l
l 222 I 33 16. 3/31/84 l ,
223 I 23 18. 4/02/84 224 I 33 16, 3/31/34 225 I 2D 20, 4/06/84 226 I 3A 18, 4/02/84 227 I 33 21, 4/08/84 228 I 33 17, 4/01/84 229 I 23 21, 4/08/84 I
230 1 23 (Resolved) 15, 3/29/84 l 231 I 33 17, 4/01/84 232 I 33 17, 4/01/84 233 I 13 20, 4/06/84 l 23'A I 3A 18, 4/02/84 l 235 I 23 18, 4/02/84 l 236 I 23 17, 4/01/84 237 I 2D 15, 4/02/84 4 238 I 2D 18, 4/02/84 239 I 2D 18, 4/02/84 240 I 2D 17, 4/01/84 241 I 2D 17, 4/01/84 242 I 33 18, 4/02/84 243 _I 33 18, A/02/84 2&& I 23 18, 4/02/84 245 I 23 17, 4/01/84 246 I 23 18, 4/02/84 247 I 23 18, A/02/84 248 I 2D 18, 4/02/84 249 I 2D 22, 4/09/84 250 I 23 18, 4/02/84 251 I 2F 18, 4/02/84 252 I *33 18, 4/02/84 ,,
253 I 2C 18, 4/02/84 I 254 I 33 18, 4/02/84_
g
- P;teriev changed from 1A per J. C. Roberts 3/27/84.'
L26sd7 l
a . . . - . . .._ , , - . - ._ _ _~ - ____-.w __-
~
FROBLEM SHEE2 LISTING ITEM NUMBER RETII'JD BT RFD FRIORITT REVISION, DATE 255 1 21 18, 4/02/84 .
~
256 I 21 18, 4/02/84
, 256-1 I Sub, 2E 18. 4/02/84 257 I 23 17, 4/01/84 258 I 33 18, 4/02/84 18, 4/02/84 1 259 I 23 260 I 33 18, 4/02/84 261 1 34 18, 4/02/84 262 I IC 16, 3/31/84 263 I 2D 17, 4/01/84 264 I 23 17, 4/01/84 I 2D 18, 4/02/84 265 266 I 23 17, 4/01/84 267 I 23 18, 4/02/84 268 I 27 18, 4/02/84 1 2D 18, 4/02/84 269 270 I 2E 22, 4/09/84 271 I 2B 18, 4/02/84 .
4 272 I 2D - 22, 4/09/84 273 I 23 18, 4/02/84 274 I 2D 18, 4/02/84 275 I 13 18, 4/02/84 276 I 2D 18, 4/02/84 277 I 23 18, 4/02/84 278 I 2D 18, 4/02/84 279 I 2D 17, 4/01/84 280 I 2D 18, 4/02/84 281 1 2E 18, 4/02/84 282 I 2E 17, 4/01/84 283 I 23 17, 4/01/84 I 23 18, 4/02/84 e 284 1 1C 18, 4/02/84 285 286 I 2D 18, 4/02/84 -
287 I 2D 18, 4/02/84 I 2D 18, 4/02/84 288 I 2E 18, 4/02/84
% 289 I 2E 18, 4/02/84-290 L26sd8 ,,
. . --- . - . .~ _ . . . , , .
P30BLDi SHIIT LISTING
- ITIM NUMBER RE7IEiTED ST IPD PRIORITT RI7ISION, D4TI 291 I *33 18, 4/02/84 292 I 13 18, 4/02/84
,, 293 I 13 18 -4/02/84 294 I 23 18, 4/02/84 295 I 2E 18, 4/02/84 296 I 2Z 18, 4/02/84 ,
297 I 23 18, 4/02/84 298 I 2E 18, 4/02/84 299 I 23 18, 4/02/84 300 I 3A 18,'4/02/84 301 I 2E 18, 4/02/84 302 I ZD 18, 4/02/84 303 I 23 18, 4/02/84 304 I 2D 21, 4/08/84 305 I 21 18, 4/02/84 306 I 13 18, 4/02/84 307 I 23 18, 4/02/84 ar 308 I 13 18, 4/02/84
[,
- 309 I 2A 18, 4/02/84 310 I 24 18, A/02/84 311 I 2E 18, 4/02/84 312 I 23 22, 4/09/84 313 I 23 18, 4/02/84. , ,_
314 I 23 18, 4/02/84 315 I 23 18, 4/02/84 316 I 23 18, 4/02/84 317 I 2I 18, 4/02/84 318 I 33 18, 4/02/84 319 I 2E 21, 4/08/84 320 I 2Z 18, 4/02/84 321 I 13 18, 4/02/84 322 I 2E 18, 4/02/84 323 I 23 18, 4/02/84 324 I 2E 18, 4/02/84 325 I 2I 18. a/02/84
- Priertev changed frem 1A ser J. C. Rober s 3/27/84 L26sd9 l
l PROBLEM SHIET LISTING REVISION, DATE ITEM NUMBER REVII'JED BT RFD PRIORITT 2I 18, 4/02/84 326 I .
3B 18, 4/02/84 327 I' 3B 18, 4/.02/84 328 I IC 18, 4/02/84 329 I 2B 18, 4/02/84 330 X 1 23 18, 4/02/84 l 331 I 33 21, 4/08/84 332 I 2B 18, 4/02/84 333 I 2D 18, 4/02/84 334 I
. 23 18, 4/02/84 335 I 2D 18, 4/02/84 336 I 2D 18, 4/02/84
, 337 I 23 18, 4/02/84 338 -
I I 21 18, 4/02/84 339 2I 18, 4/02/84
.. 340 1 1 3B 18, 4/02/84 341 2B 19, 4/05/84 342 I 2D 19, 4/05/84_ .
I O 343 344 I 1B 23 19, 4/05/84 21, 4/08/84 345 I 23 23, 4/10/84 346 I I 23 21, 4/08/84 347 2E 21, 4/08/84 - - - . .- ,
348 I 2 2D 21, 4/08/84 349 23 21, 4/08/84 .
350 I 2D 21, 4/08/84 351 X 2D 21, 4/08/84 352 I 2D 21, 4/08/84 353 I 2D 21, 4/08/84 354 1 ZD 21, 4/08/84 355 I 2D 21, 4/08/84 356 I 23 21, 4/08/84 357 I 2D 21, 4/08/84 l 358 I 23 21, 4/08/84 l i 359 I 23 21, 4/08/84 360 I 2D 21, 4/08/84 361 I l 21, 4/08/84 I I 2D 362 l
2D 21, 4/08/84 36.3 I
l .
L26sd10 1
l
l PROBLEM SHEET LISTING PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD I 2B 21, 4/08/84 364 I 2D 24,-4/13/84 365 I 2D 24,_4/13/84 ;
366 3B 24, 4/13/84 367 I 3B 24, 4/13/84 368 I 3B 24, 4/13/84 369 I 3A 24, 4/13/84 370 I 2D 24, 4/13/84 371 I I 3B 18, 4/02/84 800 I 3B 18, 4/02/84 801 I 3B 18, 4/02/84 802 I 3B 18, 4/02/84 803 _
I 3B 18, 4/02/84 804 I 3B 24, 3/13/84 805 I 3B 18, 4/02/84 806 I 3B 18, 4/02/84 O 807 808 I 3B 18, 4/02/84 18, 4/02/84 809 I 3B I 3B 18, 4/02/84 810 I 3B 18, 4/02/84 811 I 3B 23, 4/10/84 812 I 3B 22, 4/09/84 813 I 3B 22, 4/09/84 814 I 3B 22, 4/09/84 815 I 3B 23, 4/10/84 816 I 3B 23, 4/10/84 817 I 3B 23, 4/10/84-818 l
I 3B 23, 4/10/84 819 I 3B 23, 4/10/84 ,
820 I 3B 24, 4/13/84 l 821 I 3B 24, 4/13/84 822 I 33 24, 4/13/84 823 I 3B 24, 4/13/84 824 I 3B 24, 4/13/84 825 L26sd11 4 I
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i . . ..
TECENICAL SPECIFICATION PROBLEM SHEET Item Number: 365 Priority: 2D .
Impell / 4/3/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
4.8.2.1.e. 4.8.2.1.f Tech Spec'Page: 3/4 8-12 Problem
Title:
Battery Performance / Service Test
- a. FSAR Appendix 3A states that GCNS complies with Regulatory Guide 1.32, Revision 2. The Regulatory Guide position C.1.c states: "The battery service test described in IEEE Standard 450-1975 should be performed in addition to the battery performance discharge test." GCNS Technical Specification 4.8.2.1.e states: "Onc's per 60 month interval, this performance discharge test may be performed in lieu of the battery service test." These requirements seem to be in conflict.
- b. Regulatory Guides 1.32 and 1.129 refer to IEEE Standard 450-1975, which O' states that a performance test of battery capacity should be made within the first two years of service. This test is not addressed in the Technical Specifications.
- c. Surveillance Requirement 4.8.2.1.e requires a performance discharge test once per 60 months to verify battery capacity is at least 80 percent of the manufacturer's rating. However, Surveillance Requirement 4.8.2.1.f requires annual performance discharge tests when battery capacity drops below 90 percent of manufacturer's racing.
- 2. Safety Significance:
- a. None. Both the service test and the discharge test are performed according to IEEE Standard 450-1975. It is not necessary to perform the service test when the discharge test is required, since the discharge test is acre severe and envelopes the service test requirements.
O Rev. 24, 4/13/84 Pisd282.1
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l TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) .
i Item Numbei: 365 Priority: 2D
- b. None. Present Technical Specifications are adequate. Present testing requirements include a pre-installation service test and a service test within 18 months of installation.
- c. None. There is no conflict. The requirements as presently stated in the Technical Specification is to perform a performance test once every 60
. months to verify battery capacity is at least 80 percent of rated. If the battery capacity drops belov 90 percent, however, this test is performed annually, again to verify battery capacity is at least 80 percent of rated.
- 3. Anticipated Resolution:
Evaluate to confirm that all regulatory requirements pertaining to battery testing are adequately addressed by the Technical Specifications.
i 4. NRC Response to Item (NRR/IE):
NRC Notified: / -
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
. /
Date Time cc: J. E. Cross R. F. Rogers l
Rev. 24, 4/13/84 A.
Plsd282.2 1
l
e TECHNICAL SPECIFICATION PROBLEM SHEET f -
!1 Priority: 2D Item Nunber: 366 _
RPD /3/31/84 ,,_
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.3.8, Table 3.3.8-2 Tech Spec Page: 3/4 3-97, 3/4 3-99 B3/4 3-6 Problem
Title:
Containment Spray System Response Time
The present Technical Specification does not provide for a complete containment spray system response time test. Presently, administrative controls are required to assure that the combination of instrumentation response times Table 3.3.8-2, and the opening time for the E12-7028 valves does not exceed the 13 minute limit derived from FSAR 6. 2.1.1. 5. 5.
An LCO and Surveillance could be developed in a similar fashion to the ECCS system response time testing presently in 4.3.3.3. .
O 2. Safety Significance:
None. The total time for containment spray response can be administratively controlled, determined, and verified to be less than the required overall time by both:
- 1. Performing the surveillance required by Table 3.3.8-2.
- 2. Measuring valve opening time in accordance with ASME Section I.
- 3. Anticipated Resolution:
Investigate and evaluate the need to add a requirement for containment spray i system response time testing to the GGNS Technical Specification.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
.O Rev. 24, 4/13/84-i
?lsd283
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) .
Priority: 2D Item Number: 366
- 5. Disposition:
Items Closed: (How)
/
Date Time ec: J. E. Cross -
R. F. Rogers t
)
i i
Rev. 24, 4/13/84 Pisd283.0.1 f
- . u
) TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 367 Priority: 3B .
W. A. Russell / 3/20/84 Identified By Data Responsible Supervisor Tech Spec
Reference:
3.3.7.5 Tech Spec Page: 3/4 3-70, 3-71 Problem
Title:
Action Statement Not Consistent with Table
Item 13, containment /drywell area monitors, of Table 3.3.7.5-1 references Action 81. Action 81 addresses only operation with less than the " minimum channels operable". The Action Statement for item 13 should address " Required number of channels," as well as the " minimum channels operable"; therefore, Action 81 is inappropriate for item 13.
- 2. Safety Significance:
None. As long as the minimum operable channel requirement of Action 81 is met, accident monitoring capability is provided.
J
- 3. Anticipated Resolution:
Evaluate changing Action Statement to Action 80 for item 13.
l 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
- /
Date Time cc: J. E. Cross R. F. Rogers
' Rev. 24, 4/13/84
- Plsd283.1 l
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TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 368 Priority: 3B W. A. Russell / 3/20/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.7.5 Tech Spec Page: 3/4 3-70 Problem
Title:
Incorrect Nomenclature
4 Table 3.3.7.5-1 and 4.3.7.5-1, Items 13 through 18, should be revised to read
" radiation monitor" instead of " monitor". ]
i l
,2 . Safety Significance:
Resolved as part of Problem Sheet Item 329.
! 3. Anticipated Resolution:
- Resolved as part of Problem Sheet Item 329.
i 4 NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition: Refer to Problem Sheet Item 329.
Items Closed: (How)
/
Date Time cc: J. E. Cross R. F. Rogers
\
Rev. 24, 4/13/84.
Pisd283.2
l l
1
( TECENICAL SPECIFICATION PROBLEM SHEET Item Number: 369 Priority: 3B W. A. Russell /3/19/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.1 Tables 3.3.1-1 and 4.3.1.1-1 Tech Spec Page: 3/4 3-2, 3, 7, and 8 j
Problem
Title:
Applicable Operational Condition Inconsistencies
Table 3.3.1-1 specifies applicable operational conditions for reactor protection system instrumentation and several items have footnotes describing exceptions to these operational conditions. Table 4.3.1.1-1 specifies Surveillance Requirements for the instrumentation listed in Table 3.3.1-1, but does not contain the same footnotes for the affected items. This in effect j requires Surveillance to be performed when the instrumentation is not required l to be operable.
- 2. Safety Significance:
! None. Current instrumentation Surveillance Requirements are more conservative than the operability requirements.
- 3. Anticipated Resolution:
Evaluate to determine if appropriate footnotes should be added to Table 4.3.1.1-1, to make it consistent with Table 3.3.1-1.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time i
i 4
}
Rev. 24, 4/13/84 Plsd283.3
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I Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) .
4 Item Number: 369 Priority: 3B
- 5. Disposition:
Items Closed: (How) l
/
Date Time i ect J. E. Cross l
R. F. Rogers
~
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Rev. 24, 4/13/8f4 Plsd283.3.1
TECHNICAL SPECIFICATION PROBLEM SHEET i Item Number: 370 Priority: 3A _
W. A. Russell / 3/19/84 l
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.1 Tech Spec Page: 3/4 3-1 Problem
Title:
RPS Trip Bypass Instruments Not Addressed in Technical Specification
Instrumentation that provides for bypassing reactor protection system (RPS) trip functions is not addressed in CGNS Technical Specifications or the BWR-6 Standard Technical Specifications. The BWR owners group should give consideration toward including this instrumentation in Technical Specification.
- 2. Safety Significance:
I None. Instrumentation that provides RPS trips'is included in the Technical Specification.
- 3. Anticipated Resolution:
Evaluate incorporating any BWR onver's group resolutions.
- 4. NRC Response to Item (NRR/IE):
> NRC Notified: /
Individual Notified Date Time 1
- 5. Disposition:
]
Items Closed: (How)
/
Date Time ec: J. E. Cross R. F. Rogers Rev. 24, 4/13/84 Plsd283.4
TECHNICAL SPECIFICATION PROBLEM SHEET Priority: 2D Iten Number: 371 _
GE / 3/16/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.1.3.4 Tech Spec Page: 3/4 1-10 Problem
Title:
Control Rod Drive Coupling i 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
The BWR/6 Standard Technical Specification 3.1.3.4 states "The provisions of Specification 3.0.4 are not applicable" at the end of the Action Scacements but the Grand Gulf Technical Specification 3.1.3.4 does not contain this provision.
- 2. Safety Significance:
None. The Grand Gulf Technical Specification 3.1.3.4 is conservative as
- written by not allowing exception to the provisions of Technical Specification 3.0.4 I 3. Anticipated Resolution
l Investigate the necessity of a Technical Specification change to add "The provisions of Technical Specification 3.0.4 are not applicable" to provide operational enhancement.
! 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
'l l
l i Rev. 24, 4/13/84 I
- Pisd283.4.1
l A
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) ,
Item Number: 371 Priority: 2D
- 5. Disposition: -
Items Closed: (How)
/
Date Time ec: J. E. Cross R. F. Rogers j
1 l
i Rev. 24, 4/13/84 l
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Pisd283.4.2
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l TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 805 Priority: 3B CE FSAR/SER Reviev / 3-19-84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.1.5, FSAR Figure 9.3-26, 9.3.5.3 Tech Spec Page: 2/4 1-18 Problem
Title:
Sodium Pentaborate Volume
- a. FSAR Figure 9.3-26 specifies that the SLC shall be able to deliver 4,170 gallons of sodium pentaborate solution or the equivalent into the reactor. Technical Specification 4.1.5.a.2 requires verification that the available volume of sodium pentatorate solution is greater than or equal to 4.587 gallons. Technical Specification requirements are more restrictive than that required by FSAR Figure 9.3-26.
- b. FSAR Section 9.3.5.3 implies that operation of the redundant SLC pump will be demonstrated when an SLC pump is out for maintenance. There is O no Technical Specification requirement to perform this type of surveillance.
- 2. Safety Significance:
- a. None. Technical Specifications are conservative, relative to the FSAR.
- b. None. Pump operability is verified by normal Surveillance every 31 days.
Since the loops are redundant, there is no need to increase Surveillance.
on the operable loop where a redundant component of one loop is out for maintenance.
- 3. Anticipated Resolution:
- a. Confirm that changes to FSAR Figure 9.3-26 are not required.
- b. Revise the FSAR to reflect the testing required by Technical Specifications.
C) Rev. 24, 4/13/84 I'
Pisd289
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Page 2 I
TECHNICAL SPECIFICATION PROBi$M ' SHEET (CONT'D) ,
Item Number: 805 Priority: 3B
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
. Items Closed: (How) 4
/
Date Time lO cc: J. E. Cross R. F. Rogers 1
s I
s I
l I
O Rev. 24, 4/13/84 Plsd289.1
.: . :. :.. . .: . - . - L
^^ ~" -
TECHNICAL SPECIFICATION PROBLEM SHEET j
1 821 Priority: 3B Item Number: _
Impe11 /4/3/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4 1.3.3, FSAR 4.6.3.1.1.5.d i Tech Spec Page: 3/4 1-9 I
Problem
Title:
Control Rod Drive Accumulator Level
3 FSAR Section 4.6.3.1.1.5.d states that " Experience with control rod drive systems of the same type indicates that weekly verification of accumulator pressure and level is sufficient to assure operability of the accumulator portion of the control rod drive system." This is inconsistent with Surveillance 4.1.3.3.a. which only requires weekly verifict. tion of accumulator pressure. Plant design does not provide an indicator for accumulator level; however, a high level alarm is provided for leakage past the accumulator seals.
- 2. Safety Significance:
None. When the high water level alarm is noted for an accumulator' proper i actions are taken to ensure accumulator operability.
- 3. Anticipated Resolution:
Revise FSAR to delete the implication of a weekly accumulator Surveillance test.
I
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time t
lO Rev. 24, 4/13/84 P!sd312.1 1
-a a -m a Page 2 l i
TECHNICAL 'PECIPICATION PROBLEM SHEET (CONT'D) ,
Item Number: 821 Priority: 3B
- 5. Disposition:
Items Closed: (Hov)
/
Date Time cc: J. E. Cross i R. F. Rogers T
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f I
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l Rev. 24, 4/13/84 Plsd312.2 ,
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1
i TECHNICAL SPECIFICATION PROBLEM SHEET i Priority: 3B Item Number: 822 Imeell / 4/13/84 t Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.6.6.3; FSAR 6.2.3, 6.5.3 1 Tech Spec Page: 3/4 6-54 Problem
Title:
Standby Gas Treatment System Flow Test
- a. FSAR Appendix 3A states GGNS is in compliance with Regulatory Guide 1.52 Revision 1, but should reference Revision 2.
- b. Regulatory Guide 1.52 paragraph C.5.b describes an air flow distribution test, but this test is not included in Technical Specification 3/4.6.6.3. -
- c. GGNS FSAR erroneously states that the time for secondary containment negative pressure to be achieved is 120 seconds instead of 101 seconds in paragraph 6.5.1.3. FSAR paragraph 6.2.3.1.1.c should be revised to reflect the correct value of the 120 seconds
- d. F3AR Section 6.5.3 states that long tern operation flow rate of the ,
'O standby gas treatment system is 2300 cfa. However, Technical Specification 3/4.6.6.3 and the Surveillance Procedure state that long term flow rate is less than 4000 cfa.
! 2. Safety Significance:
J j a. None. This is a typographical error.
None. The referenced test is not required for normal operational b.
surveillances. The FSAR should be changed to reflect this,
- c. The FSAR Section 6.2.3.1.1.c does not accurately reflect the standby gas treatment system paramater. However, this has no effect on plant f operation or safety.
- d. None. Technical Specification and Surveillance Procedures are correct, and FSAR should be changed to reflect GGNS design requirements.
- 3. Anticipated Resolution:
Perform an evaluation to determine what FSAR changes, if any, are required.
l l Rev. 24, 4/13/84' f
i l -
Pisd313 l
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) ,
Item Number: 822 Priority: 3B
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time I cc: J. E. Cross
- ' ~ - ~ '
R. F. Rogers l
l O Rev. 24, 4/13/84 P1sd313.0.1
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i l
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( TECHNICAL SPECIFICATION PROBLEM SHEET
- )
Item Number: 823 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.6.6.2-1; FSAR Table 7.6-12 Tech Spec Page: 3/4 6-48 through 6-52; FSAR Table 7.6-12 Problem
Title:
FSAR/ Secondary Containment Ventilation System Automatic
- Isolation Dampers / Valves
The completeness of Technical Specification Table 3.6.6.2-1 cannot be verified by FSAR Table 7.6-12, auxiliary building isolation, since the specific I isolation dampers are not listed in FSAR Table 7.6-12.
I Additionally, FSAR Table 7.6-12 does not list the RHR "A" loop discharge to liquid radvaste valve (E12-F203) which is listed in Technical Specification Table 3.6.6.2-1.
- 2. Safety Significance
- -
None. The Technical Specification requirements can be verified by plant design documents other than the FSAR.
- 3. Anticipated Resolution:
Evaluate the necessity of adding the isolation dsspers and isolation valve E12-F203 to FSAR Table 7.6-12 and, if necessary, include the appropriate ,
changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
.l I
O Rev. 24, 4/13/84 Plsd313.1
/
1 .
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) ,
1 Item Number: 823 Priority: 3B
- 5. Disposition:
Items Closed: (How)
/
Date Time ec: J. E. Cross R. F. Rogers
(
~
\
Rev. 24, 4/13/84 Pisd314
/
TECHNICAL SPECIFICATION PROBLEM SHErr 6 -
Priority: 3B Item Number: 824 INEL Audit of Tech Specs /
Identified By Dato Responsible Supervisor Tech Spec Reference Technical Specification Table 3.6.4-1; FSAR Table 6.2-44 Tech Spec Page: 3/4 6-33 t.hroura 44 .
Proble:2
Title:
Containment and Drrvell Iso 3ation valves
Technical Specification Table 3.6 d-1, items 1.h through 4.b. lists several ,
containment and drywell isolation valvey that are not listed in FSAR Table -
6.2-44 (containment isolation valve information). Ecvever, some of these velves are listed in ISAR '.' ables 7.6-12, 6.2-48, and 6.2-49. .- 1
- F l
. 2. Safety Significance:
, None, Ihe ,Tec 2ical Specifiestion requirements can be verified by plant design documents other than the 7SAR. -
14 Anticipated Resolution:,,
investinne the ne-d to revise FSAR Table 6.2-44 r.sd if necessary, include appropriate changes in the next anassi FSAR update pe.r 10 CFR 50.71(e)(4). a
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
IndLT idual Notified Date Time
- 5. Disposition:
t'
\>
ear #
Items Closed: (How)
U j \
Date Time t
J. C. Cross cc: ,
R. F. Rogers .
Aav. 24, 4/13/84
[
f 7:ed115 f
- ,g , j
. 1 TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 825 Priority: 3B _
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.2-1; FSAR Section 5.4.6 Tech Spec Page: 3/4 3-12 & 13; FSAR Pages 5.4-15 & -16 Problem
Title:
FSAR/RCIC Isolation Instrumentation
FSAR Section 5.4.6 reactor core isolation cooling system (RCIC), does not currently reflect that valve group 9 requires concurrent drywell high pressure and RCIC staan supply pressure-low signals to isolate. However, note (m) to Technical Specification Table 3.3.2-1, items 5.b and 5.m for the RCIC steam supply pressure-low and drywell pressure-high actuation signals of the RCIC isolation trip function states that " Valve Group 9 require concurrent dryvell high pressure and RCIC steam supply pressure-lov signals to isolate".
- 2. Safety Significance:
O None. The note (a) in Table 3.3.2-1 adds explanatory information not necessary for safe operation of the isolation function. This information will only add clarification to the FSAR.
- 3. Anticipated Resolution:
! Evaluate the need to revise FSAR Section 5.4.6 and, if necessary, include appropriate changes in tae next annual FSAR update per 10 CFR 50.71(e)(4).
l
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time O Rev. 24, 4/13/84 Pisd316
t
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Page 2 6 _
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) ,
Item Number: 825 Priority: 3B j
- 5. Disposition:
Items Closed: (How)
/
Date Time cc: J. E. Cross R. F. Rogers 1
I
\ Rev. 24, 4/13/84 Plsd317 l
" TECH SPEC PRIORITY" O
MEMO TO: Tech Spec Review Personnel FROM: C. L. Tyrone
/
SUBJECT:
Rev. d to Technical Specification Problem Sheet j TSRT: 84/[)Q3Y DATE: Aotit // /98$l The following changes / additions are to be incorporated into the Tech Spec Problem Sheets:
~
ITEM NUMBER CHANGES / ADDITION 004 RemoveRev.l7.InsertRev.0$
0 19 Remove Rev.Ib Insert Rev.0 3 O(09 Remove Rev.l7, Insert Rev.85 ,
b 9(n RemoveRev.15,InsertRev.M
\OO RemoveRev.l$,InsertRev.@f kbh RemoveRev.Ib.InsertRev.95
\ Remove Rev.11 Insert Rev. O b
\gD RemoveRev.}Q,InsertRev.(C)
}Q RemoveRev.@,InsertRev.y 177 Remove Rev.17 Insert Rev. y
$Sb RemoveRev.SO,InsertRev.$$
i hM RemoveRev.h6InsertRev.$$
1 QQ RemoveRev.l8,InsertRev.gA I
C. L. Tyrone i
j CLT: sad Attachment j l
l cc: S. H. Hobbs (w/1)
File (Tech Spec Records) (w/1) i M2sd1
- Pega c1
" TECH SPEC PRIORITY" O' ITEM NUMBER CHANGES / ADDITION t
9% bwe Mcv 19 kn+ lev M k\ $nwve ev 19 bFe 5 $EV a15 294 l!Mov E ev. {S 1 N520Y sv Mi 3 05 9emnvE b 12 InsutRev D6 381 bove b 13 TNfEri REV d$
979 beve b , Lectb DS 990, hwsb -- ' Len&k os kM h vs % ,Tnsec+ L a5 RDS b ye % - Tussc+ 1 45 R99 %ovs % .- Iusso+ k n.S
%3b 9eMovn Lv - 1%sof ?ev.D$
O R3) weve L -- sse+L os RM b ovsh ,Twsectb 95
~s cc: S. H. Hobbs (w/1)
File (Tech Spec Records) (w/1)
M2sd2 I
TSRT-84/0934 PROBLEM SHEET LISTING AS OF April 16, 1984
( L Date PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD IB 15, 3/29/84 001 X 2E 15, 3/29/84 002 X 2D 17, 4/01/84 003 X X 2E 22, 4/09/84 004 IB 15, 3/29/84 005 I I 2D 21, 4/08/64 006 2F 15, 3/29/84 007 I I 2H 17, 4/01/84 008 X 2B 25, 4/16/84 009 X 2B 15, 3/29/84 010 X 2B 15, 3/29/84 011 2D 18, 4/02/84 012 X X 3A 21, 4/08/84 013 X 2B 21, 4/08/84 014 I IB 17, 4/01/84 .
015 0- 016 X IB 15, 3/29/84 X 2D 15, 3/29/84 017 I 3B 15, 3/29/84 018 X 2B 25, 4/16/84 019 020 X 2B 17, 4/01/84 021 X IC 15, 3/29/84 X 2A 17, 4/01/84 022 X 2B 15, 3/29/84 023 X 2B 18, 4/02/84 024 X 2D 17, 4/01/84 025 I 2D 15, 3/29/84 026 I 2E 15, 3/29/84 027 X 2B 15, 3/29/84 028 029 X 3B 17, 4/01/94, X 2D 17, 4/01/84 030 X 2D 17, 4/01/84 031 X 2B 21, 4/08/84 032 0- 033 X IB 18, 4/02/84 18, 4/02/84 034 X IC X 2C 15, 3/29/84 035 L26sd1
- , PROBLEM SHEET LISTING ITEM NUMBER REVIEiiED BY RPD PRIORITY REVISION, DATE 036 X 2E 20, 4/06/84 037 X IC 15, 3/29/84 038 X IC 15, 3/29/84 039 X 2G 17, 4/01/84 040 X 2F 17, 4/01/84 041 X 2B 21, 4/08/84 042 X 2B 15, 3/29/84 043 X 2D 15, 3/29/84 044 X 3B 17, 4/01/84 045 X 2B 17, 4/01/84 046 I 2F 15, 3/29/84 L
047 I 2B 15, 3/29/84 048 I 2H 15, 3/29/84 049 X 2B 18, 4/02/84 050 X 2B 17, 4/01/84 051 X 2D 15, 3/29/84 052 X 2E 15, 3/29/84 l
053 X 2E 17, 4/01/84 054 X 1B 21, 4/08/84 ,,
055 X 2D 15, 3/29/84 056 I 3B 21, 4/08/84 057 X 2B 17, 4/01/84 i
058 X 2D 17, 4/01/84 059 I 2D 17, 4/01/84 060 X 2B 15, 3/29/84 061 X 2D 15, 3/29/84 062 X 2E 18, 4/02/84 063 X 2E 17, 4/01/84 064 I 2E 15, 3/29/84 4
065 I 2E 15, 3/29/84 , ,
066 I 2D 22,'4/09/84 067 I 2D 15, 3/29/84 068 I 3B 15, 3/29/84 1
069 I 2E 25, 4/16/84 070 X 3B 18, 4/02/84 071 X 2D 17, 4/01/84 l 072 X 2D 17, 4/01/84 L26sd2
- PROBLEM SHEET LISTING PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD (s 073 074 X
X 2B 2D 18, 4/02/84 17, 4/01/84 x 2B 17, 4/01/84 075 X IB 18, 4/02/84 076 2B 21, 4/08/84 077 I IB 15, 3/29/84 078 X 2E 15, 3/29/84 079 X X N/A (Resolved) 15, 3/29/84 080 3A 15, 3/29/84 081 X 3A 15, 3/29/84 082 X 083 X 2B 22, 4/09/84 X 3A 15, 3/29/84 084 085 X 2D 20, 4/06/84 086 I 2D 18, 4/02/84 087 I 2D 17, 4/01/84 I 2D 17, 4/01/84 088 089 I 2D 15, 3/29/84 090 X 2D 17, 4/01/84 091 X 2D 15, 3/29/84 092 X 2D 18, 4/02/84 X 2E 22, 4/09/84 093 X 2D 21, 4/08/84 094 095 X 2E 22, 4/09/84 X 2E 25, 4/16/84 096 I 2E 15, 3/29/84 097 I 2G 15, 3/29/84 098 X 2G 21, 4/08/84 099 100 X 2B 25, 4/16/84 f
101 X 2E 15, 3/29/84 102 X 2B 15, 3/29/84 X 1B 18, 4/02/84 103 X 2E 17, 4/01/84 104 105 I 2E 25, 4/16/84 I 2E 25, 4/16/84 106
() 107 108 X
I 2E 2C 18, 4/02/84 15, 3/29/84 X 2D 15, 3/29/84
- 109 L26sd3 i - . . - . . , . . , , - . - . - -. . . . . -_ -- . _ . . .
. l
- PROBLEM SHEET LISTING ,
PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD I 2B 17, 4/01/84 j
! 4110 I 2D 18, 4/02/84 111 I 2A 15, 3/29/84 112 I N/A (Resolved) 15, 3/29/84 113 I 2B 18, 4/02/84 l 114 2D 17, 4/01/84 115 I I 2B 15, 3/29/84 116 N/A (Resolved) 18, 4/02/84 j l 117 I '
2D 16, 3/31/84 118 I I 2B 15, 3/29/84 119 X 2B 25, 4/16/84 120 121 I N/A (Resolved) 15,3/29/M I 2D 17, 4/01/84 122 I 2D 18, 4/02/84 123 124 I 2C 18, 4/02/84 125 I N/A (Resolved) 18, 4/02/84 I 2D 15, 3/29/84 126 I 2G 17, 4/01/84 127 128 I 2D 17, 4/01/84 I 2B 15, 3/29/84 129 I N/A (Resolved) 15, 3/29/84 130 I 2G 15, 3/29/84 131 .
I 2B 15, 3/29/84 132 I 2D 18, 4/02/84_
133 I 2D 17, 4/01/84 134 I N/A (Resolved) 18, 4/02/84 135 I 2D 15, 3/29/84 136 I 2B 15, 3/29/84 137 I 2D 15, 3/29/84 138 I IC 15, 3/29/84 139 I 2D 18, 4/02/84 140 I 2F 17, 4/01/84 141 I 2F 15, 3/29/84 142 I 2G 15, 3/29/84 7
143 I 2B 15, 3/29/84 144 I 2F 17, 4/01/84 145 I 2E 15, 3/29/84
- 146 L26sd4
- PROBLEM SHEET LISTING REVIE'ED BY RPD PRIORITY REVISION, DATE ITEM NUMBER X 3B 16, 3/31/84 147 X 3A 17, 4/01/84 f 148 X 3B 18, 4/02/84_
I 149 2G 17, 4/01/84 150 X X 3B 25, 4/16/84 151 X 2E 16, 3/31/84 152 X 2H 17, 4/01/84 153 2D 16, 3/31/84 154 X X 2D 18, 4/02/84 155 X 2D 17, 4/01/84 156 X 2D 17, 4/01/84 157 -
I 2D 17, 4/01/84 158 X 2D 16, 3/31/84 159 X 2E 21, 4/08/84 160 X 2E 18, 4/02/84 161 X 2D 16, 3/31/84 l 162 X 2D 16, 3/31/84 163 2 164 X 2B 18, 4/02/84 X 2D 17, 4/01/84 165 I 3B 17, 4/01/84 166 167 X 2B 17, 4/01/84 I 2B 21, 4/08/84 168 X 2D 18, 4/02/84 t
169 X 2E 16, 3/31/84 170 X 2D 16, 3/31/84 171 X 2B 17, 4/01/84 172 X 2D 21, 4/08/84 173 174 X 2E 17, 4/01/84 175 I 3B 21, 4/08/84 l 17, 4/01/84 176 X 2B I 2D 25, 4/16/84 177 178 X 2D 17, 4/01/84 179 X 2D 16, 3/31/84 180 X 2A 17, 4/01/84 181 X 2F 17, 4/01/84 1 X 2D 17, 4/01/84 182 X 2D 18, 4/02/84 183 L26sd5
FRCELIM SEZZ: 1.IST3G l IT m NUMBE1 IITITUE II 17D F1:01 5 IITI5 ION, DA2T 184 I 2D 16, 3/31/84
.I 185 I 23 18, 4/02/84 186 I N/A (lasolved) 18, 4/02/84 187 I 2G 18, 4/02/84 188 I 33 (lasolved) 15, 3/29/84 189 I ZH 18, 4/02/84 190 I 2D 20, 4/06/84 191 I ZD 78, 4/02/84 192 I ZD 16, 3/31/84 193 I ZD 16, 3/31/84 194 I 2D 18, 4/02/84 195 I 3A 18, 4/02/84 196 I 23 16, 3/31/84 197 I 3A _
21, 4/08/84 198 I IC 16, 3/31/84 199 I 33 18, 4/02/84 200 I 2G 18, 4/02/84 201 I 23 22, 4/09/84 202 I 3B 18, 4/02/84.
203 I 2D 22, 4/09/84 204 I 23 18, 4/02/84 205 I 23 16, 3/31/84 206 1 2G 16, 3/31/84 l
207 I 23 18, 4/02/84 )
208 I 23 18. 4/02/84 209 I 2B 15, 3/29/84 210 I 2G 18, 4/02/84 211 I 23 18, 4/02/84 212 I 2D 18, 4/02/84 213 I IC 16, 3/31/84 214 I 33 21, 4/08/84
- 215 I 33 16, 3/31/84 216 I 33 18, 4/02/84 217 I 33 21, 4/08/84 218 I 3A 21, 4/08/84 219 I 2
- 16, 3/31/84 220 I 3A 18, a/02/84 C6sd6
i
.= PROBLYM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 221 X 2D 16, 3/31/84 222 X 3B 16, 3/31/84 223 X 2B 18, 4/02/84 224 X 3B 16, 3/31/84
.225 X 2D 25, 4/16/84 226 X 3A 18, 4/02/84 227 I 3B 21, 4/08/84 228 X 3B 17, 4/01/84 229 X 2B 21, 4/08/84 230 X 2B (Resolved) 15, 3/29/84 231 X 3B 17, 4/01/84 232 X 3B 17, 4/01/84 233 X 2E 25, 4/16/84 l
l 234 X 3A 25, 4/16/84
! 18, 4/02/84
! 235 I 2B 236 X 2B 17, 4/01/84 237 X 2D 18, 4/02/84 18, 4/02/84 O 238 X 2D 239 X 2D 18, 4/02/84 240 X 2D 17, 4/01/84 l
l 241 X 2D 17, 4/01/84 242 X 3B 18, 4/02/84 243 X 3B 18, 4/02/84 244 X 2B 18, 4/02/84 245 X 2B 17, 4/01/84 246 X 2B 18, 4/02/84 247 X 2B 18, 4/02/84 248 X 2D 18, 4/02/84 249 X 2D 22,'4/,09/84 250 X 2B 18, 4/02/84 251 X 2F 18, 4/02/84 252 I *3B 18, 4/02/84 253 X 2C 18, 4/02/84 254 X 3B 18, 4/02/84 O
- Priority changed from 1A per J. C. Roberts 3/27/84 L26sd7 y ,-www-,-,--w,*y.ye-w%i-e--e w,- --- w-w-- -r- , ,+e- m- . ,, -e--
. e - -- -----, - - - - - - y --- -. ..-- - - - - s -
_ ~ _
I PROBLEM SHEET LISTING PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD 2E 18, 4/02/84 (p 255 X X 2E 25, 4/16/84 256 X Sub, 2E 18, 4/02/84 256-1 I 2B 17, 4/01/84 257 3B 18, 4/02/84 258 X X 2B 18, 4/02/84 259 X 3B 18, 4/02/84 4 260 X 3A 18, 4/02/84 261 X IC 16, 3/31/84 262 I 2D 17, 4/01/84 i 263 X 2B 17, 4/01/84 264 I 2D 18, 4/02/84 265 X 2B 17, 4/01/84 266 I 2B 18, 4/02/84
! 267 X 2F 18, 4/02/84 268 I 2D 18, 4/02/84 269 X 2E 22, 4/09/84 270 X 2B 18, 4/02/84 271 X 2D 22, 4/09/84
! 272 X 2B 18, 4/02/84 i 273 X 2D 18, 4/02/84 274 X 2B 18, 4/02/84 1
275 I 2D 18, 4/02/84 276 X 2B 18, 4/02/84 277 18, 4/02/84 I 2D
'. 278 17, 4/01/84 279 I 2D X 2D 18, 4/02/84 280 1 X 2E 25, 4/16/84 281 X 2E 17, 4/01/84 ,
282 X 2E 17, 4/01/84 <
283 ' ' '
X 2B 18, 4/02/84 284 X IC 18, 4/02/84 285 X 2D 18, 4/02/84 j 286 X 2D 18, 4/02/84 I 287 I 2D 18, 4/02/84 1 288 X 2E 18, 4/02/84 l 289 X 2E 18, 4/02/84 1 290 I
L26sd8
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 291 X *3B 18, 4/02/84 l
292 X IB 18, 4/02/84 293 X IB 18, 4/02/84 294 X 2B 18, 4/02/84 295 X 2E 18, 4/02/84 296 X 2E 18, 4/02/84 297 X 2B 18, 4/02/84 298 X 2E 18, 4/02/84 299 X 2B 25, 4/16/84 300 X 3A 18, 4/02/84 301 X 2E 18, 4/02/84 302 X 2D 18, 4/02/84 303 X 2B 18, 4/02/84 304 X 2D 21, 4/08/84 305 X 21 25, 4/16/84 306 X IB 18, 4/02/84 307 X 2B 18, 4/02/84 308 X 1B 18, 4/02/84 309 X 2A 18, 4/02/84 310 X 2A 18, 4/02/84 311 X 2E 18, 4/02/84 312 X 2B 22, 4/09/84 313 X 2B 18, 4/02/84 314 X 2B 18, 4/02/84 i 315 X 2B 18, 4/02/84 316 X 2B 18, 4/02/84 317 X 2E 18, 4/02/84 318 I 3B 18, 4/02/84 319 I 2E 21, 4/08/84 320 X 2E 18, 4/02/84 321 X 2B 18, 4/02/84 322 X 2E 18, 4/02/84 323 X 2B 18, 4/02/84 324 X 2E 18, 4/02/84 325 X 2I 18, 4/02/84
- Prioriev changed from 1A per J. C. Roberts 3/27/84.
L26sd9
. -. - - ~ _ . . -. - - - ._ _
PROBLEM SHEET LISTING PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD X 2I 18, 4/02/84
- 326 X 3B 18, 4/02/84 327 I 3B 25, 4/16/84 l 328 1C 18, 4/02/84 329 I l 18, 4/02/84 X 2B 330
' 2B 18, 4/02/84 331 X 3B 21, 4/08/84 332 I X 2B 18, 4/02/84 333 X 2D 18, 4/02/84 i 334 i
X 2B 18, 4/02/84 335 X 2D 18, 4/02/84 ;
336 I 2D 18, 4/02/84 j 337 I 2B 18, 4/02/84
! 338 X 2I 18, 4/02/84 339 X 2I 18, 4/02/84 340 1'
3B 18, 4/02/84 341 X X 2B 19, 4/05/84 i 342 X 2D 19, 4/05/84 343 IB 19, 4/05/84 j 344 X I 2B 21, 4/08/84 345 I 2B 23, 4/10/84 346 X 2B 21, 4/08/84 347 2E 21, 4/08/84
- 348 X 2D 21, 4/08/84
- 349 I X 2B 21, 4/08/84 350 X 2D 21, 4/08/84 351 1
' 2D 21, 4/08/84 352 X X 2D 21, 4/08/84 353 X 2D 21, 4/08/84 354 2D 21, 4/08/84
+ 355 X 2D 21, 4/08/84 i 356 X X 2B 21, 4/08/84 357 X 2D 21, 4/08/84 j 358 X 2B 21, 4/08/84 359 X 2B 21, 4/08/84 j 360 2D 21, 4/08/84'
! 361 X 2D '21, 4/08/84 362 X ;
X 2D 21, 4/08/84 363
! L26sd10 l I
_ -)
s
__ . _ _ . = _ _ . _ __ _ _ _ _ _ _ _ . _ _ _ . _ . . ._ _- . _ _ _ . _ _ _ _ _ _ _ _ .
PROBLEM SHEET LISTING REVISION, DATE ITEM NUMBER REVIEWED BY RPD PRIORITY 2B 21, 4/08/84 364 X 2D 24, 4/13/84 365 K 2D 24, 4/13/84 366 I 3B 24, 4/13/84 367 X 24, 4/13/84 )
I 3B l 368 3B 24, 4/13/84 l
! 369 I 3A 24, 4/13/84 370 X 2D 24, 4/13/84 371 X f
' X 2B 25, 4/16/84 372 18, 4/02/84 X 3B 800 l
3B 18, 4/02/84 801 X 3B 18, 4/02/84 802 X j
3B 18, 4/02/84 803 X i 3B 18, 4/02/84 804 X 3B 24, 3/13/84 I 805 I 3B 18, 4/02/84 806 I l
3B 18, 4/02/84 807 X 3B 18, 4/02/84 808 I l,
3B 18, 4/02/84 809 X 3B 18, 4/02/84 810 X 3B 18, 4/02/84 811 X 35 23, 4/10/84 812 X 3B 22, 4/09/84 813 I l 3B 22, 4/09/84 814 X l 22, 4/09/84 I 3B l 815 3B 23, 4/10/84 816 I 3B 23, 4/10/84 817 X f 23, 4/10/84 X 3B 818 35 23, 4/10/84 819 I 3B 23, 4/10/84 820 X 35 24, 4/13/84 821 X f
35 24, 4/13/84 822 X l
3B 24, 4/13/84 i 823 X 3B 24, 4/13/84 824 X 3B 24, 4/13/84 !
825 X i
J L26sd11
(
- _ _ . . . . _ . . . . _ _ _ _ _ . . _ . . , . . - . _ . _ _ . . . _ _ _ . . . _ . . _ . - _ _ . . . _ . . . _ . . . _ _ , _ _ .. _.,_ . _ . . _ _ _ ,_.a, , . _ _ _ _ . . . .
. PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 1
X 3B 25, 4/16/84 826 827 I 3B 25, 4/16/84 i 828 X 3B 25, 4/16/84 i
829 I 3B 25, 4/16/84 830 I 3B 25, 4/16/84 831 X 3B 25, 4/16/84 I 3B 25, 4/16/84 832' i
i O
1 i,
l 4
i i
1 ,
1
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! L26sd12 i
t - _ _ _ . , _ _ . - _ _ _ _ _ . . _ _ _ . ~ -
l l
TECHNICAL SPECIFICATION PROBLEM SHEET l Item Number: 009 Priority: 2B l
- Identified By Date Responsible Supervisor
- l Tech Spec
Reference:
3.3.7.6, 3.9.2 and Table 3.3.6-1 Tech Spec Page: 3/4 3-50, 3/4 3-73, 3/4 9-3 ;
I j Problem
Title:
SRM Operability Requirements
{ 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
The Technical Specifications give different requirements for the minimum number of operable source range monitor (SRM) channels in the same applicable j operational conditions.
i 1. Technical Specification Table 3.3.6-1. Item 3 requires a minimum of four
{
operable SRM channels per trip function in Operational Conditions 2 and 5.
! 2. Technical Specification 3.3.7.6 states that at least three SRM channels be operable in Operational Condition 2* (with IRMs on range 2 or below),
!O 3 and 4.
required.
However, preliminary investigation indicates that four are
, 3. Technical Specification 3.9.2 requires that at least two SRM channels be operable and inserted to the normal operating level with several
) additional special requirements in Operational Condition 5.
i
- 2. Safety Significance:
None. There are different requirements for the minimum number of Operable SRM ,
channels in the same operational condition because some requirements are addressing control rod block trip; functions and other requirements are addressing the monitoring of the neutron level in the core.
- 3. Anticipated Resolution:
Evaluate the different requirements for the required minimum number of operable SRM channels in Operational Conditions 2 and 5 (with respect to control rod block trip. functions and monitoring of the neutren level in the core). Propose Technical Specification changes if necessary.
O Rev. 25, 4/16/84 Misd14
i Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 009 Priority: 2B
! 4. NRC Response to Item (NRR/IE):
l NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
1 I
l l
j Items Closed: (How) 1
/
Date Time l
Reference:
TSRT-84/0153, page 14
] TSRT-84/0283, pages 1, 2, 4, 8, and 9.
cc: J. E. Cross R. F. Rogers i
i I
\-
e 3
1 i
,i Rev.. 25. 4/16/84-Misd15 4
w--, , - ,-- - - - -,,-,,,,.yr.-vr--~ ,,n.---r., --
e-.-r- r , ,-y-- - . .._--- ..,,-y . . , - - - - ,-
\
i ECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 019 Priority: 2B
. /
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.6.7.3.b.1 Tech Spec Page: 3/4 6-58 Problem
Title:
Drvwell Purge Flow Rate Definition
Technical Specification 4.6.7.3.b.1 requires verification of a dryvell purge flow rate of 1000 cfm every 18 months. However, MP&L's response to NUREG-0588 specified a drywell purge flow rate of 1000 scfm. Since the flow rate is temperature and pressure dependent, it may be appropriate to require scfm flow rates to meet NUREG-0588 requirements.
I Delete the word " continued" adjacent to " Surveillance Requirements" under
O
- 2. Safety Significance:
Adequate drywell purge flow is needed to ensure that drywell conditions s're maintained within equipment qualification limits. The use of cfm instead of scfm may result in flow rates less conservative than those required to meet qualification requirements. MP&L surveillance procedures require the use of the more conservative method.
i
- 3. Anticipated Resolution:
Review requirements of the response to NUREG-0588 and evaluate whether a i
Technical Specifications revision from cfm to scfm is required. Present plant surveillance procedures use scfm.
4 NRC Response to Item (NRR/IE):
l l NRC Notifiad: /
Individual Notified Date Time O
Rev. 25, 4/16/84 Ml?d31
l l .
l Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number 019 Priority 2B
- 5. Disposition:
Items Closed: (How) f
/
Date Time
Reference:
TSRT-84/0440, Page 5 4
cc: J. E. Cross R. F. Rogers i
1 1
I Rev. 25, 4/16/84 Misd34 l
TECHNICAL SPECIFICATION PROBLEM SHEEI Item Number: 069 Priority: 2E
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.6.7.2 Tech Spec Page: 3/4 6-57 j
Problem
Title:
H2 Igniter Surveillance
Surveillance Requirement 4.6.7.2.a specifies that at least 41 hydrogen igniter glow plugs per containment and drywell hydrogen ignition subsystem must be verified to be energized after the supply breakers are energized during the surveillance test. The wording for this Surveillance Requirement riay need clarification since there is a question whether the igniter glow plugs are
. energized after the supply breakers are energized. The Nuclear Regulatory Commission (NRC) has suggested that the Surveillance Requirement should be .
I supplemented with an additional requirement to ensure operability for a minimum of one igniter on cach redundant circuit in an enclosed region. A question has been raised with respect to the NRC's suggestion that.if all inoperable igniters were located in the drywell, igniter coverage in the drywell might be inadequate.
! 2. Safety Significance:
The wording of the Surveillance Requirement has no safety significance since the igniters will be determined to be operable regardless of whether or not they are energized after the supply breakers are energized or after some other action. Ignitors from redundant emergency safeguard feature power supplies are located in each enclosed region in the containment or drywell. The l present requirement for containment and drywell hydrogen ignition subsystem operability would allow 41 out of 45 slow plugs to be operable. It is possible that, of the 4 igniters per division which could be inoperable, ignitors from both divisions in an enclosed region could be inoperable at the same time. This could create conditions which allow pocketing of hydrogen in enclosed regions.
O Rev. 25, 4/16/34 Misd121
_ - - - ~ - _ --, -- .
Page 2 i TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) i
) Item Number: 069 Priority 2E The issue of all inoperable igniters from each igniter subsystem being located in the dryvell has no safety significance. The igniter system has been designed with sufficient redundancy so that the igniters powered from a single division would be sufficient to assure initiation of hydrogen combustion, in
\
the drywell or containment. Thus, inoperability of 8 igniters in the dryvell j would not impair the hydrogen ignition system's ability to perform its l intended function.
! 3. Anticipated Resolution:
A review by the Architect / Engineer concluded that the wide spread distribution of the igniters provides assurance that the system would perform its intended function even with up to 4 igniters per division inoperable. An additional v evaluation will be completed to determine if the wording for Surveillance i
Requirement 4.6.7.2.a should be modified so that it accurately reflects how the igniter glow plugs are energized. An additional evaluation will be performed to determine if the igniter glow plug operability requirements should be modified to require operability of at least one glow plus per redundant circuit in an enclosed region. This evaluation will also confirm that inoperability of up to 4 igniters in the drywell per igniter subsystem is acceptable.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time l
O Rev. 25, 4/16/84
$8.l sd 122
Page 3 TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 069 Priority 2E
- 5. Disposition:
i i
f Items Closed: (How)
/
Date Time i
Reference:
TSRT-84/0341, page 27 (items 1 and 2), page 12-14 AECM-82/193 cc: J. E. Cross ,
l R. F. Rogers l
l J
i t
1 4
l l
i 1
i i
)
Rev. 25, 4/16/84 I
Misd123
TECHNICAL SPECIFICATION PROBLEM SHEET O
Item Number: 096 Priority: 2E
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
6.5.2.7 Tech Spec _Page: 6-10 Problem
Title:
FSAR Section 12.1.1.2 states that the Safety Review Committee (SRC) will review the audits of ALARA appraisals semiannually. This iten is not included in the list of items to be reviewed by the SRC in Technical Specification 6.5.2.7.
- 2. Safety Significance:
None. This item has no impact on plant safety.
- 3. Anticipated Resolution:
O Investigate the necessity of changing Technical Specification 6.5.2.7 to add review of ALARA appraisals to SRC duties.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/ <
Date Time
Reference:
TSRT-84/0741, pages 8 and 14 TSRT-84/0550 cc: J. E. Cross R. F. Rogers Rev. 25, 4/16/84 Misd169 l
TECHNICAL SPECIFICATION PROBLEM SHEET 100 Priority: 2B l Item Number:
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.7.8-1 Tech Spec Page: 3/4 7-44 Problem
Title:
ESF Switchgear and Batterv Room Maximum Temperature
During the environmental qualification review performed in response to NUREG-0588, Bechtel determined that the control building ESF switchgear and battery room maximum temperature specified in Technical Specification 3/4.7.8 should be reduced to 90*F from 104*F. This temperature reduction is necessary to maintain a 40-year lifetime rating for the ESF switchgear transformer. The existing ventilation system for the EST switchgear and battery room may not be able to maintain the area temperature at 90*F during some portions of the year. Other temperatures within Table 3.7.8-1 may not reflect or be consistent with NUREG-0588 qualification assumptions.
- 2. Safety Significance:
None. The effect of subjecting equipment to an elevated normal operating temperature is limited to a reduction in its qualified lifetime. The equipment would operate as required to satisfy its design function with a ,
shortened qualified life.
- 3. Anticipated Resolution:
A design modification is being implemented to provide additional ventilation to the ESF switchgear and battery room to permit the normal operating area temperature to be maintained below 90*F. The Bechtel environmental qualification analysis for the EST switchgear transformer will be reviewed and a Technical Specification change to the room temperature limit will be submitted if necessary. An engineering evaluation of any equipment in the ESF switchgear and battery room which experiences an elevated normal operating temperature will be performed to determine the associated reductions in O Rev. 25, 4/16/84 Misd17A l
________________________._______j
._. - - . -_ . . - - . .-. . - _ _ . - - . - . =- __ ..
i, Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number 100 Priority 2B j
qualified life for the affected equipment. The results of this investigation v111 be incoprorated into appropriate maintenance and surveillance programs to l
! ensure proper equipment qualifications. Evaluate Table 3.7.8-1 to determina j if it should reflect NUREG-0588 requirements.
1
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
s Items Closed: (How) l l /
Date Time i
Reference:
TSRT-84/0750 cc: J. E. Cross R. F. Rogers l
l l
Rev. 25. 4/16/84 Misd177 y, t
. . - - - - , - _ , - . - - , . - - - . . . . - - _ - - ---~,-----__._-.m ---,.--.-_.------._r---_ -
- . _ ._.~.,.--,,.-,,--,-----,.-,--.y --.ir< . , , . , , - ~ ~
.-w.-
4 TECHNICAL SPECIFICATION PROBLEM SHEET i Item Number: 105 Priority: 2E
, /
) Identified By Date Responsible Supervisor j Tech Spec
Reference:
5.1.3, (Figure 5.1.1-1 note 3, Figure 5.1.2-1 note 2, 5.1.3-1 Tech Spec Page: 5-1, 5-2, 5-3, and 5-4 j
Problem
Title:
Effluent Release Boundary for Gaseous and Liquid Effluent
a) The terminology " Unrestricted Area Boundary" used in Technical Specification 5.1.3 is incorrect for gaseous and liquid effluents. " Effluent j release boundary" is the . appropriate terminology for the Technical l Specification. " Unrestricted area boundary" is also used in the text of I Technical Specification 5.1.3, and in the title of Figure 5.1.3-1, and in note 1
- 3 of Figure 5.1.1-1. b) A typographical error exists in note 3 of Figure I 5.1.1-1, as it references " Figure 5.1.4-1" instead of the correct " Figure 5.1.3-1." c) A typographical error exists on Figure 5.1.2-1, note 2; "if" .
should be "is."
- 2. Safety Significance:
None. The change is purely administrative in nature, since it involves only the correction of terminology and typographical errors.
i
! 3. Anticipated Resolution:
, Submit proposed Technical Specification changes to correct the terminology in i Technical Specification 5.1.3, Figure 5.1.1-1 note 3 and Figure 5.1.3-1 and the typographical errors in Figure 5.1.1-1, note 3 and Figure 5.1.2-1, note 2.
1
- 4. NRC Response to Item (NRR/IE):
! NRC Notified: /
- Individual Notified Date Time 1
l l
Rev. 25, 4/16/84
- l. ,
i- '
- -P.1sd135 I 4 -- 2 .4 . g ,.
- .
_ .t. . . . . . . . ... ... .. . . _ ,
. _ . _ _ . _ . _ _ _ _ _ _ . __ . _ . _ _ _ . _ _ _ _ . . _ _ _ _ _ ,,-. _ __ __ .~
L Page 2 a
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) d Item Number 105 Priority 2E
5.1 Disposition
Items Closed: (How) r
. , /
Date Time
^
Refarence: TSRT-84/0211 cc: J. E. Cross
~
R. F. Rogers ~
i o
Rev. 25, 4/16/84 Misd186
TECHNICAL SPECIFICATION PROBLEM SHEET O 2E Item Number: 106 Priority:
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
6.5.1.2 Tech Spec Page: 6-7 Problem
Title:
Change in PSRC Membership
Technical Specification 6.5.1.2 currently limits the Plant Safety Review Committee (PSRC) composition to seven members. This proposed change would add two members to the PSRC. The plant responsibilities of the proposed new members are described in FSAR Section 13.1.2.2.10.
- 2. Safety Significance:
None. The proposed change would add two members whose job specification requires a broad-based knowledge of GGNS operation and would enhance the capabilities of the PSRC by permitting the insights based on these new members functional responsibilities to be utilized in the review function.
- 3. Anticipated Resolution:
A Technical Specification change has been proposed to the NRC in a letter from L. F. Dale to H. R. Denton, dated September 9,1983 (AECM-83/0565, Item 20).
1
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time l
O Rev. 25, 4/16/84 Misd187
l O Page 2 O
TECHNICAL SPECIFICATICH PP.0BLEM SHEET (CONT'D)
Item Number: 106 Priority: 2E
- 5. Disposition:
l 1
Items Closed: (Hov) i
/
Date Time
Reference:
TSRT-84/0551 cc: J. E. Cross R. F. Rogers i
9 f
Rev. 25, 4/16/84 Misdl87.1
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 120 Priority: 2B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Tables. 3.3.7.1-1, 4.3.7.1-1, 3.3.7.12-1, and 4.3.7.12-1 Tech Spec Page: 3/4 3-56, 3-59, 3-90, 3-94 Problem
Title:
Offgas Pretreatment and Post-treatment Radiation Monitors
The offgas pre-treatment and post-treatment radiation monitors appear in Tables 3.3.7.1-1, 4.3.7.1-1, 3.3.7.12-1, and 4.3.7.12-1. Tables 3.3.7.1-1 and 4.3.7.1-1 identify requirements for radiation monitors while Tables 3.3.7.12-1 and 4.3.7.12-1 identify requirements for radioactive gaseous effluent monitors. Since the offgas pre-treatment and post-treatment radiation l monitors provide a gaseous affluent monitoring function, the instruments should be included in Tables 3.3.7.12-1 and 4.3.7.12-1 and not in Tables 3.3.7.1-1 and 4.3.7.1-1.
O The minimum number of operable channels for the offgas pest-treatment monitors should be inc.reased to 2 for consistency with the GE Standard Technical Specifications.
- 2. Safety Significance:
None. The changes are purely administrative and will provide consistency in the Technical Specifications.
- 3. Anticipated Resolution:
Mississippi Power & Light Company submitted the changes required to resolve this item in a letter to H. R. Denton from L. F. Dale, dated September 9, 1983 (AECM-83/0565).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time O Rev. 25, 4/16/84 Misd211
i e
I Page 2 i
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number 120 Priority 2B
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
Reference:
TSRT-84/0264, page 8 l cc: J. E. Cross O
R. F. Rogers i
l I
l i
l O !
- Rev. 25, 4/16/84 i l . I I
Misd212 l
TECHNICAL SPECIFICATION PROBLEM SHEET O
Item Number: 151 Priority: 3B
/
Identified By Data Responsible Supervisor Tech Spec
Reference:
Table 2.2.1-1, Item 2 Tech Spec Page: 2-4 Problem
Title:
APRM Power Setpoint Discrepancy
- a. Section 7.2.2 of the Safety Evaluation Report (SER) for Grand Gulf (NUREG-0831) states:
"The average power range monitor for Grand Gulf is designed to permit different setpoints for slow and rapid changes in flux level. Each APRM signal is fed to two trip amplifers rather than one. The APRM signal is connected directly to one trip amplifier that operates with a fixed high speed trip point to be specified in the Technical Specifications, but no more than 112.5 percent power according to the current PSAR."
O b. Technical Specification Table 2.2.1-1 item 2 lists the allowable values for APRM neutron flux-high as less than or equal to 120 percent of rated thermal power.
- 2. Safety Significance: -
None. The Technical Specifications are correctly written to the current General Electric Specification data sheet 22A3739AE Revision 4 Sheet 11.
- 3. Anticipated Resolution:
A change to FSAR Table 7.2.1 will be submitted.
- 4. N?.C Response to Item (NRR/IE): ,
NRC Notified: /
Individual Notified Date Time Rev. 25, 4/16/84 Misd262
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) 1 Item Number: 151 Priority: 3B l J
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
References:
- 1) TSRT-84/0235
- 2) TSRT-84/0648, page 11 cc: J. E. Cross O R. F. Rogers i
O Rev. 25, 4/16/84 Misd263
. . . . - _ . . ~ . , . . . . ~ .- . - . . ..
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 177 Priority: 2D
/
. Identified By Date Responsible Supervisor Tech Spec
Reference:
3.8.2.2 Tech Spec Page: 3/4 8-14 Problem
Title:
D.C. Sources - Operating and Shutdown - Action Statement
Action Statement c. of Technical Specification 3.8.2.2 is not worded consistently with Action Statement c. of Technical Specification 3.8.2.1.
Both of these Action Statements require completion of essentially the same action and the Action Statements should be worded consistently to avoid any possible confusion. In Technical Specification 3.8.2.2 Action Statement c.,
the phrase "with the above required full capacity charger inoperable..."
should be changed to "with one of the above required full capacity chargers inoperable.."
O 2. Safety Significance:
None. The Technical Specifications are correct as currently worded and reflect the requirements for D.C. sources - operating and shutdown.
- 3. Anticipated Resolution:
None. The wording of each Technical Specification is correct for that Technical Specification. No changes are required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time Rev. 25, 4/16/84 MIsd308
l I
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TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 177 Priority: 2D
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
Reference:
TSRT-84/0422 cc: J. E. Cross R. F. Rogers e
l Rev. 25, 4/16/84 Misd309
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 225 Priority: 2D NRC (I&E plus NRR) /1/24/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
Figures That Are Illegible or Contain Nonsafetv-Related 4 Errors.
Tech Spec ? age: Applicable Pages Problem
Title:
Illegible Figure Unrestricted Area Boundary
Various Technical Specification Figures have been identified as being difficult to read to the point of being illegible. Some of these include inappropriate terminolgy or misspelled words as well (e.g. unrestricted area l boundary should be site boundary).
Additionally, Figure 5.1.3-1 which is presently illegible must be corrected such that it is legible and well marked. This figure must also identify the
" site" with respect to Technical Specification 3.fl.2.1.
- 2. Safety Significance:
None. This is an enhancement item. These figures can presently be obtaired from the FSAR or other plant specific documents.
- 3. Anticipated Resolution:
Review those figures considered illegible and obtain new and corrected figures, as appropriate, for inclusion into the Techneial Specifications.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time O . Rev. 25, 4/16/94 Pisd49
O Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 225 Priority: 2D
- 5. Disposition:
Items Closed: (How)
/
Date Time
References:
TSRI-84/G035 TSRT-84/0220 TSRT-84/0212 O TSRT-84/0210 TSRT-84/0288 TSRT-64/0211 Proof and Review comments from Enclosure 3. Attachment A, Items 8 and 9 of Category 1 l
cc: J. E. Cross R. F. Rogers O
Rev. 25, 4/16/84 Ptsd50
,s :. . : war y n n ; ;. .
- _, n ; 1.; :,; .; e _.n ., . T;, y .,..y, ~ _ _. _ . p ._ , ; i 3 TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 233 Priority: 2E
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.5.1.b, 4.6.3.2.b Tech Spec Page: 3/4 5-4, 3/4 6-24 froblem
Title:
RHR Flows for Containment Spray Mode
The flow rates for the RER pumps required in Surveillance Requirements 4.5.1.b and 4.6.3.2.b are not consistent. Surveillance Requirement 4.~5.1.b, which is the flow tist for low pressure coolant injection (LPCI), requires a flow of 7,450 gpm through the RHR heat exchanger to the suppression pool, while Surveillance Requirement 4.6.3.2.b, for the containment spray system. only requires a flow of 5,650 gpm. It appears that the containment spray flow rate of 5,650 gpm was taken from the design value of flow at the spray nozzles (see FSAR Figures 5.4-18 and 19 and FSAR Section 6.5.2.2). This flow value is lower than the LPCI value of 7,450 gpm since the RHR pump must overcome a greater head to deliver ficw to the noz les. Therefore, testing to confirm a flow rate of 7,450 gpm through the heat exchangers to the suppression pool should be sufficient to demonstrate adequate flow at the spray nozzles.
- 2. Safety Significance:
None. The requirements of 4.5.1.b and 4.6.3.2.b may not be satisfied by the performance of the same surveillance procedure. This procedure verifies that a flow of 7,450 gpm is delivered through the heat exchangers to the suppression pool.
4
- 3. Anticipated Resolution:
Verify that a tested flow rate of 7,450 gpm through the RER heat exchangers to the suppression pool corresponds to the required flow rate of 5,650 gym at the spray nozzles. A Technical Specification change may be required to assure that the performance test will demonstrate containment spray operability.
O Rev. 25, 4/16/84 Pisd61
\
Page 2 O
TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D)
Item Number: 233 Priority: 2E
- 4. NRC Response to Item (NRR/IE):
NRC Notified: / ,
Individual Notified Date Time
- 5. Disposition: The ECCS scope of Problem Sheet 233 has been transferred to Problem Sheet 344.
Items Closed: (How) l l
Date Time
Reference:
'TSRT-84/0585, Page 22 cc: J. E. Cross R. F. Rogers -
l l
1 -
O Rev. 25, 4/16/84' Pisd62
{ s.
l TECHNICAL SPECIFICATION PROBLEM SHEET l
1 Item Number: 234 Priority: 3A
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.3.7.5-1. 4.5.3.1, 4.6.3.1 -
Tech Spec Page: 3/4 3-72, 3/4 5-9. 3/4 6-22 Problem
Title:
Suppression Pool Water Level
An NRC inspector identified in his exit interview on February 24, 1984, the following: ,;
FSAR Section 6.2.7.5 indicates that the suppression pool level indication system is m'ade up of four level detector channels, (two detector channels per division). It also indicates that each of these channels provides a high-water-level alarm, low-water-level alarm, low-low-water-level alarm, as well as a signal to open suppression pool makeup valves. I In actuality, there are three active level detector channels per division. Two channels are vida range and one channel is narrow range.
~ '
Ihere is also one aYditional channel per division which is only used for indication at the remote shutdown panel. Fach wide range channel supplies input to their respective division's suppression pool makeup system in a one-out-of-two logic as well as providing a low-low-level alarm at 16 feet 10 inches. The narrow range channel in each division I provides the divisional low-level.and high-level alarms (18 feet 5 1/2 inches and 18 feet 9 inches, respectively). Surveillance Requirements 4.3.7.5-1 (Item 3), 4.5.3.1, and 4.6.3.1.c are written to conform to the
- FSAR but are not in. clear agreement with actual plant design.
- 2. Safety Significance:
None. The provisions in the current Technical Specifications, FSAR, and plant design can cause misinterpretation as to which instrument chaanel is being addressed and which Limiting Condition for Operation (LCO) and Surveillance Requirement apply.
Rev. 25, 4/16/84 Pisd63
i l
l Page 2 O TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 234 Priority: 3A
- 3. Anticipated Resolution:
Evaluate and submit changes to FSAR and Technical Specifications to make them consistent with plant design and to be specific as to which channel and associated requirements are being addressed.
p
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Itecs Closed: (How)'
- u.-.-- .-. _.,
/
Date Time
References:
TSRT-84/0243 TSRT-84/0461 TSRT-84/0621 TSRT-84/0329 cc: J. E. Cross R. F. Rogers 9
~s .*
l 1
O Rev. 25, 4/16/84 Plsd64
s TECHNICAL SPECIPICATION PROBLEM SHEET l
Item Number: 256 Priority: 2E
/3-15-84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.7.4, Bases 3/4.7.4, Bases 3/4.5.1, and 3/4.5.2 :
Tech Spec Page: 3/4 7-13. B3/4 7-2, and B3/4 5-1 Problem
Title:
Generic Bases Problems , ,
I
Minor typographical errors were found and identified on pages 3/4 7-13 and B 3/4 7-2 of the GGNS Technical Specifications. Also, tha-values for high pressure core spray (HPCS) operating pressures were not revised in Bases 3/4.5.1 and 2 when those values were changed in Technical Specification 4.5.1 by Amendment 9.
- 2. Safety Significance:
None: These are minor typographical errors and inadvertent omissions which do affect plant safety or operational receirements.
- 3. Anticipated Resolution:
Propose a Technical Specification change to correct the typographical. error ca page 3/4 7-13 from "maintanence" to " maintenance" and page B3/4 7-2 from "enusre" to ensure." Also propose a change to correct the HPCS operating pressures in Bases 3/4.5.1 and 2 to be consistent with the values in Technical Specification 4.5.1 if necessary.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time O
.Rev. 25, 4/16/84 Pisd101
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 256 Priority: 2E
- 5. Disposition:
Items Closed: (How)
.e
/
Date Time
References:
TSRT-84/0143, Page 9 TSRT-84/0447, Pages 4 - 9 TSRT-84/0649 Page 11 TSRT-84/0651, Pages 12 and 13 TSRT-84/0554, Page 5 and 6 TSRT-84/0882, Page 1 cc: J. E. Cross R. F. Rogers
- l t
Rev.'25, 4/16/84 Pisd102
l TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 281 Priority: 2E Burgess / 3/14/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
5.3.1 Tech Spec Page: 5-5 Problem
Title:
Fuel Assemblies .
Technical Specification 5.3.1 lists the maximum average enrichments for the fuel assemblies in the initial core loading and in subsequent core reloads. l The values of enrichment in this Technical Specification are not consistent with the loaded core design. I l
- 2. Safety Significance:
None. The cycle analyses performed by the fuel vendor verify the existing core design to meet all 10 CFR 50 design criteria with adequate margin. These analyses were perforned using the core design data and not the. Technical O Specification 5.3.1 values.
- 3. Anticipated Resolution:
An evaluation of the fuel assemblies Technical Specification will be performed and appropriate Technical Specificatida revisions submitted as necessary. The core reload parameters may be addressed in the reload licensing submittal, l 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time l
l Rev. 25, 4/16/84 Plsd147 I
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 281 Priority: 2E
- 5. Disposition:
Items Closed: (Hov)
.A
/
Date Time
Reference:
TSRT-84/0738, Pages 1 - 5 TSRT-84/0233, Page 1 cc: J. E. Cross O- R. F. Rogers O
Rev. 25, 4/16/84 l
l Plsd147.1 1
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 299 Priority: 2B R. W. McNally / 3/16/84 R. C. Slovic Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.7.6.3 Tech Spec Page: 3/4 7-33, 7-34 Problem
Title:
CO, Storage Tank Level ,
GGNS Technical Specification 4.7.6.3.2.a requires at least a 50 percent level in the CO2 se rage tank. A Bechtel analysis concluded that the amount of CO 2
represented by this minimum level would not be sufficient to satisfy the design requirement for two system discharges to the largest room protected by the CO2 system and one purge of the main generator. This preliminary evaluation indicates that a minimum 60 percent level in the CO2 se rage tank would be necessary to meet the design requirements.
Technical Specification 3.7.6.3 contains two minor typographical errors in the O- list of areas having CO2 pr tacti n. The Auxiliary Building elevation should be revised from 139' 6" to 139' 0". The system number for the motor generator room should be revised from N1P64D214 to N1P64D2143. These corrections should be included in any Technical Specification changes resulting from the CO tank 2
- 1evel concern. *
- 2. Safety Significance:
The existing CO 2 se rage tank level requirement may not be sufficient to fulfill the design intent for the system.
The typographical errors do not involve a safety implication. The errors are minor and do not affect system performance.
- 3. Anticipated Resolution:
A review of the Bechtel analysis will be performed. If the results of this evaluation confirm the preliminary conclusions, a Technical Specification change will be proposed to reflect the corrected CO 'st rage tank minimum O level.
2 Rev. 25, 4/16/84 P1sd181
, l l
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number 299 Priority 2B 4 NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition: NPE concurs with correcting system number to N1P64D214B. (See TSRI-84/0079, PDTS-84/0061)
Items Closed: (How)
/
Date Time O
Reference:
TSRT-84/0521, Pages 2, 3, and 18 cc: J. E. Cross R. F. Rbgers ,
a o g #
O Rev. 25, 4/16/84 Plsd182 et
l l
l
\
I
't O TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 305 Priority: 2I
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4 (New Specification)
Tech Spec Page: N/A Problem
Title:
Potential For Pls nt Flooding From Probable Maximum ,
Precipitation
The evaluation for the local Probable Maximum Precipitation (PHP) on the plant area presented in the SER (Section 2.4.4) was based on a finished plant grade of elevation 132.5 feet mean sea level and a finished entrance floor level of 133.0 feet mean sea level. It was concluded that runoff from the local PHP would not exceed elevation 133.0 feet mean sea level in the plant area. It was subsequently determined that (1) finished plant grade on some areas (mainly parking areas) exceeded the 132.5 feet mean sea level, (2) some drainage svales in the main plant area had been filled in, (3) berms and O fencing for security might impede local runoff, and (4) security skirting on trailers parked in the main plant area would block flow and impede runoff from
, local intense storms. These changes from the original design condition might i
induce flood levels above the 133.0 feet mean sea level finished floor j elevation and cause flooding of safety-related equipment.
In order to ensure that proper flood protection is maintained, a new Grand Gulf Technical Specification has been proposed which is consistent with the BWR/6 Standard Technical Specifications, the provisions of which have been l approved by the NRC. However, BWR/6 Standard Technical Specification 3/4.7.3 states that 3/4.7.3 is not required if the facility design has adequate passive flood control protection features sufficient to accommodate the Design-Basis Plood identified in Regulatory Guide 1.59, August 1973.
- 2. Safety Significance:
The potential exists for PMP flood levels reaching above the 133.0 feet mean j sea level finished floor elevation. '
Rev. 25, 4/16/84 Pisd191
O Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 305 Priority: 21
- 3. Anticipated Resolution:
Perform an evaluation to determine the need for the new Technical ,
Specifiention addressing this issue. Submit the new Technical Specification, if deemed required.
/
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time Referenc&: TSRT-84/0928
- cc: J. E. Cross ,
R. F. Rogers O
Rev. 25, 4/16/84 Plsd192 * ' *N' ' # ' ' *"
- p. > ,,;yg .., } m 7 . _ y. _ n , ; ,. .. .. ; ., . . :. - _- . . :, .; , .- ;;-); : . g. e,
. . y, _ . y . . q. . y u.y_.. .
TECHNICAL SPECIFICATION PROBLEM SHEET O
Item Number: 328 Priority: 3B Dave Noonan / 3/13/84 J. Catlin l Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.7.5-1 Tech Spec Page: 3/4 3-70 Problem
Title:
Containment /Drywell Area Radiation Monitor Minimum Channels ,
Technical Specification Table 3.3.7.5-1 item 13 requires.'one minimum operable channel each for containment and drywell area monitors. However, GE Standard Technical Specifications (STS) Table 3.3.7.5-1, item 14 raquires two minimum operable channels each for containment and drywell area monitors and GGNS has cocnitted to having two channels operable. Also, the note at the bottom of Table 3.3.7.5-1 in the Standard Technical Specification indicates " secondary containment and drywell," whereas the corresponding GGNS note states containment and drywell." There is no Action Statement for item 13 for less O "than the Required Channels Action Operable.
81 does not include less than Required Channels Operable. .
l
- 2. Safety Significance:
None. The proposed change does not affect the probability of occurrence or the consequences of an accident or malfunction. The proposed change enhances the assurance that the system will perform its intended monitoring function.
- 3. Anticipated Resolution:
Perform an evaluation to determine if two channels are required. Verify that the note at the bottom of Technical Specification Table 3.3.7.5-1 is correct.
Submit Technical Specification changes, if necessary. Evaluate item 13 and Action Si to make them consistent.
O Rev. 25, 4/16/84 Pisd226
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O Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) .
Item Number: 328 t
Priority: 3B 4
{
NRC Response to Item .(NRR/IE). I I
NRC Notified:
/
Individual Notified Date Time
- 5. Disposition: __
-/
Items Closed: (How)
/
Data Time cc: J. E. Cross R. F. Rogers ..
O Rev. 25, 4/16/84 Plsd227
l TECHNICAL SPECIFICATION PROBLEM SHEET O
Item Number: 372 Priority: 2B S. Loeper / 4/16/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
Tables 3.3.2-1 Tech Spec Page: 3/4 3-10 Problem
Title:
Manual Initiation of Valve Group 6A ,
According to Isolation Actuation Instrumentation Technical Specification Table 3.3.2-1, valve group 6A receives a closure signal from/ manual initiation (item
. 1.h) of primary containment isolation. Eight valves in group 6A do not close from the manual initiation of primary containment isolation. These valves isolate chilled water to the drywell coolers (P44-F070, P44-F069, P44-F053, i
P44-F076, P44-F074 and P44-F077) and the auxiliary building floor and equipment drain tanks line to the suppression pool (P45-F273 and P45-F274).
l '
- 2. Safety Significance:
The accident analysis coes not take credit for the manual initiation functicn for primary containment isolation. Automatic isolation signals are assumed to provide the necessary isolation function. Emergency and off-normal procedures for the plant do not take credit for the manual initiation of primary containment isolation. Since the automatic isolation signals close all group 6A valves, the subject problem description is not safety significant.
However, Technical Specification Table 3.3.2-1 is currently misleading and can lead to mininterpretation as to which valves receive manual initiation isolation signals.
- 3. Anticipated Resolution:
Evaluate the problem to determine if a plant design change or Technical Specification change is required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time O Rev. 25, 4/16/84 Pisd283.4.3 n
Page 2
(
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 372 Priority: 2B
- 5. Disposition:
Items Closed: (How)
/
/
Date - T,ima ec: J. E. Cross {
R. F. Rogers O
4 l
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a O
Rev. 25, 4/16/84 Plsd283.4.4
TECHNICAL SPECIFICATION PROBI.EM SHEET Item Number: 826 Priority: 3B J. C. Cesare /
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.7.9; FSAR Section 9.1.3.4; SER Section 9.1.3 Tech Spec Page: 3/4 7-45; FSAR Page 9.1-17; SER Page 9-4
' Problem
Title:
SER/ Periodic Operation of Spare Fuel Pool Cooling Pump
Technical Specification 3.7.9 requires that the spent fuel storage pool be maintained at less than or equal to 150*F, but does nog explicitly address operability requirements for system components. Operability is discussed in Section 9.1.3.4 of the FSAR, which states that the " spare" system components (i.e. , the pump, heat exchanger, and filter-demineralizer) are operated periodically to handle abnormal heat loads or to allow the normal components I
to be serviced.
Section 9.1.3 of the Safety Evaluation Report (SERF presently states that the spare pump will be cpera:ed pariedi: ally in accordance *eith plant Technical Specifications. As stated above, the Technical Specifications do not l explicitly require the spare pump to be operated periodically; therefore, the SER is not consistent with respect to its reference to the Technical Specifications. The SER may need to be revised to state that the spara pump will be operated periodically in accordance with the FSAR.
- 2. Safety Significance:
Not applicable.
- 3. Anticipated Resolution:
Investigate the need to request a change to the SER in an SER supplement to correctly address the periodic operation of the spara fuel pool cooling pump.
- 4. NRC Response to Item (NRR/IE):
j NRC Notified: /
Individual Notified Date Time i
Rev. 25, 4/16/84 l Pisd317.1 l- _ _ - - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ . _, n.
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 826 Priority: 3B l
- 5. Disposition:
l Items Closed: (Hov)
'f
/
Date Time
Reference:
LCTS Item Number 198 TSRT-84/0102 cc: J. E. Cross -
R. F. Regers - -- - -- - - - - -
O Rev. 25, 4/16/84 Plsd317.2
I O
\
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 827 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.7.6.1, FSAR 9.5.1.2.1 Tech Spec Page: 3/4 7-28 .
Problem
Title:
Firewater Storage Tank Automatic Level Makeup
FSAR 9.5.1.2.1 states that automatic makeup to the storage tank occurs at 18" i below the overflow pipe. The actual makeup point is 457 below the overflow pipe. FSAR also states the system is maintained at 125 psig vs. Technical Specification 120 psig.
- 2. Safety Significance:
None. The actual makeup point provides adequate water volume in the fire storage tanks. The water of 120 psig is adequate as only 118 psig is required for =axi=um 2717 gpm for sprinkler flow plus 1000 gpm for hose strains.
O
- 3. Anticipated Resolution:
Review FSAR 9.5.1.2.1 to reflect the proper level of 45". Revise FSAR 9.5.1.2.1 and 9.5.1.2.2.1 to reflect 120 psig.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (Hov)
/
Data Time cc: J. E. Cross '
R. F. Rogers Rev. 25, 4/16/84 Plsd318
_ - _ _ - - - _ _ _ _ _ _ - _ _ _ n
i
)
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 828 Priority: 3B S. M. Faith /
i Identified By Date Responsible Supervisor 4
Tech Spec
Reference:
3/4.3.5; FSAR Section 7.4.1.1 Tech Spec Page: 3/4 3-44 through 3-49: FSAR Pages 7.4-3 & 7.4-5 Problem
Title:
FSAR/RCIC Actuation on Reactor Low-Water Level .
FSAR Sections 7.4.1.1.3.2 and 7.4.1.1.3.5 indicate that the reactor core isolation cooling (RCIC) system is actuated by a reactor/ low-water level signal. This is different that the title for the functional unit in Technical Specification Tables 3.3.5-1, 3.3.5-2, and 4.3.5.1-1 which indicate that RCIC is actuated by the reactor vessel water level-low low, Level 2 signal.
- 2. Safety Significance:
j Not applicable.
- 3. Anticipated Resolution:
Review the discussions contained in FSAR Sections 7.4.1.1.3.2 and 7.4.1.1.3.5 with respect to the need to indicate the title for the functional unit that actuates RCIC. If necessary, include the appropriate changes in the next annual FSAR update per 10 CPR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time l
O Rev. 25, 4/16/84 l
l l Pisd319 i I
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 828 Priority: 3B
- 5. Disposition:
Items Closed: (How)
/
/
Date Time
Reference:
TSRT-84/0903, Item 3 cc: J. E. Cross R. F. Regers O- Rev. 25, 4/16/84 O .
1 P1sd320
_ _ _ _ _ _ _ - - _ - - - - - _ _ _ n.
l TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 829 Priority: 3B S. M. Faith / 4/4/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.4.4; FSAR Table 5.2-6 l
Tech Spec Page: 3/4 4-11, 4-12 and 4-13 Problem
Title:
FSAR/ Reactor Coolant System Chemistry Requirements .
- a. FSAR Table 5.2-6 (Coolant Chemistry Requirements) requires thr.t the reactorbeshutdownifthepHisoutoflimitsforM4 hours. However, Technical Specification 3.4.4.a.2 allows the pH to be out of limits for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before taking action.
- b. FSAR Table 5.2-6 requires checking the continuous conductivity monitor with an in-line flow cell once a week and performance of an in-line conductivity calibration every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> whenever the reactor coolant conductivity is 1.0 umho/cm at 25'C. Technical Specification Surveillance Requirement 4.4.4.d requires the performance of a channel check of the continuous conductivity monitor with an in-line flow cell at least once per 7 days and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> whenever conductivity is greater than the limit in Technical Specification Table 3.4.4-1.
- 2. Safety Significance:
Not applicable.
m
- 3. Anticipated Resolution:
Evaluate the need to revise FSAR Table 5.2-6 and, if necessary, include appropriate changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE): . ..
NRC Notified: /
Individual Notified Date Time O
Rev. 25, 4/16/84 Plsd321
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 829 Priority: 3B
- 5. Disposition:
Items Closed: (How)
./
/
Date Time cc: J. E. Cross R. F. Rogers l
l l
I .
Rev. 25, 4/16/84 i
Plsd322
l l l
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TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 830 Priority: 3B ,
1
/ l Identified By Date Responsible Supervisor Tech Spec
Reference:
3.4.1.4; FSAR Section 5.3.3.6 Tech Spec Page: 3/4 4-4; FSAR Page 5.3-21 Problem
Title:
FSAR/ Temperature Difference Between Dome and Bottom Head-Drain a
FSAR Section 5.3.3.6 states that if the coolant temperature difference between the dome and the bottom head drain exceeds 145'F, neithd reactor power level nor recirculation pump flow shall be increased. This temperature limit value is for BWR 4/5 plants and is incorrect for BWR/6 plants. The correct value for BWR/6 plants in 100*F as specified in Technical Specification 3.4.1.4.
- 2. Safety Significance:
Not applicable.
- 3. Anticipated Resolution:
Revise the temperature limit value identified in FSAR Section 5.3.3.6 in the next annual FSAR update per 10 CFR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time ec: J. E. Cross
! R. F. Rogers l
Rev. 25, 4/16/84 l
Pisd323 o
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 831 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.1-2; FSAR Table 7.2-5 Tech Spec Page: 3/4 3-6; FSAR Table 7.2-5 Problem
Title:
FSAR/RPS Response Times .
FSAR Table 7.2-5, RPS time response (design), gives incorrect response times forthereactorvessellowwaterlevel,thereactorvesd1highwaterlevel, the turbine stop valve closure, and the turbine control valve fast closure functions. Technical Specification Table 3.3.1-2 identifies the correct response times which are in agreement with GE Design Specification 22A3771AE, as supplemented by letter number MPGE-82/077.
- 2. Safety Significance:
Not applicable.
- 3. Anticipated Resolution:
Review FSAR Table 7.2-5 with respect to the response times identified in Technical Specification Table 3.3.1-2 and, if necessary, include appropriate changes in the next annual FSAR update per 10 CFR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
- Date Time ;
cc: J. E. Cross '
R. F. Rogers Rev. 25, 4/16/84 PIsd324
S i
j i
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 832 Priority: 3B C. D. Stafford / 3/17/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.6.6.3; FSAR Section 7.3.1.1.8.2 Tech Spec Page: 3/4 6-53: FSAR Page 7.3-67 Problem
Title:
FSAR/ Incorrect Description of SGTS Logic g
FSAR Section 7.3.1.1.8.2 is incorrect in stating that any manual or automatic initiation signal starts both trains of the standby gas Ireatment system (SGTS). The logic for the SGTS is divisional and will only start its associated SGTS train. The system design and Technical Specification 3.6.6.3 are consistent with divisional separation criteria.
- 2. Safety Significance:
Not applicable.
- 3. Anticipated Resolution
Revise FSAR to reflect correct as-built configuration of the SGTS logic in the
! next annual FSAR update per 10 CTR 50.71(e)(4).
- 4. NRC Response to Item (NRR/IE): ,
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
i i
Date Time ;
i I
cc: J. E. Cross ;
!' R. F. Rogers Rev. 25, 4/16/84 I l
Pisd325
. n
" TECH SPEC PRIORITY" MEMO TO: Tech Spec Review Personnel PROM: C. L. Tyrone
SUBJECT:
Rev. M to Technical Specification Problem Sheet TSRT: 84/ C) St\
DATE: hdd\ 1% %4)-\
The following changes / additions are to be incorporated into the Tech Spec Problem Sheets:
ITDi NUMBER CRANGES/ ADDITION OGA Remove Rev. \T. Insert Rev.1\D D \ %. O US) Remove Rev.\e,. Insert Rev. 11.
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9
. g v3 C. L. Tyrone s
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Attachment ec: S. E. Hobbs (w/D SFile (Tech Spec hcords) (w/1)
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cc: S. H. Hobbs (w/1)
O- File (Tech Spec Records) (w/1)
M2sd2
s
. TSRT-84/0%bk-l i
O PROBLEM SHEET LISTING AS OF April 25, 1984 Dace ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 001 1 1B 15, 3/29/84 I 2D 26, 4/24/84 002 I 2D 17, 4/01/84 l 003 I 2E 22, 4/C9/34 C04 I 1B 15, 3/29/84 005 ,
I 2D 21, 4/08/84 006 007 I 2F 15, 3/29/84 008 I 2H 17, 4/01/84 009 I 2B 25, 4/16/84 010 I 2B 15, 3/29/84 1 2B 15, 3/29/84 011 012 I 23 26, 4/24/84 013 I 2D 26, 4/24/84 014 I 23 21, 4/08/84 17, 4/01/80 0 013 I 13 07 I 2D k5 3/29/84 018 I 3B 15, 3/29/84 019 I 25 25, 4/16/84 020 I 2B 17, 4/01/84 021 1 1C 15, 3/29/84 022 1 1A 17, 4/01/84 023 I 2B 15, 3/29/84 I 2B 18, 4/02/84 024 025 I 3B 26, 4/24/84 I 2D 15, 3/29/84 026 ,
15, 3/29/84 -
027 I 2E 028 I 2B 15, 3/29/84 029 I 35 26, 4/24/84 030 1 2D 17, 4/01/84 031- I 2D 17, 4/01/84 032 1 25 21, 4/08/84 0, 033 I IB ' 18, 4/02/84 18, 4/02/84 034 1 1C I 2C 15, 3/29/84 035 L26sd1
i FROBLDi SHEET LISTING ITEM NUMBER REVIEk'ED BY RPD PRIORITY REVISION, DATE l
036 I 2D 26, 4/24/84 037 I 1C 15, 3/29/84 038 I 1C 15, 3/29/84 ;
} 039 I 2G 17, 4/01/84 -
l 040 X 2F 17, 4/01/84 !
041 X 2B 21, 4/08/84
! 042 X 33 26, 4/24/84 043 X 2D 15, 3/29/84 044 X 2B 26, 4/24/84 045 I 2B 17, 4/01/84 046 X 2F 15, 3/29/84 047 I 2B 15, 3/29/84 048 X 2H 15, 3/29/84 049 X 2B 18, 4/02/84 050 X 2B 17, 4/01/84 051 -
X 2D 15, 3/29/84 052 X 2E 15, 3/29/84 O =
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PROB 1JDi SHEET LISTING .
ITEM NUMBER REVIEWED BT RPD PRIORITT REVISION, DATE 073 X 2B 18, 4/02/84
! 074 I 2D 17, 4/01/84 075 I 2B 17, 4/01/84 076 I 13 18, 4/02/84
! 077 I 2B 21, 4/08/84 078 I l'B 15, 3/29/84 079 -
X 2E 15, 3/29/54 080 I N/A (Resolved) 15, 3/29/84 l
081 X 3A 15, 3/29/84 082 I 3A 15, 3/29/84 083 I 2B 22, 4/09/84 084 I 3A 15, 3/29/84 085 1 2D 20, 4/06/84 086 I 2D 18, 4/02/84 l 087 I 2D 17, 4/01/84 088 I 2D 17, 4/01/84 l 089 I 2D 15, 3/29/84 090 X 20 1 . a/01/34
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101 X 2E 15, 3/29/94 102 X 23 15, 3/29/84 103 I IB 18, 4/02/84 104 I 2E 17, 4/01/84 105 I 2E 25, 4/16/84 106 I 2E 25, 4/16/84 l
-M7 I 2E 18, 4/02/84 v) 108 I 2C 15, 3/29/84 l 109 I 2D -M, S/29/84 L26ed3
FROBLEM SHEET LISTING REVISION, DATE ITDi NUMBER REVIEWED BT RPD PRIORITY 2B 17, 4/01/84
! 4110 X 2D 18, 4/02/84 111 X 2A 15, 3/29/84 112 X N/A (Resolved) 15, 3/29/84 113 I 2B 18, 4/02/84
- 114 X 2D 17, 4/01/84 115 X 15, 3/29/34 116 X 2B N/A (Resolved) 18, 4/02/84 -
117 I l 16, 3/31/84 I 2D l 118 2B 15, 3/29/84 119 X 25 25, 4/16/84 120 X N/A (Resolved) 15, 3/29/84 -
121 X 2D 17, 4/01/84 122 X 2D 18, 4/02/84 123 X 2c 18, 4/02/84 124 X X N/A (Resolved) 18, 4/02/84 -
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' 15, 3/29/84 X 2B 137 i 2D 15, 3/29/84 ,
138 X IC 15, 3/29/84 ;
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PROBLDi SHEET LISTING REVIEWED BY RPD PRIORITY REVISION, DATE ITEM NUMBER l
16, 3/31/84
( 147 I 3B 17, 4/01/84 148 I 3A I 3B 18, 4/02/84 149 I 2G 17, 4/01/84 150 I 33 25, 4/16/84 151 I 2E 16, 3/31/84 152 I OE 17, 4/01/64 153 I 2D 16, 3/31/84 154 I 2D 18, 4/02/84 155 I 2D 17, 4/01/84 156 157 I 2D 17, 4/01/84 158 I 2D - 17, 4/01/84 I 2D 16, 3/31/84 159
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- 65 . _0 17, ,Gili-I 2H 26, 4/24/84 166 167 I 2B 17, 4/01/84 I 2B 21, 4/08/84 168 I 2D 18, 4/02/84 169 170 1 2E 16, 3/31/84 171 I 2D 16, 3/31/84 I 2B 17, 4/01/84 172 I 2D 21, 4/08/84 173 I' 2E 17, 4/01/84 174 I 3B 21, 4/0*/S4 175 I 2B 17, 4/01/84 176 177 I 2D 25, 4/16/84 178 I 2D 17, 4/01/84 179 I 2D 16, 3/31/84 I 2A 17, 4/01/84 180 181 I 2A 26, 4/24/84 l ( j 1E2 I 2D 17, 4/01/84 18, 4/02/84 183 I 2D L26sd5 One O M
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PROBLEM SHEET LISTING ITDi NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
! O 184 I 2D 16, 3/31/84 185 I 2B 18, 4/02/84 j j
186 I N/A (Resolved) 18, 4/02/84 187 I 2G - 18, 4/02/84 188 I 3B (Resolved) 15, 3/29/84 189 I 2H 18, 4/02/84 190 I 2D 20, 4/06/84 l 191 I 2D 18, 4/02/84 192 1 2D 16, 3/31/84 193 I 2D 16, 3/31/84 194 I 2D 18, 4/02/84
- 195 1 2D 26, 4/24/84 196 I 2B 16, 3/31/84 197 I 2B 26, 4/24/84 198 I 1C 16, 3/31/84 199 I 3B 18, 4/02/84 200 X 2G 18, 4/02/84 O
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202 X
I 23 22, -/Ch Ji 18, 4/02/84 3B 203 I 2D 22, 4/09/84 204 I 2H 18, 4/02/84 205 I 2H 16, 3/31/84 206 I 2G 16, 3/31/84
! 207 I 2H 18, 4/02/84 208 I 2H 18, 4/02/84 209 I 2H 15, 3/29/84 210 I 2G 18, 4/02/84 211 I 3B 26, 4/24/84 212 X 2D 18, 4/02/34 213 1 1C 16, 3/31/84 214 1 35 21, 4/08/84 l
i 215 I 35 16, 3/31/84 216 I 3B 18, 4/02/84 217 I 3B 21, 4/08/84 218 I 25 26, 4/24/84 219 I 2I 16, 3/31/84 I 220 I 3A 18, 4/02/84 L26sd6
PROBLEM SHEET LISTING ITEM NUMBER REVIEVED BY RPD PRIORITY REVISION, DATE 221 I 2D 16, 3/31/84 222 1 3B 26, 4/24/84 223 1 2B 18, 4/02/84 224 I 3B 16, 3/31/84 225 I 2D 25, 4/16/84 226- I 3A 18, 4/02/84 227 I 3B 21, 4/08/84 228 I 3B 26, 4/24/84 229 I 2B 21, 4/08/84 230 I 2B (Resolved) 15, 3/29/84 231 I 3B 17, 4/01/84 232 I 3B 17, 4/D1/84 233 I 2E 25, 4/16/84 234 I 3A 25, 4/16/84 23' I' 2B 18, 4/02/84 236 I 2B 17, 4/01/84 237 I 2D 18, 4/02/84
_ 223 _ __
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'. 5 , e ,' 51, 31 239 I 2D 18, 4/02/S4 240 I 2D 17, 4/01/84 241 I 2D 26, 4/24/84 242 I 3B 18, 4/02/84 243 I 33 18, 4/02/84 244' I 2B 18, 4/02/84 245 1 2B 17, 4/01/84 246 I 2B 18, 4/02/84 247 I 2B 18, 4/02/84 248 I 2D 18, 4/02/84 249 I 2D 22, 4/09/S4 250 X 2B 18, 4/02/84 . . -
251 I 2F 18, 4/02/84 252 I *3B 18, 4/02/84 253 I 2C 18, 4/02/84 254 I 3B 18, 4/02/84 O./
- Priority changed from 1A per J. C. Roberts 3/27/84.
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FROBLEM SHIET LISTING PRIORITY REVISION, DATE ITEM NUMBER REVIEWED BY RPD I 2E 18, 4/02/84 255 I 2E 25, 4/16/84 256 I Sub. 2E 18, 4/02/84 256-1 I 2B 17, 4/01/84 257 _
I 33 18, 4/02/84 ,
258 I 3B . 26, 4/24/84 259 3B 18, 4/02/84 260 I 3A 18, 4/02/84 261 I 1 1C 16, 3/31/84 262 263 1 2D 17, 4/01/84 I 2B 17, 4/01/84 264 265 1 2D 18, 4/02/84 266 1 2B 17, 4/01/84 267 1 23 18, 4/02/84 268 I 2F 18, 4/02/84 269 ' I 2D 18, 4/02/84 270 1 2E 22, 4/09/84
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- 6 , . ' 2 !. / 3 :. ,
1 2D 22, 4/09/84 272 I 3B 26, 4/24/84 273 274 I 2D 18, 4/02/84_
275 I 23 18, 4/02/84 I 2D 18, 4/02/84 276 I 25 18, 4/02/84 277 27S I 2D 18, 4/02/84 279 I 2D 17, 4/01/84 280 1 2D 18, 4/02/84 1 2E 25, 4/16/84 281 1 2E 17, 4/01/84 292 283 1 2E 17, 4/01/84 1 3B 26, 4/24/84 284 285 1 1C 18, 4/02/84 286 1 2D 18, 4/02/84 I 2D 18, 4/02/84 287 288 1 2D 18, 4/02/84 1 2E 18, 4/02/84
) 289 290 1 2E 18, 4/02/84 L26sd8
PROBLEM SHIET LISTING REVIEWED BT RPD PRIORITY REVISION, DATE l ITEM NUMBER I *3B 18, 4/02/84 291 4
292 I 1B 18, 4/02/84 293 x 13 18,' 4/02/84 I 23 18, 4/02/84 294 '
I 3B 26, 4/24/84 295 I 3B 26, 4/24/84 296 I 2E 26, 4/24/84 297 I 2E 18, 4/02/84 -
j 298 I 2B 25, 4/16/84 299 300 1 3A 18, 4/02/84 ,
301 1 2E 18, 4/02/84 j 302 1 2D 26, 4/24/84 303 1 23 18, 4/02/84 304 I 2D 21, 4/08/84 j
305 I 33 26, 4/24/84 t'
I 1B 26, 4/24/84 306 <
307 I 2B 18, 4/02/84 Ke :: '. 3 1 . :. : ' i '-
309 X 2A is , e, G2; d.,
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- j. 310 1 2A 18, 4/02/84 311 1 2E 18, 4/02/84 j
4 312 I 2B 22, 4/09/84 1 2B 18, 4/02/84 313 314 I 2B 18, 4/02/84 l .
315 1 2B 18, 4/02/84 316 I 2I 26, 4/24/84 ,
317 I 2E 18, 4/02/84 l
I 33 18, 4/02/84 f 318 319 I 2E 21, 4/08/84 1 2E 18, 4/02/C4 i 320 321 I 35 26, 4/24/84 i 322 I 2E 18, 4/02/84
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! 324 1 2E 18, 4/02/84 325 I 35 26, 4/24/84 l
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- Priority changed from 1A per J. C. Roberts 3/27/84.
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PROBLDi SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 326 I 3B 26, 4/24/84 i 327 I 35 18, 4/02/84 328 I 2D 26, 4/24/84 329 I 1C . 18, 4/02/84
. 330 I 3B 26, 4/24/84 i 331 I 3B 26, 4/24/84 )
332 1 3B 21, 4/08/84 !
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333 I 3B 26, 4/24/84 334 I 2D 18, 4/02/84 335 I 2B 18, 4/02/84 336 I 2D 18, 4/02/84 :
337 I 2D 18, 4/02/84 338 I 2B 18, s/02/84 339 I 3B 26, 4/24/84 340 I 3B 26, 4/24/84 341 "' I 3B 18, 4/02/84
- 342 I 2B 19, 4/05/84 1 33 "
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- 344
- : 13 19, 4/05/84 345 I 2B 21, 4/08/84 346 I 2D 26, 4/24/84 347 I 2B 21, 4/08/84 348 I 2D 26, 4/24/84 349 I 2D 21, 4/08/84 350 'I 25 21, 4/08/84 1
351 1 2D 21, 4/08/84 352 I 2D 21, 4/08/84 1 353 I 2D 21, 4/08/84 )
l 354 I 2D 21, 4/08/84 ,
355 1 2D 21, 4/08/84 ,
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356 I 2D 21, 4/08/84 l 357 I 2B 21, 4/08/84 j 358 I 2D 21, 4/08/84 359 I 23 21, 4/08/84 i 360 X 23 21, 4/08/84 361 1 2D 21, 4/08/84 362 I 2B 26, 4/24/84 l
363 I 2D 21, 4/08/84 l
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PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 364 I 23 21, 4/08/84 365 I 2D 24, 4/13/84 366 1 2D 24, 4/13/84 j
367 I 2D (Resolved) 26, 4/24/84 368 I 3B (Resolved) 26, 4/24/84 i 369 I 2D 26, 4/24/84 i
370 I 3A 24, 4/13/84 371 I 2D 24, 4/13/84 372 1 35 26, 4/24/84 800 1 3B 18, 4/02/84 801 I 3B 18, 4/02/84
) 802 I 3B 18, 4/02/84 803 I 35 18, 4/02/84 804 I 3B 18, 4/02/84 805 < I 3B 24, 3/13/84 l
806 I 3B 18, 4/02/84 l *-- "
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j 203 I 33 13, 4/02 3 809 I 3B 18, 4/02/84 810 I 3B 18, 4/02/84 i 811 I 38 18, 4/02/84 812 I 35 23, 4/10/84 813 I 35 22, 4/09/84 l
814 I 35 22, 4/09/84 815 I 3B 22, 4/09/84 816 I 3B 23, 4/10/84 l l
817 I 3B 23, 4/10/84 813 I 3B 23, 4/10/34 819 I 3B 23, 4/10/84 820 1 33 23, 4/10/84 821 I 35 24, 4/13/84 1 38 24, 4/13/84 j 822 823 1 3B 24, 4/13/84 l
824 I 35 24, 4/13/84 l I 38 24, 4/13/84 s 825 1 L26sd11 1
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PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BT RPD PRIORITY REVISION, DATE O 826 I 3B 25, 4/16/84 827 I 3B 25, 4/16/84 828 I 3B 25, 4/16/84 829 I 3B 25, 4/16/84 830 X 3B 25, 4/16/84 831 X 3B 25, 4/16/84 832 X 3B 25, 4/16/84 O . - . .- - .. _ .. . . - - = . . ._ . - _-- .. .._
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TECHNICAL SPECIFICATION PROBLEM SHEET _
Item Number: 002 Priority: 2D I
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.7.1.2 Tech Spec Page: 3/4 7-3 Problem
Title:
HPCS Service Water Operability, Typographical Error
The footnote (*), involving Operational Conditions 4 and 5, has the acronym "HPSCS" instead of "HPCS."
l 4
l 2. Safety Significance:
None: Typographical error.
l l ,
3." Anticipated Resolution: ,
j Propose a Technical Specification change to correct the typographical error.
4 NRC Response to I:a= (57.R/IE):
NRC Notified:
/
Individual Notified Date Time l1f 5. Disposition:
1 j Items Closed: (How) l J
1 /
Date Time i
cc J. E. Cross , , ,
R. F. Rogers l 0 l
Rev. 26, 4/24/84 Misd3 N ma 3
_ - - - _ - " e_ _--- %M- _ , - - - -ah. h_
i l
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 012 Priority: 2B
/ 1 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.6.3.2 and 3.6.3.3 Tech Spec Page: 3/4 6-24 and 25 Problem
Title:
Typograehical Error Referring to SSW Heat Exchanger
l a. Technical Specifications 3.6.3.2.b (containment spray) and 3.6.3.3.b (suppression pool cooling) require an operable flow path for containment spray and suppression pool cooling through an "SSW. heat exchanger." This is not the correct component, and should be changed to "RER heat exchanger."
! b. The footnotes on pages 3/4 6-24 and 25 states, "Whenever both RER
( subsystems are inoperable . . .", but should read "Whenever both RER shutdown cooling subsystems are inoperable . . .".
l
- c. A: tion 5:7.:ena . i. :: Technical Specificatien 3.6.3.3 centains the j '
s tater.ent , " . . . rascora at least one loop to operable status w:.:. :.: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or . . .". However, the GE Standard Technical Specification does not contain this statement. Also, Action Statement a.' specifies 7 days to restore one inoperable loop. but the GE-STS specifies 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 2. Safety Significance:
l
- a. None. This change corrects the component name and is consistent with i
terminology used in Surveillance Requirements 4.6.3.2.b and 4.6.3.3.b.
- b. None. The current footnotes may be confusing since cold shutdown can be !
attained with one shutdown cooling loop. Therefore, the footnotes would not be necessary unless both shutdown cooling loops were inoperable.
- c. The proposed change is more conservative than present Technical l
Specifications but has not been substantiated.
i 3. Anticipated Resolution:
Perform an evaluatton to determine the necessity for making the above changes.
l %
)
Rev. 26, 4/24/84 Misd19
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i Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) i Item Number: 012 l'riority: 2B
- 4. NRC Response to Item (NRR/IE):
I NRC Notified: / -
i
< Individual Notified Date Time
- 5. Disposition:
i r
i' Items Closed: (How) t t
i
/
Date Time u
?..i n t .a : !!?.!: 2 *.10' 3, ;4;;e 10 .
TSRT: as/0157, pages 12 through 17 1 cc: J. E. Cross 1
R. F. Rogers 1
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, tav. 26, 4/24/84 i
- Misd20
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, _ . _--. ,---_., .. l___,._, .O._ ,_,..m __-_..-_m----.,- - - , . _ - . - . .
I l
(/ TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 013 Priority: 2D
. /
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.2-1 Tech Spec Page: 3/4 3-10 .
Problen
Title:
High Radiation MSIV Isalation Terminology
- a. Table 3.3.2-1 " Isolation Actuation Instrumentation " indicates main steam isolation valva (MSIV) closure as a result of a main steam line (MSL) high radiation signal. MSIV closure also occurs, however, upon receipt
'of an MSL low radiation signal indication of a sensor failure (reference TSAR 7.3.1.1.2.4.1.2.3). The NSL low radiation signal is not listed in Table 3.3.2-1 as an MSIV closure signal. This situation is one example of's generic situation wherein the various instrument trip' function tables in the Technical Specifications do not necessarily list all
, ='I-='S - :M ing,_fre indica:ed tri: functien. _ ,_ _
- b. The NRC, Division of Project and Residenc Prograns, has identifiad caac four valves of the combustible gas control system (E61-F009, F010, T056, 7057) receive Group 5 isolation signals and that clarifying notes should be placed in the specification or in Table 3.3.2-1. .
- c. Refer to anticipated resolution item "c".
- 2. Safety Significance:
- a. None. The unlisted signals which also result in the trip functions identified in the various instrument trip function tables are not safety significant. These unlisted signals are not necessary to initiate actions to nitigate the ccusequences of accidents and, as such, should e not be listed in the Technical Specification
- b. None. Preliminary investigations revealed that the four valves received Group 7 isolation signals which is reflected in Technical Specification Table 3.6.4-1.
O d
Rev. 26, 4/24/84 Misd21
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as_~'
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! TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) i Ites Number: 013 Priority: 23 1
i
- 3. Anticipated Resolution
l a. Evaluate the impcrtance of those signals not currently listed in the
- Technical Specification instrumentation trip function tables (e.g., Table 3.3.2-1) and confirm that these signals are not necessary to initiate I actions to mitigate the consequences of accidents.
t
- b. Evaluate the isoletion signals to the four valves identified in the
- problem description and confirm that Technical Specification changes are j not necessary.
- c. Evaluate the need to add testing auxiliary building and containment
] isolation signal upon depressing respective divisional ECCS manual initia:4 ;ushiu:t:ss.
I 1
! 4. NRC Response to Item (NRR/IE):
1 NRC Notified: /
Individual Notified Date Time
- 5. Dispositions l
t Items Closed (Hov) i i /
j Date Time i
I
References:
TSRT-84/0344 NRC/NER Second Proof and Review Comments, Page 10 of letter from Richard C. Lewis to Dattell G. Eisenhut, dated February 9, 1984 cc: J. E. Cross
/ 1. F. Rogers Rev. 26, 4/24/84 Misd22
. . . . . . _ _ . . . _ _ _ _ . _ _ . . . - . . . . . . - . _ _ _ _ _ , . . , . . _ . _ . _ . _ _ . _ _ . . . _ . _ _ ~ . . - . . _ . _ . -. .- _ _ . _ - . . . . - _ . . , . . . . . . -, . - - .
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 025 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.4.7 ;
Tech Spec Page: 3/a 4-22 Probles
Title:
MSIV Mini =un Closine Stroke Ti=e
Technical Specification 3.4.7 requires that two main steam line isolation valves CMSIVs) per main steam line be operable with closing times greater than or equal to 3 seconds and less than or equal to 5 seconds. The 3-second closing time is inconsistent with the NSSS vendor design specification which is reflected in the Level 1 Acceptance Criteria of the Startup Test Program (FSAR Section 14.2.12.3.22). This section of the FSAR states that:
a "MSIV closure time, exclusive of electrical delay, shall be no faster than 3.0 3:::nds (ararage :f tha f.=.stss: relre in 4::h s:a*- line;. T .*
. . . ~ . . . . - . . = - .
time between tee isolatics trip signal and valve full cicaec dusE'ea 5.0
~
seconds or less for each valve. The electrical time delay at 100 pe~rcent open shall be less than or equal to 0.5 seconds, and the fastest valve closure time shall be greater than or equal to 2.5 seconds."
FSAR Section 15.2.4 states that the MSIVs close in 3 to 5 seconds and that the 3-second closure time is assumed in the transient analysis for the closure of all MSIVs events. The transient analysis assumptions for MSIV closure times are also based on the NSSS vendor design specifications which are more explicitly defined in TSAR Section 14.2.12.3.22, Level 1 Acceptance Critera.
t I
- 2. Safety Significance:
None. The present Technical Specification closure time limits are more conservative than the NSSS vendor design specifications and FSAR analysis assumptions. Changes to the Technical Specification limits would provide consistency and provide more margin in MSIV closure times.
(O/J Rev. 26, 4/24/84 Misd44
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Page 2 TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D)
. l 4
i .
i Iten Number: 025 Priority: 33 l
t
- 3. Antic'ipated Resolution:
j Perform an evaluation of the MSIV closure time requirements to determine whether the present Technical Specification 3/4.4.7 should be changed to
) reflect the methodology presented in FSAR Section 14.2.12.3.22.
l 4. NRC Response to Item (NRR/II):
4 NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
]
]
- :ars O*: sed: +H:s' 1
l .
l Date Time i
Reference:
TSIT-84/0035 4
! cc J. E. Cross l R. F. Rogers i
j ,.
i I
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J i Rev. 26, 4/24/84 p
Misd45 l ... . . . . . .
N TICHNICAL SPECIFICATION PROBLEM SHEET Item Number: 029 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 4.3.6-1 Tech Spe: Paga: 3/* 2-52 and 3/1 3-31 Problem
Title:
Changing Mode Switch Neutron Monitoring Instrumentation Test
Technical Specification Table 4.3.6-1 lists the control rod block instrumentation surveillance requirements for the neutron monitoring system in
) Operational Conditions 1, 2, and 5. Technical Specification 4.3.7.6.b requires a channel functional test of the source range monitors (SRMs) prior to moving the reactor mode switch out of SHUTDOWN. The surveillance procedures for neutron monitoring system channel functional test require the reactor, mode switch to be placed in REFUEL. Following discussions with the GCNS NRC Resident Inspector and NRC Region II, an interim measure was est:bli:hei te pernit placir.g the rea:ter --f a svitch in ?I?'!!'. f-- -he !?M
~
'-h:nts* ITEIEic:al cast until a fi s' .i..*u:1:n .:u*; '.. is;1._c.....
- 2. Safety Significance None. The interim administrative control did not compromise plant safety in that the reactor mede switch was placed conditionally in REFUEL for performance of the SRM channel functional test. The design intent of Technical Specification 4.3.7.6.b was satisfied. .
- 3. Anticipated Resolution:
An interim administrative control reviewed by the Commission was implemented to allow the SRM channel functional test to be performed using existing surveillance procedures. GE has identified an alternate surveillance nethod for the neutron monitoring system which is independent of reactor mode switch position. An evaluation of this method has been completed and appropriate surveillance procedure revisions are being prepared. The alternate surveillance method will remove the need for the interim administrative control.
x ;
Rev. 26, 4/24/84 Misd50
. _ . = ,
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, t i TECENICM. SPECIFICATION FRCBLEM SHEET (CONT'D)
I
- k. .
35 Item Number: 029 Priority:
i i
I I 4 NRC Response to Item (NRR/IE):
NRC Notified: / .'
Individual Notified Date Time
- 5. Disposition:
l Items Closed: (How)
I j / '
' Date Time cct J. E. Cross
?.. F. h ia:7 _ . . . _ _ . . _
i i.
4 I
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Rev. 26, 4/24/84 Misd51
I
, I i l l l TECHNICAL SPECIFICATION PROBLEM SHEET
- Item Number
- 036 Priority: 2D
! /
j Identified By Date Responsible Supervisor
} Tech Spec
Reference:
3/4.12 l Tech Spec Page: 3/4 12-1 through 3/4 12-12. B 3/4 12-1, 6-19, and 6-25 1
i Problem
Title:
Environ = ental Monitoring Specifications ,
The Radiological Environmental Monitoring requirements contained in Technical
)
Specification 3/4.12 are inconsistent. The environmental monitoring section j should be revised to correct typographical errors, eliminate inconsistencies, 1
and ensure compliance with the appropriate regulations.
i l Specific typographical errors and inconsistencies for the Radiological l Environmental Monitoring Program requirements include the foll'oving:
l 1. Superscript "c" which describes the neaning for the ter:: "ga=a isotepic a:La 2. .I . '.-1 ta s ':s ei :.: de "Tyne sind Ire:uency c:
n-al s.s" :
Analysis" colunn entry on pages 3/4 12-3, but was omitted in the applicable entries on pages 3/4 12-4 and 3/4 12-5.
- 2. Entries in the " Type and Frequency of Analysis" column of Table 3.12.1-1 have been omitted for the last two items concerning food products on page 1 3/4 12-5.
l 3. Changes in the Offsite Dose Calculation Manual should be reported in the Semiannual Radioactive Effluent Release Report rather than in monthly l reports. Monthly reports of changes are presently required by Technical
! Specifications 6.9.1.10 and 6.14.2.
e A comprehensive revision to Technical Specification 3/4.12 is being addressed ,
by Problem Sheet 249. -
- 2. Safety Signifiesace:
See Problem Sheet 249 for the safety significance of this item sad related items on the Radiological Environmental Technical Specifications.
/ 1 l
Rev. 26, 4/24/84 l Misd64
. _ _ _ _ - _ _ _ _ _ _ _ . _ . _ . . _ ______..__..-____._..._.__.__..J
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Page 2 i
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 036 Priority: 2D j
- 3. Anticipated Resolution:
See Problem Sheet 249 for the proposed resolution to'this ites and related items on Radiological Environmental Technical Specifications.
I
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Ite=s Cicsed: (Hew)
/
Date Time 4
Reference:
Proof and Review comments from Enclosure 3 Attachment A.
Items 3, 4, and 10 of Category 1 cc: J. E. Cross I
- 1. F. Rogers 1
1 i
i l
O V)
Rev. 26, 4/24/84 Misd65
)
l s
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 042 Priority: 3B
/
l Identified By Date Responsible Supervisor Tech Spec
Reference:
3.4.1.3 i
Tech Spec Page: 3/4 4-3 I
Problem
Title:
Recirculation Flow Nemenclature j 1. Problem Description (Tech Spec FSAR, SER, GE Design, Other):
Technical Specification 3.4.1.3 uses the terms recirculation loop flow and
! rated recirculation flow. The reference to " recirculation loop flow" should ,
be changed to " jet pump flow" and the reference to " rated recirculation flow" l
should be changed to " effective core flow."
, 2. Safety Significance:
None. Technical Specification 3.4.1.3 as written can be used to determine -
recirculation loop misnatch fer the purpose of the Technical Specifications.
This change ::: tides .tn f.:4:nc:e nt-h:d Of nan arin; racir:c;acien Ice; f1:v mismatch. Operation uncer the presant specificacions does not lead to nonconservative conditions.
- 3. Anticipated Resolution:
Perform evaluation of both methods of determining recirculation flow mismatch and select the most effective method. Incorporate results of this evaluation into the GGNS Technical Specification.
i 4 NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time 1
l
}
Rev. 26, 4/24/84 Misd75
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s Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) l Item Number: 042 Priority: 3B
- 5. Disposition: Per TSRT-8d/0031 GE, SRO and NPE recemc:end canceling Item #0/.2. RPD ceneurs and is clesing this item. .'
Items Closed: (How) Closed based on RPD review of TSRT-84/0031.
/
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1 TECHNICAL SPECIFICATION PROBLEM SHEET Ites Number: 044 Priority: 2B
/
j Identified By Date Responsible Supervisor .
i Tech Spec
Reference:
Table 3.3.3-2, Ites_D.2 Tech Spec Page: 3/4 3-29 Problem
Title:
Division 3 LOP Time Delav Trip
In Technical Specification Table 3.3.3-2, the 2.3-second time delay for Division 3, 4.16 kV bus undervoltage (loss of voltage) is presented in the same format as the time delays for Divisions 1 and 2. In Divisions 1 and 2 the time delay means that the undervoltage condition must exist for the specified time before ECCS actuation occurs. For Divison 3, a momentary undervoltage condition is sufficient to initiate the ECCS actuation logic.
The timin delay for Division 3 relates to the time before the Division 3 diesel l
i receives a start signal. ,
- 2. Safety Significance:
None. The problem described above is for clarification of the information presented in Table 3.3.3-2.
- 3. Anticipated Resolution:
Investigate the necessity for revising the format or providing explanatory footnotes to Table 3.3.3-2 to clarify the information presented.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date- Time i
O /
Rev. 26, 4/24/84 Misd78 ,
, , ,m, ..-__--_--.y.,, -
...,a-,-,-.-_y. . ~ , , - _,,_ -mw ww,s ,w,,.r*4. q+-- .---+-+# - v--ov--w,* c-.---t =*'-w e - -
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I Item Number: 044 Priority: 2B i 5. Disposition:
4 Items Closed: (How)
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Reference:
TSET-84/0273
), cc: J. E. Cross
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Rev. 26, 4/24/84 l Misd79 :
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TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 064 Priority: 3B NRC (I&E plus NRR) /1/24/84 ,
! Identified By Date Responsible Supervisor
. Tech Spec
Reference:
6.5.1.3 Tech Spec Page: 6-7 Problem
Title:
PSRC Alternates
Technical Specification 6.5.1.3 states that " alternate members" may be appointed by the Plant Manager to serve on the PSRC on a " temporary basis."
However, this section does not define " temporary basis" nor provide criteria for the qualifications of the alternate members.
Additionally, the Standard Technical Specifications stata that all alternate members shall be appointed in writing by the PSRC Chairman. Technical Specification 6.5.1.3 is inconsistent with the Standard Technical I;:acificati:n in that tha ?lant Manager rather than tha ?S?.C Chairman 1.. -ha,_ _ , ,
Standard Technical Specification appoints alternate nenbers.
- 2. Safety Significance:
None. This is an administrative change to clarify the qualifications, duration of assignment, and appointment responsibility for alternate members of the Plant Safety Review Committee.
l
- 3. Anticipated Resolution:
Determine if the qualification requirements and duration of assignment for i
alternate me=bers of the Plant Safety Review Co=mittee should be specified in plant procedures and, if necessary, in the Iachnical Specifications.
a Investigate the necessity of changing the appointment responsibility for alternate members.
/
Rev. 26, A/24/84
"-~
Misd113
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i TECPIICAL SPECIFICATION PROBLEM SHEET (CONT'D)
. Item Number 064 Priority 3B ,
- 4. NRC Response to Item (NRR/IE):
1.
( NRC Notified: /
4 a Individual Notified Date Time
- 5. Disposition:
1 i
j Items Closed: (How) i i .
- - /
Date Time 1
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Reference:
ISRT-64/0495, Sheets 5 through 9 a
cc: J. E. Cross j 1. F. Rogers I,
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il TECHNICAL SPECIFICATION PROBI.EM SHEET Iten Number: 065 Priority: 3B
/
Identified By Data Responsible Supervisor
- Tech Spec
Reference:
6.5.2.3 Tech Spec Page: 6-9 1
Problem
Title:
SRC Alternatives
Administrative controls 6.5.2.3 states that " alternate members" may serve on the SRC on a " temporary basis." However, the section does not define
" temporary basis" nor provide criteria for the qualification of the l alternates.
i j
- 2. Safety Significance:
l None. This ites clarifies the qualification requirements and the duration of appointment for " alternate members" of the Safety Review Committee.
- 3. Anticipated Resolution:
l Evaluate qualification requirements and duration of appointment for alternate members of the Safety Review Committee and investigate the need for incorporation in the Technical Specifications.
- 4. NRC Response to Ites (NRR/IR)
l NRC Notified: /
Individual Notified Data Time l
I
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
Reference:
TSET-84/0509 cc: J. E. Cross E. F. Rogers l
Rev. 26, 4/24/84 l Misd115
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TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 069 Priority: 3B
/
Identified By Date Responsible Supervisor l Tech Spec
Reference:
4.6.7.2 Tech Spec Page: 3/4 6-57 Problem
Title:
H2 Igniter Surveillance
Surveillance Requirement 4.6.7.2.a specifies that at least 41 hydrogen igniter glow Pl ugs per containment and dryvell hydrogen ignition subsystem must be verified to be energized after the supply breakers are energized during the surveillance test. The wording for this Surveillance Requirement may need clarification since there is a question whether the igniter glow plugs are energized af ter the supply breakers are energized. The Nuclear Regulatory Commission (NRC) has suggested that the Surveillance Requirement should be supplenented with an additional requiranent to ensure operability for a O ri-inun :f :ne i; niter on each redundant circuit .in-4s anciosed . retic ... L-question has been raised with respect to the NRC's suggestion that if all inoperable igniters were located in the dryvell, igniter coverage in the drywell might be inadequate.
- 2. Safety Significance:
The wording of the Surveillance Requirement has no safety significance since the igniters will be determined to be operable regardless of whether or not they are energized after the supply breakers are energized or after some other action. Igniters frem redundant emergency safeguard feature power supplies are located in each enclosed region in the containment or dryvell. The e present requirenent for containment and dryvell hydrogen ignition subsysta= ,
operability would allow 41 out of 45 glow plugs to be operable. It is . . -
possible that, of the 4 ignitors per division which could be inoperable, ignitors from both divisions in an enclosed region could be inoperable at the same time. This could create conditions which allow pocketing of hydrogen in enclosed regions.
J Rev. 26, 4/24/84 Misd121
l Page 2 i
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) l Item Number: 069 Priority 3B I
The issue of all inoperable igniters from each igniter subsystem being located in the drywell has no safety significance. The igniter system has been designed with sufficient redundancy so that the ignitors powered from a single division would be sufficient to assure initiation of hydrogen combustion, in the dryvell or containment. Thus, inoperability of 8 igniters in the drywell would not' impair the hydrogen ignition system's ability to perform its intended function. ,
- 3. Anticipated , Resolution:
A revies by the Arch %tect/ Engineer concluded that the wide spread distribution of the igniters provides assurance that the system would perfor= its intended O function even vi:h up te /- 1 ni:ers ;e: di. isien inoperable.. An additienal . - - _ . . . .
evaluation will be completed to determine if the wording for Surveillance Requirement 4.6.7.2.a should be modified so that it accurately reflects how the igniter glow plugs are energized. An additional evaluation will be performed to determine if the igniter glow plug operability requirements should be modified to require operability of at least one glow plus per redundant circuit in,an enclosed region. This evaluation will also confirm that inoperability of up to 4 ignitors in the drywell per igniter subsystem is acceptable.
4 NRC Response to Item (NRR/IE):
NRC Notified: /
. Individual Notified Date Time 1
Rev. 26, 4/24/84 Misd122
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. tage 3 TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 069 Priority 3B I
- 5. Disposition:
4 Items Closed: (How) i i
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Reference:
TSRT-84/0341, page 27 (items 1 and 2), page 12-14 '
l AECM-82/193 .
i
- J. E. S !s . _ _ _ . _ . . _ . . . _ . . . .,__
} R. F. Rogers i
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1 TECHNICAL SPECIFICATION PROBI.EM SHEET i
Item Number: 070 Priority: 3B NRR /1/24/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.7.6.1 4
i , Tech Spec Page: 3/4 7-28 '
Problem
Title:
Fire Suppression Water Svstem (Action Clarification) j 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
The NRC Chemical Engineering Branch has recommended rewriting Action j Statements a and b of Technical Specification 3.7.6.1 in order to clarify the l
language. The NRC recommendation is as follows:
I Technical Specification 3.7.6.1 Action Statements a and b should be rewritten
! as follows: ,
a.V With one pump and/or one fire water storage tank inoperable, restore the ineperable equipment to OPERABLE status with 7 days or provide an
]
_..__.. 1:4.r J:e.ic:lu;._.;un cr_tu2;1". The previsions cf A :hn'.ul Specificatiens 3.0.3 and 3.0.4 are not applicable.
- b. With the fire suppression water system otherwise inoperable, establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2. Safety Significance:
None. The problem represents a clarification only and no safety significance is identified.
- 3. Anticipated Resolution:
Evaluate and deter =ine the changes, if any, required for incorporation into the GGNS Technical Specifications and submit proposed changes to the 3RC.
- a
- 4. NRC Response to Item (NRR/IE): CEB Notified NRR 11-7-83 NRC Notified: /
) . Individual Notified Date Time i
d
/ Rev. 26, 4/24/84
- l
! Misd124 i
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TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) !
i l Ites Number: 070 Priority: 3B l 5. Disposition:
i !
Items Closed: (How) i 4
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i 1.,F. Ro8ers
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TECHNICAL SPECITICATION PROBI.EM SHEET i
)
i Item Number: 071 Priority: 2D NRC (I&E plus NRR) /1/24/84 Identified Ry Date Responsible Supervisor Tech Spec
Reference:
3.7.6.1, 2, 3, 4, 5, 6 and 3.7.7 f Tech Spec Page: 3/4 7-28 throuali 3/4 7-39 and 3/4 7-41 1
Problem
Title:
Deletion of Soecial Reporting Recuirements Fire Protection
Technical Specifications 3.7.6.1, 3.7.6.2, 3.7.6.3, 3.7.6.4, 3.7.6.5, 3.7.6.6, and 3.7.7, involving . fire protection systems and assemblies, require a Special Report be filed with the Nuclear Regulatory Commission (NRC) in the event of
- system inoperability beyond 14 days (7 days for 3.7.7). This is a requirement in addition to the establishment of fire watches and fire patrols. The NRC has reconenended that.this Special Reporting requirement be deleted.
- 2. Safety Significance: ,
- - e . . .t s c..a .:a invC . a + re;;:: ar. :..:.:*e m.-- u.c hu ... .f f er- e- pla r--- -
cp eracier.s .
l I
- 3. Anticipated Resolution: -
Evaluate the reportability requirements of these specifications to determine i
the effect that deletion of these reportability requirements would have on plant safety and regulatory commitments. Implement the appropriate Technical Specification changes.
I J
) 4. NRC Response to Item (NRR/IE):
! NRC Notified: /
f Individual Notified Date Time l
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/
Rev. 26, 4/24/84 i
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i TECHNIC L SPECIFICATION PROBLEM SHEET (CONT'D) i Item Number: 071 Priority: 2D i
i 5. Dispositten:
J, i
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j Items Closed: . (How) 1 1
i /
Date Time
, Esference: TSRT-84/0366 and TSRT-84/0460 1
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j R. F. Rogers l
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- NRC Proof & Review /10-26-84 l Identified By Date Responsible Superviso'r Tech Spec
Reference:
4.7.1.2 !
! Tech Spec Fage: 3/4 7-3 Froblen
Title:
l The NRC noted that in Surveillance Requirement 4.7.1.2, two of the high l pressure core spray (EFCS) service water system surveillance requirements have been deleted and should be added as follows: ;
"At least once per 18 months during shutdown, verifying:
i l 1. Each automatic valve servicing nonsafety-related equipment actuates to j its isolation position on an isolation signal.
.i 2. Iach,;ung stary at::_ati:a* *. r p .Jl. .tain ser ej.;,jt xa:ar ;re sr.f,a jrsa:n _
l than or equal to (60'; psig."
t l
4 These surveillance requirements are in the General Electric Standard Technical .
Specifications. .
- 2. Safety Significance None. There is one IFCS service water pump and this system does not servir !
4 i
j nonsafety-related equipment and, therefore, has no automatic valves for that ,
! isolation function. There is, however, one automatic valve, the NFCS pump 1
{ discharge valve, which is tested monthly. Pitsp characteristics, including l' discharge pressure, are tested quarterly per Surveillance Requirement 4.0.5
- and service water initiation logic is tested every 18 months per Surveillance '
Requirement 4.8.1.1.2.d.4.b.2. These required tests are sufficient to verify EPCS service water system operability.
i j 3. Anticipated Rasolutions j l Evaluate the need to incorporate the NxC concerns.
1 I
1 i Rev. 26, 4/24/84 1
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Iten Number: 094 Friority: 35 l -
1
- 4. NRC Response to Ites (NRR/IE):
i 1
NRC Notified: /
li Individual Notified Date Time j 5. Dispositions t *
- Items Closed (Bow) r i
/ ;
I '
Date Time !
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- - -?.e f t:w.c e : Sn?.:en f n 4;i*.. ;_L;2;. ::ani . '<i-h :;70 f eu !, ?? 0 :,
- l. ,,
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cc: J. E. Cross i
i R. F. Rogers 1
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s new. 26, 4/24/s4 l
Misd167 i 1
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O TECENICAL SPECIFICATION PR031.EM SEEET Item Number 128 Friority: 2E
/
Identified Ry Date Responsible Supervisor Tech Spec
Reference:
Bases 3/4.6.7 Tech Spec Page 33/4 6-7 Problem
Title:
Uptrade Revision Date of NRC Regulatory Guide
Technical Specification Rasee 3/4.6.7 references'NRC Regu,1 story Guide 1.7, dated March 1971. The applicable revision according to the FSAR is Revision 1 dated September, 1976.
- 2. Safety significance None. The change is administrative to reflect the commitment to Regulatory Guide 1!7, Revision 1 and has no effect on plant safety.
. ___. 3.. a escipaced Resolutier.:
A Technical Specification change to reflect the correct reference to Regulatory Guide 1.7, Revision 1. dated September 1976, was transmitted by letter to the NEC, Harold R. Denton from L. F. Dale, dated September 9, 1983 (ARCM-43/0565).
- 4. NRC Response to Itse (NRR/IR):
NRC Notified: /
Individual Notified Date Time
- 5. Dispositions e
Items Closed (Rov) , ,
/
Data , Time est J. R. Cross R. F. Rogers
- Rev. 24, 4/24/s4 Misd226
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! TECENICAL SPECIFICATI0W FR05t.tM SHttT i
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Ites Number 131 Priority: 2B
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Identified By Date Responsible Supervisor I
Tech Spec
Reference:
Table 3.7'.6.5-1 Tech Spec Page 3/4 7-37
' Frobles
Title:
Additional Fire Hose Stations to Table 3.7.6.5-1
Two additional hose stations are required to be added to Table 3.7.6.5-1. One i
station (13C) was added per design change, and the other hose station (55C) was inadvertently omitted from the table.
1
- 2. Safety Significances
! Inclusion of all fire hoes stations in Technical Specification operability requirements is important to ensure adequate fire protection for safety-related equipment.
-- r. .. . , . . . . .
- 3. Anticipated Resolutions ,
i A proposed Technical Specification chasse adding fire hoes stations 13G and SSC to Table 3.7.6.5-1 has been oubettted to the NRC in a letter from L. F.
Dale to E. R. Destes, dated September 9, 1943 (AECM-43/0545. Item 23).
1 I 4 NRC Response to item (NRR/IE):
WRC Notified: /
Individual Notified Date Tisc
- 5. *)isposition:
4 Items Closed (How)
/
Date Time 4
as J. E. Croce R. F. Resers Rev. 24, 4/24/s4 l,
M1ed231 l
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TICFMICAL SPECITICATION PROBLEM SEEET 3
Ites Number: 166 Priority: 25 WRC/CSB /
Identified By Date Responsible Supervisor i
Tech Spec
Reference:
4.6.1.5 Tech Spec Fage: 3/4 6-8 Frobles
Title:
Tendvater Leakage control System Interlocks
The NRC Centainment Systems Branch (CSS) has espressed soscera regarding the ability of the Feedwater Leakage Centrol Systes (TWLC8) to maintain a water seal in the feedwater system following a LOCA. The Ntc proposed that l feedwater valves 7010A and I, 7032A and 3, and 706SA and 8 be pneumatically 1eak tested per Appendix J to 10 CTR 50, unless further analysis saa l
- demonstrate that the FWLCS can asintain a water seal following a LOCA. The l scheds)ed performance of any leak rate testing would be at the.first refueling
) outage. Technical Specification 4.6.1.5 does not currently contain C.rtei1*t.:a ra ptre enti !:r the reftren:sf " *..*es.
- 2. Safety Significances l Wone. The existing design of the feedwater systen has been determined set to be a credible drywell bypass leakage path.
1
} 3. Anticipated Resolutions
- The feedwater leakage control systes design and operation will be reviewed to l determine the long-tern resolution to the NRC-CSE concern. This investigation
- will consider design modificatione to the FWLC8 to ensure a 100 percent water '
i seal on the feedwater check valves after a LOCA, surveillance testing requirements to verify check valve leskage integrity, and procedure revisions to optimise TVLCS response in an accident. Appropriate Technical i
< Specification revisions, if any, will be submitted followise sempletion of this evaluation. i
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Item Number: 166 Priority: 2H
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (Hov)
/
'< Date Time
..s f e t .:: e : TSRT-5-/0131 =
cc: J. E. Cross R. F. Rogers o
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Rev. 26, 4/24/84 Misd289 .
w
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TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 181 Priority: 2A
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.8.4.3 Tech 3pec Fage: 3/4 8-l.o Problem
Title:
RPS Electric Power Monitor
Technical Specification 3.8.4.3.a and 3.8.4.3.b require that an inservice RPS M-G set or alternate power supply be removed from service when time requirements for inoperable clectric power monitor assemblies are not met. -
l Compliance with these Action Statements could result in a full scram if a half I
l scram condition previously existed. Provisions should be made so that an RPS
- t power supply need not be removed from service where this would cause a full I
scram.-
- . 5:fe:y Iig.ift::::e:
.;e ne . O.e c:ange w::.. c.a.p cc clar.dy !a:nni:ci specif t:::1:n .sc::.:n Statements 3.8.4.3.a and 3.8.4.3.b so that compliance with these Action Statements will not result in an unwarranted scram.
- 3. Anticipated Resolution:
Submit a Technical. Specification change to 1) clarify Action Statements 3.8.4.3.a and 3.8.4.3.b to prevent the unnecessary tripping of an instrument channel, 2) specify actions to be taken to allow operation in this condition, and 3) provide a Bases Section for Technical Specification 3.8.4.3.
1 i
4 NRC Response to Item (NRR/IE): !
NRC Notified: /
Individual Notified Date Time r
Rev. 26, 4/24/84 Misd315
f . >
O Page 2 TECHNICAL SPECITICATION PROBLLM SHEET (CONT'D)
Priority: 2A Item Number: 181
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
Reference:
TSRT-84/0451, page 8 cc: J. E. Cross
. _. __ . R. F . Re i;e r s __
O, Rev. 26, 4/24/84 Misd316
- _r3 _. _ _ . . .
T TECHNICAL SPECIFICATION PROBLEM SHEET l
Item Number: 195 Priority: 2D R. Keeton /
l Identified By Date Responsible Supervisor Tech Spec
Reference:
4.6.1.4 Tech Spec Page: 3/4 6-7 Problem
Title:
MSIV-LCS Operability
Surveillance Requirement 4.6.1.4.a.2 should be reworded to properly reflect the design of the main steam isolation valve leakage control system as
.follows: " Inboard s'ubsystem heater operability by demonstrating . . ."
Surveillance Requirement 4.6.1.4.c.2 should be modified as follows:
l
- a. Inboard System,10"ti" H 2O vacuum at greater than or equal to 100 sefa.
- b. Outboard System, greater than or equal to 15" H 2O vacuum at greater than or equal to 200 scfm.
- 2. hia:: Signifi::n:a:
- cne . ~he p;cpesed changes, if accepted, wculc enhance the surveillance i testing of the system and provide clarification.
i 3. Anticipated Resolution:
Evaluate the proposed changes described in the problem description and incorporate into the Technical Specifications, as required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time l
l
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Item Number: 195 Priority: 2D
- 5. Disposition:
Items Closed (How)
/
Date Time
Reference:
TSRT-84/0152 9
cc: J. E. Cross
-R.
F. Regers . . . _.. _
+
l s.
J Rav. 26, 4/24/84 Misd340
^ . - - - - - , .. .
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TECENICAL SPECIFICATION PROBLEM SHEET Item Number: 197 Priority: IB 1
/
Identified By Date Responsible Supervisor l Tech Spec
Reference:
3.3.6-1 -
Tech Spec Page: 3/I. 3-50 Problem
Title:
Rod Block Instrumentation
Tables 3.3.6-1, 3.3.6-2, and 4.3.6-1 list certain control rod block trip
- functions which are required to be operable but this list does not include refueling equipment interlocks or all rod blocks initated by the RCIS and RPIS. In addition, the reactor mode switch initiated rod blocks are not shown on the tables.
I
- 2. Safety Significance:
None. The refueling platform and reactor mode switch interlocks are included in th raf: Ci.; :pera:icns specifica:icns (1.?.1). C:::rris : r:i
.-1: crs tal are presen:ly specifie in f ac.in:. cal dpectiic.2:1on 3.. 2.3 concerning control rod position indication.
I -
- 3. Anticipated Resolution:
Perform an evaluation to determine if Table 3.3.6-1, 3.3.6-2, and 4.3.6-1 should be revised to include the refueling equipment, RCIS, RPIS, and reactor mode switch rod block. functions.
i 4. NRC Response to Item (NRR/IE):
! NRC Notified: /
Indiatidual Notified Date Iic:e 9
! Rev. 26, 4/24/84 Misd342
N.
l Page 2 TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D)
Item Number: 197 Priority: 2B
- 5. Disposition: I l
2 Items Closed: (How) .
/
Date Time
References:
TSRT-84/0644, page 11
'- TSRT-84/0369, page 11 & 12
--- 7 C: ss . _ _ . . r -
R. F. Rogers 5 .g e i
3 N ,', 1 Rev. 26, 4/24/84 Misd342.1
l r l 1
TECENICAL SPECITICATION PROBLEM SHEET Item Number: 211 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.2-1 note (e) & Table 3.3.7.1-1 note (h)
Tech Spec Page: 3/4 3-1!. and 3/4 3-57 -
Problem
Title:
Isolation Actuation Instrumentation Notes and Radiation Monitoring Notes
The Isolation Actuation Instrumentation Table 3.3.2-1 note (e) and Table 3.3.7.1-1 note (h) states "Two upscale Hi R1, one upscals Hi Hi and one downscale, or two downscale signals from the same trip systes...". This statement is incorrect in that the downscale trip only actuates an alarm.
The statement should read, "Two upscale Hi Hi, or one upscale Hi Hi and one Inop, or two Inop signals from the same trip system actuates the trip system...."~
.. :4:a :y -:.gn .f:. car.ce :
None. For clarification only, current notes do not affect system operation.
- 3. Anticipated Resolution:
Investigate the necessity of clarifying note (e) of Table 3.3.2-1 and note (h) of Table 3.3.7.1-1 in the Technical Specifications. .
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- e .
i Rev. 26, 4/24/84- i l
Pisd21 i
____~ E_ ______ _ _ _ _ _ _ _ _ _ _ , - _ _ _ . . . . . . _ . . , . _ , , , _ , . _ , . . . _ , . . . ,. . . _ _ , . . ,
)
i l
Page 2 TECHNICAL SPECITICATION PROBLEM SHEET (CONT'D)
Item Number: 211 Priority: 3B
- 5. Disposition:
i
.i Items Closed: (Hov)
/
Date Time-
Reference:
TSRT-84/0344
~< ,
cc: J. E. Cross
-Er I ?0&?:1.- _
1 l
l l
l 1
Rev. 26, 4/24/84 Pisd22
I TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 214 Priority: 3B Jim McMahan (QA) /
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.1.3.3.b.2 Tech Spec Page: 3/4 1-9 Problem
Title:
Reactivity Control System Acceptance Criteria
Technical Specification 4.1.3.3.b.2 requires an integrity test of the control rod scram accumulator check valves to be performed at least once per 18 months. A concern was identified that the existing Technical Specification conflicted with the Standard Technical Specifications in that it did not list appropriate acceptance criteria for the check valve surveillance. A review of the scram accumulator operability requirements has been performed to resolve this issue.
Additie:11%. , :he 'U.C, Tirisien Of ?r:f set and 14s114 : ?r: grams. h J rec ::ence: :.414:12: ef Sc. ;4:.1.n:4 2aqu:.ra a.t ..i.J.5.b.2, since 1: appu[r[
to be unnecessary.
- 2. Safety Significance:
None. General Electric indicates that the design intent of the Technical Specification's Surveillance Requirement is adequately satisfied by the existing Technical Specification.
- 3. Anticipated Resolution:
An evaluation of the Technical Specifications Surveillance Requirements for ;
the centrol red scram ace.:culators deter =ined that a Technical Specification e !
revision is not necessary and that the Technical Specifications, as presently '
written, are correct.
Evaluate the NRC recommendation to delete Surveillance Requirement 4.1.3.3.b.2 and propose a Technical Specification change, if required.
s ,
Rev. 26, 4/24/84 Pisd27
, e , - . - -_m- y-%-.v.,n.-m,--, , - - - - - .
_ _ . - - ,,-.,-,p-.- ,,,-vg.gv., ypw,
1 1
l l
^. Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 214 Priority: 3B i
- 4. NRC Response to Item (NRR/IE): IE rece= ended deletion of specificatien. NRR (Hoffman) on 4/11/84 meeting indicated that the Tech Spec vill have to be changed and acceptance criteria established.
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
, Items Closed: (How) i
References:
- 1) TSRT-84/0268
- 2) TSRT-84/0201 l
- 3) Memo from R. C. Lewis to D. G. Eisenhut," Comments on Drafe Appendix A Technical Specifications. Grand Gulf Unit 2",
February 9, 1984.
ec: J. E. Cross -
R. F. Rogers i
f, J
Rev. 26, 4/24/84 Pisd28
\
~
= . = _ - _. - = . _ _
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 218 Priority: 2H l
Identified By Date Responsible Supervisor Tech Spec
Reference:
Technical Specification 3.3 Tech Spe: Page: 3/4 3-1 Problem
Title:
Trip Setpoint-Allevable Values ,
An NRC proof-and-review item (NRC-ICSB, 10/31/83) identified a potential area of concern relating to setpoint methodology used at Grand Gulf. This item states that at Grand Gulf, the numerical difference between the Technical Specification's trip setpoints and allowable values is deficient in that both trip unit drift and sensor drift are included. It is suggested that only trip unit drift should be included in the setpoint and allowable values.
l
- 2. Safety Significance:
i Tr.e safa:7 si;.ift:2nes :f se:;:in: t:hef:1::7 is :::re.:1 the su':'s:: :f c 32 Cvners' G: cup s:udy en 1:.s::.24:.: s 2:;c.r.:3.
- 3. Anticipated Resolutfon:
Evaluate the results of the owner's group study and its of fact on the GGNS I Technical Specifications
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time 1
l l .
- l
' l Rev. 26, 4/24/s4 ;
i Pisd35 1
l
- _ _ . - = _ _ _ _ . . _
Page 2 TICENICAL SPECITICATION PROBLEM SHEET (CONT'D)
Item Number: 218 Priority: 2H
- 5. Disposition:
- Items Closed
- (How) l
/
Date Tina i,
i
Reference:
TSAR Chapter 7 Question and Responses NRC Question No. 031.60,
< pages Q&R 7.3-12 through 7.3-12d and Figure 031.60-1.
- ' ._hl . i.7 0.s L ,__ _ __...,_,, ., __ __, ,, _ _ _ ,_ ,
R. F. Rogers O
t a
e e
i
- s
- i
/
new. 26, 4/24/84 f Fisd36
-- -- , , - , - - . _ _ . . _ .~.-_.,,-._.-.,_..--.m.--, _,.,-.---,,,_.,~,--,,.,..,-,,_,__.---..,-,_.r , . . . , . . , - , . . . , , , . , _ , . . , , - - . - . - . . , . - . - - _ ,
7 ..
TECHNICAL SPECIFICATION PROBLEM SHEET l Item Number: 222 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.7.2 Tech Spec Page: 3/4 7-5 Problem
Title:
Control Room Emergency Filtration System
The Nuclear Regulatory Commission (NRC) suggested in its proof and review comments, that Surveillance Requirement 4.7.2 should be revised to include the following requirement:
"At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, by verifying that the control room air temperature is less than or equal to 120*F."
This requirement was believed to be necessary for ensuring operability of the control room emergency filtration subsystems.
l
. Safecy Signifi: n::: , ,, _ . , , ,
Nene. This proposed revision is already addressed by Surveillance lequire=ent t 4.7.8 which assures that the control room air temperatures will be verified to be below 77'F at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. Anticipated Resolution:
A response to the NRC's suggestion should be prepared and transmitted to the NRC. This response should state that the proposed requirement is implemented I by Surveillance Requirement 4.7.8. This requirement specifies that the control room temperature must be verified to be below 77*F at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I
- 4. NEC Response to Item (NRR/IE): NRR per 4/11/84 meeting is planning to mandate a change to this specification based on human factors, equipment qualification and delete from control room temperature specification.
i NRC Notified: /
Individual' Notified Dets Time O. /
Rev. 26, 4/24/84 Pisd43
. i i
! Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Iten Number: 222 Priority: 3B i
- 5. Disposition:
i Items Closed: (Hov)
/
Date Time I
.I cc: J. E. Cross l R. F. Rogers ,
I I
i 1
l 1
4 l
f i
/ .
d Rev. 26, 4/24/84 i.
! Plsd44 1 l l
.- - = _._. ... :_ ..- - _. . - _...-..- . _ . - . . _ - . . _ _ . . _ _ _ _ _ . _ _ _ _ . . . _ . . . . - - . , _ . . . . . . , , . .. i
O TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 228 Priority: 3B
/
Identified By Date Responsible Supervisor-Tech Spee
Reference:
Table 3.8.4.2-1 Tech Spec Page: 3/4 8-39 Problen
Title:
Valve Identifier Nenenclature
Some of the valve identifiestion numbers in Technical Specification Table 3.8.4.2-1 have a suffix of A or B. The NRC has informally suggested that the numbering system should be modified to maka' it consistent. The suffix uniquely identifies valves that are duplicated in redundant process trains.
This concerns !&E exit item on 21-24 February, 1984 meeting pertaining to P41-F189.
1 .
- 2. Safety Significance:
j i
O --
Nen+. T.. ara is nc i:.cicaciara,.--chie. cina that .sny valves atmtlante J!
I omitted from the table.
I I 3. Anticipated Resolution:
j Perform an evaluation and determine the necessity to revise the valve ID system in these tables (Technical Specification 3/4.8.4.2). Consideration should be given to the use of hyphens followed by letters, as in the drawings, which are used to denote divisional power sources.
4 NRC Response to Item (NRR/IE);
NRC Notified: /
Individual Notified Date Tine ,
/
Rev. 26, 4/24/84
, Pisd55 .
i
- l i
l Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) 1 1
Item Number: 228 Priority: 3B
\
- 5. Disposition:
l l
Items Closed: (How)
/
Date Time ;
Reference:
TSRT-84/0304 cc: J. E. Cross
?. 7. 2:ssrs - - - - - . - . . . . . . . - . .
i +
1 i
l Rev. 26, 4/24/84 Pisd56
- , , , ,m--w.. ,
TECHNICAL SPECIPICATION PROBLEM SHEET I
Item Number: 241 Priority: 2D
/
Identifiad By Data Responsible Supervisor
- Tech Spec
Reference:
3.1.3.1
. Tech Spec Page: 3/4 1-3 Problem
Title:
Control Red Operability Clarification
- a. Surveillance Requirement 4.1.3.1.2 specifies that, when above the low power setpoints, all control rods which are withdrawn shall be demonstrated operable within a given time period. The requirement is limited to rods that have not had their directional control valves disarmed. The frequency for performing this Surveillance Requirement changes when any control rod is immovable as a result of excessive f # ction or mechanical interferences as described in Technical -
Specificat' ion 3.1.3.1, Action Statement a. The Action Statement should
- a revised to referan:2 ce:plation of Surraillanes 7. equi ane.:
!4chni:s; Spac .i:.ca:
.. 3. 1.h. .,.s:, c.. 3.1..; 1. .1.a re uiraa .nwperabia withdrawn control rods to be separated from all other inoperable control rods, i
but GE Standard Technical Specification requires they be separated from other inoperable withdrawn control rods.
- b. The lack of specific Action Statements for inoperability of the sersa discharge volumn requires that Technical Specification 3.0.3 be invoked if the scrsa discharge volume is declared inoperable. In some cases this would be an overly conservative action. i l
- 2. Safety Significance:
- a. None. Surveillance Requirenent 4.1.3.1.2 will be completed with the correce frequency under the present Technical Specifi:stions. Inclusion of a cross reference in Technical Specification 3.1.3.1, Action Statement
- a. would reduce the effort required to ensure compliance with the surveillance requirements. The addition of the word " withdrawn" to l Action Statement b.1.a would be an operational enhancement.
- b. None. However, invoking the requirements of 3.0.3 in the event of scram
) discharge volume inoperability may be overly conservative.
Rev. 26, 4/24/84 Pisd75
_ _, -~_ _ _. _ . , _ . -
Page 2 l
TECHNICAL SPECITICATION PROBLEM SHEET (CONT'D)
Item Number 241 Priority 2D
- 3. Anticipated Resolution: ,
- s. An evaluation of the Action Statements-in Technical Specification 3.1.3.1 will be completed to determine if the Action Statement should reference Surveillance Requirement 4.1.3.1.2.b. A revision to the Technical Specifications will be proposed if it is determined that: 1) the Surveillance Requirement should be referenced in the Action Statement, and 2) " withdrawn" should be included in 3.1.3.1.b.1.a to be consistent i with the GE Standard Technical Specifications.
- b. Evaluate the specific Action Statement (s) which address scrsa discharge volume inoperability and, if necessary, propose appropriate Technical Specification changes.
~ ~ ' ~ " ~
. TI" las;;n:a :: ~ ; ai ".T_'.l - ; : -
NRC Notified: /
Individual Notified Date ,
Time
- 5. Disposition:
Items Closed: (How) i
/
Date Time , ;
Reference:
TSRT-84/0628 cc: J. E. Cross R. F. Rogers I i
Rev. 26, 4/24/84 Pisd76
l l
I I
CL TECHNICAL SPECIFICATION PROBLEM SHEET Priority: 3B Item Number: 259
/3-15-84 W. E. Edge /L. C. Burgess Brian L. Steinman Identified By Date Responsible Supervisor Tech Spec
Reference:
5.7.1 & Table 5.7.1-1 !
1 Tech Spec Page: 5-6 and 5-7 Problem
Title:
Designed and Maintained Cononent Cyclic or Transient Limit
Technical Specification Table 5.7.1-1 sives the cyclic or transient limits for the reactor pressure vessel. A possible discrepancy between this table and TSAR tables 3.9-1 and 5.2-11 and the vendor instruction manual had been identified. Prelim 4 = ry investigation, however, indicates that the FSAR tables, vendor information, and the Technical Specifications are in agreement.
If the scrams from the normal and upset conditions and emergency conditions sections of the TSAR tables and thh vendor manual are added together, the results are consistent with Technical Specification Table 5.7.1-1.
- 2. Safaty Significance:
None, assuming confirmation of agreement between the Technical Specifications and the FSAR tables.
- 3. Anticipated Resolution:
Confirm agreement between Teebnical Specification Table 5.7.1-1 and TSAR Tables 3.9-1 and 5.2-11. Revise Surveillance Procedure and FSAR to reflect correct cyclic breakdown.
l NRC Respense to Itas (NRR/IE):
- 4. 1
/
SRC Notified:
Date Time Individual Notified O. . A I
Rev. 26, 4/24/84 Pisd108
_ __ t u _ , _ _ _ ,
I i
' Page 2
- TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
I Item Number: 259 Priority: 3B
- 5. Disposition:
4 Items Closed: (Hov)
/
Data Time i
Reference:
TSRT-84/0227 cc: J. E. Cross R. 7. Ec;ers 4
i
]
f I
i l
)
Rev. 26, 4/24/84 Pisd109 e o .. _ . . - _ , _ . . - _ _ . . _ _ _ _ . . . _ _ , . _ . . _ , _ . _ _ _ _ _ _ _ _ . _ . _ _ _ . . _ . . _ - . . . _ ,
l TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 271 Priority: 3B Hylander /
Identified By Date Responsible Supervisor Tech Spec.
Reference:
3.7.6.4 ,
i Tech Spec Page: 3/4 7-35 Problem
Title:
Halen Storage Requirements
Technical Specification 3.7.6.4 requires the halon storage tanks to have at least 95 percent of fun charge weight and 90 percent of fun charge pressure.
The requirement to maintain 90 percent of full charge pressure is adequate to ensure that the initial system pressure win be sufficient to overcome system pressure losses. However, a recent review of system design requirements and the system preoperational test reports indicates that 95 percent of fun charge. weight is not sufficient to provide a flooding concentration of 5 pertant by volume, 10 minutes after discharge, as required.
_ __a
- 2. Safety Significence:
Prasant system design any not ensure that minimum fire suppression
- capabilities of the halon system, required by the Technical Specification, will meet fire suppression design requirements.
- 3. Anticipated Resolution:
A design change has been requested to increase the charge weight per cylinder from 174 pounds to the manufacturer's maximum charge of 186 pounds. This change would ensure that the 95 percent of full charge weight LCO criterion presently in the Technical Specification will provide a minimum halon !
concentration of 5 percent at 10 nicutes after discharge within the protected a j
! area. Wl.ch this design change, no change to Technical Specification 3.7.6.4 {
will be required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
- Individual Notified Date Time
/
Rev. 26, 4/24/84 Pisd130 e mw - eo e-
- l l
Page 2 i
! TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D) i Item Number: 271 Priority: 3B l S. Disposition:
Items Closed: (How)
/
Date Time l
References:
TSRT-84/0409 TSRT-84/0597, Page 3 cc: J. I. C :ss _,
R. F. Rogers 1
l f
/
Bev. 26, 4/24/84 Pisd131 1 _ - - . - _ _ , _ - - - . __
. - - .-- = .. . . - . .___ _ _
l TECHNICAL SPECIFICATION PROBLEM SHEET l l
~
Item Number: 273 Priority: 3B RPD /
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.3-1, 3.5.1.e J
Tech Spec Page: 3/4 3-25, 3/4 5-3 Problem
Title:
ADS Action Statements
Table 3.3.3-1, ECCS Actuation Instrumentation, may need clarification with respect to what action should be taken when an ADS trip system is out of i
service. -
- 2. Safety Significance:
None. See the anticipated resolution below.
- 3. Anticipated Resolution:
I z';;:e :his 1: : f: ie".a:i:n since :h+ g ::--in a .sc-t: .: 1rr inJ;4rde.d .wd ifd:sm dit ddditic 1.*. '. 4 0 7.n.4 5.. 37 44if;00 Acn J.;.;, .30:1;n Statement c, and Table 3.3.3-1, Action Statements 31 through 34.
- 4. NRC Response to Item (NRR/IE): .
NRC Notified: /
Individual Notified Date Time .
- 5. Disposition:
l l Items Closed: (How)
/
2 Date Tina ec: J. E. Cross R. F. Rogers t
Rev. 26, 4/24/84 ,
l i
Pisd133 l I
t -. . . . - . . .
1
l
! l TECHNICAL SPECIFICATION PROBLEM SHEET i
Item Number: 284 Priority: 3B W. A. Russell / 3/19/84 .
l Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.7.12. Table 4.3.7.12-1 Tech Spe: Page: 3/13-??,3/1304 Problem
Title:
Surveillance Frequency Less Conservative Than BWR/6 Standard Technical Soecifications I
Technical Specification 3.3.7.12 lists the requirements for radioactive gaseous effluent monitoring instrumentation. The surveillance frequencies for i
channel checks and channel functional tests for the offgas pre-treatment and '
post-treatment monitors given in Table 4.3.7.12-1 may not be consistent with the frequencies in the BWR/6 Standard Technical Specifications.
- 2. Safaty Significance:
'J:ne. Tne ents:ing Te:hnical S;teific2: ten Su:reillar.:e Requirenents are
- .i:h :he raquirenin:3 in :he L il:1:31:21 I 'lir:7:200:1 78 h:i:21 -
, Specifications (NUREG-0473. Revision 3, Draf t 7) for the condenser air ejector radioactivity monitor.
- 3. Anticipated Resolution:
Evaluate the Survei1T - e Requirements for the offgas system radiation monitors and confirm adherence to the frequencies.for channel checks and channel functional tests specified in Grand Gulf design documents.
i
- 4. NRC Response to Item (NRR/IE):
NRC Notified: / '
i Individual Notified Date Time ,
l l
l :
/
Rev. 26, 4/24/84 1
Pisd150 1
I Page 2 ,
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) l Ites Number: 284 Priority: 35
- 5. Disposition:
Items Closed: (How) l
/ ,
Date Time '
l cc: J. E. Cross L F. Rogers ,
O :
l l
O.. /
Rev. 26, 4/24/44 Plad151
{
l .
TECHNICAL SPECIFICATION PROBLEM SHEET l
1 Ites Number: 295 Priority: 3B ,
l J. D. Petty /3-18-84 L. C. Burgess j Identified By Date Responsible Supervisor Tech Spec
Reference:
6.5.2.8 l Tech Spec Page: 6-11
} Problem
Title:
Audit's Perforned under the Cognizance of the SRC l
l
j Technical Specification 6.5.2.8 describes the audits of unit activities j performed under the cognizance of the SRC. However, some of the items are not ,
! worded consistent with the GE Standard Technical Specifications. For example, l,
ites h concerning the 24 oonth audit of the fire protection program and l implementing procedures, does not contain the GE-Standard Technical
- Specification statement " . . . by qualified licensee QA personnel." Similar ,
j problems any exist for other programs listed.
i
- . Esfety Si;;ifi:ance:
None. The composition of the SRC would ensure that the appropriate people are available to conduct the audit. Any changes made would be to clarify this i point.
I i
j 3. Anticipated Resolution:
1 Perform an evaluation of GGNS Technical Specification 6.5.2.8 and GE Standard Technical Specification to determine what, if any, changes are required.
- 4. NRC Response to Item (NRR/IE):
l NRC Notified: /
Individual Notified Date Time l
l l
i . l 4
]
Rev. 26, 4/24/84 l
i
- Fled 173
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d l TECENICAL SPECITICATION PROBLEM SHEET (CONT'D) i a .
I I Item Number: 295 Priority: 35 i
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- 5. Disposition: . , . . ~
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Items Closed: (Bow)
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Date Time , ' ,;
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TECHNICAL SPECIFICATION:. PROBLEM SHEET
\
^
Item Number: 296 Priority: 3B J. D. Petty / L. C. Burgess _ _
Identified By Data Responsible Supervisor l Tech Spec
Reference:
6.5.1.6
- Tech Spec Page: 6-7 and 8 ,
'~ '
Problem
Title:
PSRC - Responsibilities -
?'
i
s The following items are requirements in the GE Standard Technical s Specifications that are not requirements in the Grand Gulf Nuclear Station '
l Technical' Specifications. N The PSRC shall be responsible for investigation of all violations of t Technical Specifications, including preparation and f(tvarding.of reports covering evaluation and recommendations to prevent recurrence to the -
Vice President - Nuclear Operations and to the Company Nuclear Review and Audit Group.
- - .. he PSRC shall. hrres;m_e ic: r vc r. ;i -^ 2 . . . b ,. G _ . i u a_.
required by Technical Specification 6.8 and changes thereto. The Grand s Gulf Nuclear Station Technical Specifications require the PSRC to review proposed procedures and hhanges to procedures, which may involve an
- unreviewed safety question as defined in 10 CFR 50.59.
The Standard Technical Specifications require the PSRC to review al 1, x 1-proposed tests and experiments that affect nuclear safety. .The Grand' "
Gulf Nuclear Station Technical Specificatione require the PSRC to review l proposed tests or experiments which may involve an unreviewed safety ,
ouestion as defined in 10 CTR 50.59.
The Standard Iachnical Specifications require the PSRC to review all ,
i proposed modificatihns to unic' systems or equipment that affect nuclear
. .u .
safety. The Grans Gulf Nuclear Station Technical Specifications require the PSRC to review all proposed modifications to unit equipment or' systems which any involve an unreviewed safety question as defined in 10 CFR 50.59. s, s
.s, I
s -
. new. 26, 4/24/s4 Pisd175
_ _ . t .. ~ __ . _ _ _ . l_L . __ _ . _ . . _ _ _ _ .
Page 2
- . s i TECHNICAL SPECIFICATION PROBLDi SHEET (CONT'D)
!~
~
i Iten Number 296 Priority 3B i
$ - The Standard Technical Specifications require the PSRC to perform special reviews, investigations.'or analysis thereon requested by the Nuclear ~
Plant Manager. The Grand Gulf Nuclear Station Technical Specifications require the PSRC to review the investigations or analysis of special 1 --subjects as requested by the Chairman of the Nuclear Safety Review
,.. Committee. .
- The Standard Technical Specifications require the PSRC to review the implementing procedures of the Security Plan and the Emergency Plan.
This is not required by the Grand Gulf Nuclear Station Technical j
Specifications.
1
- 2. Safety Significance:
4
]
S: .t . An" : hang 2s :d2 :: 11 *. a : C. trif- -h2 res;:nsi*:ilt-ies -1 :he 7.M ,
j Iha intended functions of the Technical Specifications are being conducted by
) the PSRC.
I
- 3. Anticipated Resolution:
Perform an evaluation to determine what, if any, changes are required to the I Technical Specifications.
- 4. NRC Response to Itsa (NRR/11):
F NRC Notified: /
t
- Individual Notified Date Time
! 5. Disposition:
1 l
l '
Items Closed: (How) l Date Time j
' cc: J. E. Cross R. F. Bogers Rev. 26, 4/24/84 '
i Pisd176 1
.-_..____,m.,__._. . . _ _ . . _ , __ _ ____._ _ ____.. _ -._.m .- .--.,._..,_ -.,_ _ . . . _ - , , _ . , , , - , . . _ , , - .-.--,,,r r_ - . . . - , , , -
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 297 Priority: 2E l
Edwin Edlacher / 3-15-84 WEE /L. C. Burgess l
Identified By Date Responsible Supervisor l Tech Spec
Reference:
5.4.2 Tech Spec Page: 5-5 l
- Problem
Title:
Reactor Vessel and Recirculation System Water and Steam Temperature Discrepancy
The na=4a=1 T,,,of 533*F presented in Technical Specification 5.4.2 does not I appear to agree with the temperatures shown on FSAR Figure 5.1-1. .
- 2. Safety Significance:
None. The numerical values presented in Section 5.0 are typical nominal valuess presented for informational purposes, and are not meant to reflect precise design figures.
- 3. Anticipated Resolution:
Evaluate the temperatures given on FSAR Figure 5.1-1 to determine if the temperature presented in Technical Specification 5.4.2 can accurately be termed " nominal." If a revision of the Technical Specification is appropriate, submit the necessary change to the NRC.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
1 Individual Notified Date Time
+-
- i Eav. 26, 4/24/84
, Plad177 l
~
' I Fage 2 TECHNICAL SPECITICATION PROBLEM SHEET (CONT'D) i Iten Number: 297 Priority: 2E
- 5. Disposition:
4 Items Closed: (How)
- /
Date Time
)
Reference:
TSRT-84/0219 a
cc: J. E. Cross
?. 7. F.:; irs
]
4 l
1 i
s i
J Rev. 26, 4/24/84 Plsd178
l .
i TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 302 Priority: 2D C. Stafford /3-17-84 Responsible Supervisor Identified By Data Tech Spec
Reference:
4.8.4.1 Tech Spec Page: 3/4 8-20 1
Problem
Title:
Electrical Equipment Protective Devices 4
- Technical Specification 4.8.4.1.a.2 statement " Circuit breakers .found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation." may be construed to imply operation of the plant shall not be resumed. This should be changed to clarify that the statement is only applicable to resuming operation of the affected system or component. Determine if the 125YDC and the 120VAC circuit breakers in the i
Technical Specifications.
i %
n -3,-- S,2fatf Signifinancs : _ _ _ . .
1 None. The intent of the statement is t,o require that inoperable circuit f breakers be restored to CPERABLE status prior to resuming operation of the affected system or component. This change would be for clarification only.
- 3. Anticipated Resolution:
Evaluate the above statement in the context of Technical Specification 3.8.4.1 to determine if clarification is warranted. Propose a Technical Specification change if required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
2 Individus1 Notified Date Time s
)
)
Ray. 26, 4/24/84 Pisd185
- . . . . . - ... - - _ - - - - . . = . . . _. . _ _ ._ _ _ _ . _ _ _ _ _ _ _ _
l Page 2 l
! TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) i.
l l Iten Number: 302 Priority: 2D i
! 5. Disposition:
Items Closed: (How)
/
Date Tina i
, cc: J. E. Cross Rr F. Rogers .
l i
1 l
l l
l . i 1
< 1 1
~s i
I.
1
! ]
, Rev. 26, 4/24/84 l i
- l Pisd186
. . z ? - _~ . _ : - . __ = . _ _ - - _ , _ - , _ . _ _ _ _ _ . , . _ _ _- ,. - _,._,_... .,_. , _ , _ _ , . . . - , - - _ . . _ , , _ . . ,
l TECHNICAL SPECIFICATION PROBLEM SHEET l
Item Number: 305 - Priority: 3B i /
I Identified By Date Responsible Supervisor l Tech Spec
Reference:
3/4 (New Specification)
Tech Spec Page:'N/A -
Proble=
Title:
Potential For Plant Flooding From Probable Maximum Precipitation
The evaluation for the local Probable Maximum Precipitation (PHP) on the plant area presented in the SEE (Section 2.4.4) was based on a finished plant grade
{
. of elevation 132.5 feet mean sea level and a finished entrance floor level of 133.0 feet mean sea level. It was concluded that runoff from the local PMP would not exceed elevation 133.0 feet mean sea level in the plant area. It l was subsequently determined that (1) finished plant grade on some areas ,
(mainly parking areas) exceeded the 132.5 feet mean sea level. (2) seme i
O . drainage _svales-in 4he =ain plant ares had been filled in, (3) ber s and fencing for security might impede local runoff, and (4) security skirting on j trailers parked in the main plant area would block. flow and impede runoff from local intense storas. These changes from the original design condition might induce flood levels above the 133.0 feet mean sea level finished floor elevation and cause flooding of safety-related equipment.
i i
In order to ensure that proper flood protection is maintained, a new Grand Gulf Technical Specification has been proposed which is consistent with th's l
BWR/6 Standard Technical Specifications, the provisions of which have been approved by the NRC. However, BWR/6 Standard Technical Specification 3/4.7.3 states that 3/4.7.3 is not required if the facility design has adequate passive flood control protection features sufficient to accommodate the Design l Resis Plood identified in Regulatory Guide 1.59, August 1973.
4
- 2. Safety Significance
The potential exists for FMP flood levels reaching above the 133.0 feet mean sea level finished floor elevation.
i Rev. 26, 4/24/84 l
l Plsd191
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l l
i Page 2 TECHNICAL SPECIFICATION PROBLDI SHEET (CONT'D)
Item Number: 305 Priority: 3B
- 3. Anticipated Resolution:
Perform an evaluation to determine the need for the new Technical Specification addressing this issue. Submit the new Technical Specification, if deemed required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Ice:s Cicsed: (Hew)
I Date Time
Reference:
TSRT-84/0928 cc: J. E. Cross R. F. Rogers I
a 1 A s
Rev. 26, 4/24/84 Pisd192
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 306 Priority: IB Val Malafew /3-21-84 Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.6.4-1 Tech Spic Page: 3/4 6-27 to 6'-44 - ,
l Preblem
Title:
Contaitment and Drywell Isolation Valves ,
i
Table 3.6.4-1 does not presently include combuscable gas control system valves E61-7002A & B; 7004A & B; and the upper containment pool drain system valve l
G41-Y265.
Also, valves G33-Y001, 7004, F250, and 7251 (RWCU pump suction valves) l apparently have a GE requirement (30 seconds) concerning valve isolation time used in the analyses of potential offsite releases.
'c.? L1, 1. a *.a:n: fr:: Mr . '_ . F . O a
- e : e Mr . . . ?. . D en:e n , 'a:ed Aepust 19, l
l 1963, (4IC1-83/0492), requestaci che =aximum isolacion times for these valves be changed from the present 30 seconds to 42 seconds. Determine if electrical l division identification should be placed on valve numbers.
- 2. Safety Significance:
- There is no safety significance concerning the valve omission, since valves E61-F002A & B and 7004A & B are governed by the more restrictive requirements of Technical Specification 3/4.6.5. Valve G41-7265 is operated only during a j
refueling outage, and if inadvertently left open, the resultant leakage into the drywell would be detected by the drywell leakage detection system.
Ecwever, if the specified closing tines for the RWCU pump suction valves cre
! not within the GE analytical limits, this may result in a radiological release , , ,
i following a BWCU pipe break, in excess of previously analyzed releases.
Q Rev. 26, 4/24/84 Pisd193
.-m-_ _
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 306 Priority: IB
- 3. Anticipated Resolution:
Determine if valves 1E61-7002A & B, F004A & B and G41-7265 should be added to Table 3.6.4-1. A preliminary assessment indicates that valves 1E61-F002A & B, F004A & B should not be included in this table since the valves do not provide i an isolation function for the drywell. The isolation function for the drywell vacuum breaker lines is provided by actor-operated valves 1E61-7003A & B and 7005A & B which are included in Table 3.6.4-1. Perform an evaluation to i
determine if the RWCU pump suction valve closure times are correct and submit appropriate changes, if required. Determine if electrical division identification should be placed on valve numbers.
4 N7.C -Feepense to-Ire .-O'RR/IEL: - ---- - - - - -
~~
I NRC Notified: /
Indi'vidual Notified Date Tina
- 5. Disposition:
Items Closed: (How)
/
Date Time
Reference:
TSRT-84/0595, Pages 21, 32, and 120 cc: J. E. Cross R. F. Rogers 1
)
- Rev. 26,'4/24/84 l
Pisd194 l I !
i 1 1
l l
\
TECHNICAL SPECIPICATION PROBLEM SHEET Item Number: 316 Priority: 21 GE Tech Reviev / 3/17/84 ,,
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.2. 3.3.3 Tech Spec Page: 3/4 3-15 and 2'8 ,
Problem
Title:
Drvvell Press-High (ECCS Setpoints)
Grand Gulf Technical Specification Table 3.3.2-2 items e and f and Table 3.3.3-2 items A.1.b A.2.b, B.I.b. 3.2.b. and C.1.b specify the high dryvell ECCS setpoint and allowable value as 1.89 psig and 1.94 psig, respectively. ,
Recent GE design specification data sheets indicate that these values should be revised to 1.73 peig and 1.93 psig.
- 2. Safety Significance:
The new values previded by GE are nere conservatis"e than the values currently in the Ts:hnical I;e:ifi:: i:n; heveter. ::1:ul.*.:icns and anti; sis :: r:;-:r:
these new values have not been proviced by GE. It is, therefore, inpossible to determine the safety significance until this data is available.
- 3. Anticipated Resolution:
Perform an evaluation to determine if setpoint changes are required and submit Technical Specification changes, if needed.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Tine Rev. 26, 4/24/84 ;
1 l
Pisd210
l Page 2 l TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 316 Priority: 21
- 5. Disposition:
Items Closed: (How)
/
Date Time i
ec: J. E. Cross a
R. F. Rogers i v . . . . . . ~ -- - =- - " , , , _ [
i i
1 i
, I
% s 1
Rev. 26, 4/24/84 i F1sd211 ,
O TECHNICAL SPECIFICATION PROBLE( SHEET Item Number: 321 Priority: 3B GE /
Identified By Date Responsible Supervisor Tech Spec
Reference:
3.6.3.1 Tech Spec Page: 3/4 6-20 .
Problem
Title:
Standard Technical Specification Additional Action Statement
- with respect to 95'T
Action Statement b.2 to Technical Specification 3.6.3.1 differs from the GE Standard Tochtzical Specifications (STS) on the temperature limits for the suppression pool. The STS contains a provision allowing suppression pool temperature to exceed 95'T as long as reactor thermal power is less than 1 percent. The GGNS Technical Specifications omit this condition and its associated surveillance requirements.
- O j 27 -14fa
- Pfig.if1::::s:
j Nene. The Technical Specification is adequate as currently written.
- 3. Anticipated Resolution:
Evaluate the temperature requirements for the suppression pool and confira that no Technical Specification change is required.
- 4. NRC Response to Iten (NRR/IE):
I NRC Notified /
Individual Notified Date Time l
l O
new. 26, 4/24/s4 Pisd218
l . .
i i
l Fage 2 i
i i TECENICAL SPECIFICATION PROBLEN SEEET (CONT'D)
} -
) Ites Number 321 Priority: 35 ;
i i i
J i 5. Disposition:
- I. i t
Items Closed (Bow) 1
/ -
l* Date Time i
d I
- cc J. E. Cross t
l R. F. Rogers . ,
i l
4 j- . . _ _ _ . . . . _ . . . . ,_
I
- 2 i . .
l I !
\
1 t
i
)
l 4
i j i 1 .
i 6 I
i i i
[
' r f
Rev. 26, 4/14/84 I
Fled 219 i
\
- TECHNICAL SPECIFICATION PROBLEM SHEET i
Ites Number: 325 Priority: 3B
/
Identified By Data Responsible Supervisor Tech Spec
Reference:
3 /4. 6.1. 9 l
Tech Spec Page: 3/4 6-12 Problen
Title:
License Condition 2.C (19) requires the drywell purge valves to be sealed closed when operating above 200*F.
l 2. Safety Significance:
- None. This item is presently a license condition.
i .
l 3 Anticipated Resolutions Evaluate converting the license condition into a Technical Specification.
4 NRC Response to Item (KRR/IE):
NRC Notified: /
- Individual Notified . Date Time I 5. Disposition
i Items Closeds ' (Bow) i 1
/
Date Tine e !
I
Reference:
LCTS 9128 i act J. E. Cross
- 1. F. Rogers .
1 Rev. 24, 4/24/84 F1sd223
~
O .
TECHNICAL SPECIFICATION PROBLEM SHEET l
Item Number: 326 Priority: 35 l
Identified By Date Responsible Supervisor i
Tech Spec
Reference:
3/a.7.9 Tech Spec Page: 3/4 7-45 i
Problem
Title:
- License Condition 2.C (29) require 4 plant shutdown if spent irradiated fuel is placed in the spent fuel pool prior to installation and operability of backup *
! room coolers for the fuel pool cooling pump rooms.
I
- 2. Safety Significance:
)
l 1 None. ,This ites is presently a license condition.
\
J
- 3. Anticipated Resolution:
! ~_ __. ___P:2$31E*.2EE":rtin;: heli:::: :: li:1:n in:e i Tschtiesi ? teift:::i:n. .
.l 1
- 4. NRC Response to Item (NRR/IE):
fj NRC Notified /
l Individual Notified Date Time .
- 5. Disposition l
I l Items Closed: (Row)
/
Date Time
,i cc J. E. Cross
- 1. F. Rogers f
l i
Rev. 26, 4/24/84 l i
1 i
F1s4224
I l TECHNICAL SPECIFICATION PROBLEM SHEET _
Priority: 2D Iten Number: 328 Deve Noonan / 3/13/84 J. Catlin Identified By Data Responsible Supervisor i
- Tech Spec
Reference:
Table *3.3.7.5-1 Tech Spec Page: 3/4 3-70 f Problem
Title:
Containment /Drywell Area Radiation Monitor Minimum Channels i
] operat le Technical Specification Table 3.3.7.5-1 item 13 requires one min 4==
l However, GE Standard j
1 channel each for containment and dryvell ares monitors.
! Technical Specifications (STS) Table 3.3.7.5-1, item 14 requires two minimum operable channels each for containment and drywell area monitors and GGNS has l
1 i committed to having two channels operable. Also, the note at the bottom of Table 3.3.7.5-1 in the Standard Technical Specification indicates " secondary containment and drywell," whereas the corresponding GGNS note states
-- '--- "e:r.e1. = ... . i _. , :e il . " -Th ert- is no- 4.earea. h
- c er.er. .f ar .it em4 for less j chan the Requirac Channels Operable. Action et does not include less than
! Required Channels Operable.
i .
- 2. Safety Significance:
l None. The proposed change does not affect the probability of occurrence or the consequences of an accident or malfunction. The proposed change enhances l
l the assurance that the system vill perform its intended monitoring function.
i
- 3. Anticipated Resolution l
' Perform an evaluation to determine if two channels are required. Verify that the note at the bottom of Technical Specification Table 3.3.7.5-1 is correct. -
t Submit Technical Specification changes, if necessary. Evaluate ites 13 and Action 81 to make them consistent.
{ I g
I
~
4, Rev. 26, 4/24/84 4
I l
P1sd226
7 1
Page 2 1 -
l TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) 4 1
i Item Number: 328 Priority: 2D 1
1 1
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
i Individual Noeifisd Data Time j 5. Disposition:
1 I .
Items Closed: (Hov)
~
I , /
Date Time
{
i ._ ._
cc: J. E. Cross R. F. Rogers t,
i i
i 1
l
}
a e
9
- *s i
i i
i
)
i Isv. 26, 4/24/84 l l
)
I P1sd227 ,
- _ . _ . - - _ . - _ _ - - _ . , - . - . , . . . - - - . . . .-.- ._ . - . . - . _ . _ - . ..- ' i
t .
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 330 Priority: 3B Dave Noonan /3/12/84 J. Catlin Identified By Date Responsible Supervisor Tech Spec
Reference:
4.3.7.5-1 1
Tech Spec Page: 3/4 3-72 Problem
Title:
Surveillance Requirements
Technical Specification Table 4.3.7.5-1 requires a monthly channel check for the accident monitoring instrumentation. This agrees with the Standard ,
Technical Specification but differs from the daily checks required by other Grand Gulf Technical Specification sections for the same or similar instrumentation. In addition, FSAR 11.5.2.3.1 states that "During Reactor
! Operation, daily checks of system operability are made by observing channel e
i behavior." .
- 2. Safety Significe.:e :
None. The frequency of acciden: coni:cring in:trn=an:s::.cn channel checks should be made consistent with other Technical Specifications and the TSAR.
This represents an enhancement to the Grand Gulf Technical Specifications.
3., Anticipated Resolution:
The Technical Specification should be evaluated to determine if a daily channel check is required for those instruments which are normally operating in non-accident conditions. Also, evaluate continuing monthly calibration checks for those instruments which are turned on automatically upon an isolation system trip signal. Those instruments are:
Containment hydrogen Drywell hydrogen i l
I f
)
Bev. 26, 4/24/84 Pled 230
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 330 Priority: 3B Those instruments which operate continuously during normal plant operation are:
Drywell/ containment differential pressure Drywell pressure Containment pressure Suppression pool water level Suppression pool water temperature
- Drywell and CRD cavity temperature Containment air temperature All radiation monitors -
__ __ _4.Q.3C Respree _tei.ca_r.--(ai'M-52C Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time cc: J. E. Cross R. F. Rogers Rev. 26, 4/24/84 l l
l 71sd231 I
TECHNICAL SPECIFICATION PROBLEM SHEET l
Item Number: 331 Priority: 3B
~
J. Catlin / 3/22/84 l Identified By Data Responsible Supervisor Tech Spec
Reference:
Table 3.4.3.2-2 Tech Spec Page: 3/4 4-10 Problem
Title:
RCIC System Valve Leakage Alarm Setooinc
The alarm setpoint in Technical Specification Table 3.4.3.2-2 for the RCIC (Reactor Coolant System Interface valves leakage pressure) system should be changed from 480 to 485 psig. The 485 psig setpoint is based on a Bechtel j calculation using current data for instrument accuracies and as-built instrument elevations.
- 2. Safety Significance:
None. The 480 pais setpoint is adequately conservative. The 485 psig
. setpoint is merely a reflection of current data, i
- . Anti:1pr.:ei lasc h:i:n:
Raview the need for incorporating the prcpesed new sat;cinc in:c tha Tathnical l Specifications.
! 4. NRC Response to Item (NRR/IE):
j NRC Notified: /
I , Individual Notified Date Time
- 5. Disposition:
i i
Items Closed: (How) e e
/ ~-
Date Time
References:
TSRT-84/0787, page 6 and 7 TSRT-84/0656, page 11 i ec: J. E. Cross R. F. Rogers Rev. 26, 4/24/84 i F1sd232
-. . . .. =. . _ _ _ __ _. --__--
l O TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 333 Priority: 3B L. Rove /3/19/84 _,
J. Catlin
- Identified By Date Responsible Supervisor Tech Spec
Reference:
4.8.1.1.2.d.12.a i.
4 Tech Spec Page: 3/4 8-6 Problem
Title:
Verification of ECCS Sequencing of Loads on Offsite Power i 1. Problem Description (Tech Spec, PSAR, SER, GE Design, Other):
1 1 When the diesel generator is operating in a test mode and is connected to its I bus Surveillance Requirement 4.8.1.1.2.d.12.a requires verification that a sisatiated ECCS actuation will return the diesel generator to standby operation. The General Electric Standard Technical Specification also includes the requirement to verify that a simulated ECCS actuation will automatically energize the emergency loads with offsite power.
i
- 2. Safety Significance:
l O' Tne ;:esen- Technical Speciication En-ea111anca-Racciraman A na; .no-: ensure _ ,,,_. . . _ .
! verification of all safety functions associated with the transfer of loads ,
' from the diesel generators to offsite power. This could result in a failure f to detect unavailability of this transfer function.
- 3. Anticipated Resolutions Complete an evaluation of the Surveillance Requirements contained in the Technical Specification and in the General Riectric Standard Technical Specifications. Propose any Technical Specification modifications which are j
required to ensure verification of availability for safety functions associated with transfer of loads from the diesel generators to the offsite
- power supplies.
- 4. NRC Response to Item (NRR/IR):
NRC Notified /
Individual Notified Date Time l
l )
nav. 26, 4/24/s4 i
P1sd235
i l
1 Page 2 l
TECHNICAL $PECIFICATION PROBLEM SHEET (CONT'D) i ,
Item Number: 333 Priority: 3B i
- 5. Disposition:
Items Closed: (How)
. /
Date Tina I
cc: J. E. Cross
- 1. F. Rogers 4 .
9 I
i -
i l
i l
l 1
I
- i i,
f i
i J Rev. 26, 4/24/84 l
Pisd236
~
'l TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 339 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
6.2.2 Tech Spec Page: 6-l., 6-5 Problem
Title:
Non-Licensed vs. Auxiliarv Operator Titles -
Technical Specification 6.2.2, Table 6.2.2-1 and Figure 6.2.2-1 identifies the title of " Auxiliary Operator" within the shift crew composition. This title is inconsistent with the response to TMI related requirements (FSAR Section 18.1.3) for shift manning, which identifies the title of "Non-Licenses Operator".
2V Safety Significance:
None. The term "Non-Licenses Operator" is consistent with the title "As ilia Q erator" with respec: :: :he shif: crew c: .pj si:ipe. _ _ . . _ , , _ ,
- 3. Anticipated Resolution:
Investigate the necessity of clarifying the term "Non-Licensed Operator" in FSAR Section 18.1.3.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
. Individual Notified Date Time
- 5. Disposition:
, Items Closed: (Hov) . ,,
/
Date Time cc: J. E. Cross s
R. F. Rogers
/
Rev. 26, 4/24/84 Pisd246 i
. . l l
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 340 Priority: 3B i
/
Identified By Date Responsible Supervisor 1 Tech Spec
Reference:
6.2.2 Tech Spec Page: 6-2 Problem
Title:
Time Off Between Working Periods '
Technical Specification 6.2.2.f specifies guidelines that shall be followed
{i (for unit staff who perform safety-related functions) in the event that unforeseen problems require substantial amounts of overtime to be used. Item
- 3. of this Technical Specification states that a break of at least eight hours should be allowed between work periods, including shift turnover time. The eight hour break is inconsistent with FSAR Section 13.1.2.1 which discusses a break of at least twelve hours.
) :. Safa:y 31;.ii;:3. .c e :
Sc:a. FSid Section 13.1.2.1 should be tevised to be consistent with FSAR Section 18.1.3 and Technical Specification 6.2.2.f.
- 3. Anticipated Resolution:
Evaluate the inconsistencies between the SER, NUREG-0737 FSAR Section 13.1.2.1 and Technical Specification 6.2.2.f. Revise FSAR Section 13.1.2.1 with respect to the break time between work periods in the FSAR update if i appropriate.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: ~
/
Individual Notified Date Time l
)
Rev. 26, 4/24/84 i
i Pisd247 l
! __. J1T __ r_ - - - -- -
O - -- - - - - - - - ~ ~ - - - - ~ ~ ~-'
Page 2 i
TECHNICAL SPECIFICATION PROBLDi SEEET (CONT'D) l .
l Ites Number: 340 Priority: 38 1
3 1
l 5. Disposition:
i i
i I
l Items Closed: (How) i
. /
i Data Time l
l cc: J. E. Cross ,
< h F. Rogers
]
I I
j , ,
l l
l i
4 i
I l,
I I, .
l i
3 1
I i i ,
4 i
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4 i
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i Rev. 26, 4/24/84 i
l 71sd248
. - - - - - - . - - . , . - , - , . . , - - - - - . . - - ,-.,.n-.-..-.--,,,,,,--,,n. --n-.--,~, --ne,---,,--,--,-,-,-,, ,---,----w-, -- n,v n ~ .n~~~-
l TECHNICAL SPECIFICATION PROBI.EM SHEET Item Numbers 343 Priority: 3B GE Review /4/3/84 Identified By Data Responsible Supervisor Tech Spec
Reference:
3.3.3 Tech Spec Page:
- Problem Titler Grand Gulf Technical Specification / B7R/6 Standard Technical Specification Inconsistency
The BWR/6 Standard Technical Specification has requirements for " Division 1, 2, and 3 Bus Power Monitor"; the Grand Gulf Technical Specification does not.
GE interprets the " Bus Power Monitor" as the battery bus low voltage instrumentation.
- 2. Safety Significance:
'one. This instrument is for annunciation only and has no actuation function.
-wt ' sp u s"- c111.:.a- tsac.;;_ ant. acr.inistrati-ai" Mcitated s'Ler;?. 5 .
hcurs. The DC bus =enitors are in service with setpoints of 109 volts; enus the only change here would be a change to the Technical Specification.
- 3. Anticipated Resolution:
Add requirements to Grand Gulf Technical Specifications for Division 1, 2, and 3 bus power monitor to make consistent with BWR/6 Standard Technical Specification.
l
( 4. NRC Response to Item (NRR/IE):
NRC Notified: / '
Individual Notified Date Tine O
\ i v
)
Rev. 26, 4/24/84 P1sd249.2
. -- - 2; r '4 i ,
l t
Pge2 l
TICENICAL SY2CIFICATION PROBLEM SHIET (CottT'D)
Item Weber: 343 Priority: 33 ;
- 3. Disposition: .
/ /
Items Closed (Row) .- .
I 1
/ ,'
Date Time est J. E. Crosa ,
M F. Resers
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'c il I
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L T
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Rev. 24, 4/24/84 Pled 249.2.1 1
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' ~
1 TECHNICAI.- SPECIFICATION I?.0BI.EM SHEET Item Number: 346 Priority: 2D Loeper /4/5/84 Identified By Date~ Responsible Supervisor '
Tech Spec
Reference:
3.3.7.8 Tech Spec Page: 3/4 3-75
- I '
Problem
Title:
Chlorine Deteetion System
Technical Specification 3.3.7.8 requires two independent chlorine detection systems to be operable in all Operational Conditions. The GGNS design for the chlorine detection system includes a sensor with output contacts providing signals to the control room emergency filtration system isolation logic. The specification should be revised to replace " chlorine detection systems" with
" chlorine detection channels" for consistency with the GGNS instrumentation definitions.
_ A:ti n 5:a:anen:s (a) and (b),:31;1:e a: ". east ene cen:::1 : g. a=er;; enc -
filtration sys a= subsysta= to be operating in the isolacion :: ode unen chere are inoperable chlorine detection channel (s). The Action Statements should require that the, control room emergency filtradion subsystem which is4 associated with the Control Room HVAC subsystem that is in operation be initiated and maintained in the isolation mode of operation.
s
- 2. Safety Significance: ;
None. Replacing " systems" with " channels" for the chlorine detection instrumentation is for clarification of terminology and does not affect ,
compliance with the intent of the Technical Specification. ,l s ;
Y None. This is an enhancement 'ition for operations. As presently worded,
~
Action Statements (a) sad (b) would permit initiating and meintaininh the -
l control room emergency filtration subsystem which is associated with the control room HVAC subsystem that is not in operation in the isolatioh mode.
The operating control room HVAC subsystem in this event would only be .
recirculating air through its normal filter and would not be circulating' air s co m
~
._)
Rev. 26, 4/24/84 l
Plsd249.6
Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 346 Priority: 2D through the filters of the energency filtration subsystem. This is not a concern for an outside accidental chlorine release since the common intake for both control room HVAC subsystems would be isolated.
- 3. Anticipated Resolution:
Evaluate the necessity of changing Technical Specification 3.3.7.8 to provide the proper terminology and provide consistency with the GGNS instrumentation channel definitions.
Evaluate Action Statements (a) and (b) with respect to the design intent of the control room emergency filtration subsystens and -their associated chlorine da:actien channs;s. Pre; se ap; opriate 'e:hni:cl Spe:ifi:a:ica changes as necessary.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
i Items Closed: (How)
/ ,-
Date Time -
cc: J. E. Cross R. F. Rogers i
Rev. 26, 4/24/84 Pisd249.7
TECHNICAL SPECIFICATION PROBLEM SHEET _
Item Number: 348 Loeper ._.
Priority: _ 2D
/4/5/84 Identified By Data Tech Spec
Reference:
3.3.7.3-1 Responsible Supervisor Tech Spec Page: _3/4 3-63 Problem
Title:
_ Met Monitoring Instrunentation .
1.
Problem Description (Tech Spec. FSAR, SER, ,
Other):
GE Design .
Technical Specification Table 3.3.7.3-1 requires a mi i n mum of one operable j instrument for each of the listed meteorological monito i Statement (a) requires a Special Report to the NRC r ng functions.
if " Action one or more meteorological than 7 days. monitoring instrumentation channels" is ino perable for more The GGNS design includes 2 instrument channels c for ea h meteorological monitoring parameter of Table ... 3 3 7 3-1 St;stement (a) could require a Special Report to thThe existing Action inoperable instrunent event though the mininume NRC for a single rieuirsnan: operable instrunents
- re:.s e: :: :f ~f ~a 2.2.'.3-i is sa-isfied. Ac:icn 3:::aren: -, a; st cle 's ca_e:e tr.is unnacessary reporting requirenants.
- 2. Safety Significance:
None. ,
The GGNS Techiral Specification ensures adequate monitoring instrumentation response. asteorological the reporting requirements of this specificatiThe on.
proposed change w
- 3. Anticipated Resolution:
Review Action Statement inoperable instrument channels and evaluate th(a) r with re Specification change based on this review e necessity of a Technical 4.
NRC Response to Item (NRR/IE):
NRC Notified:
/
Individual Notified Date
. Tian
)
Rev. 26, 4/24/84 Plsd250
.-.y.- _,-,-.y., - -. - ,-.w_ g ,y,, ,, s.-,m , ,,.,a e' -9m "'* -
e
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Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 348 Priority: 2D
- 5. Disposi: ion:
Items Closed: (How)
I Data Time ec: J. E. Cross R. F. Rogers
~' - -- -- -~ . .. __ _. _ _ _ . .
9 Rev. 26, 4/24/84 Pisd251 e ,- w ,- - , , - - - - - - ,-r, -
l O TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 362 Priority: 2B )
Loeper /
j Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.2 and 3.3.5 Iech Spec Page: 3/4 3-9 and 3/4 3-44
. Problem
Title:
RCIC Time Delay for Actuation and Isolation
Recent, design changes have been made to the reactor core isolation cooling (RCIC) system to add two time delays. One time delay was added to the actuation logic to prevent RCIC turbine trip on overspead following the opening of steam admission valve 151-7045. The second tima delay was added to the isolation logic to prevent system isolation izanediately following a loss of offsite power signal. Technical Specification 3.3.2 and 5.3.5 contain Survei.11ance Requirements for similar RCIC timers, but not for the timers installed for the new time delays.
~~
- 2. Safety Significance:
None. ' Operability of the timers installed for the new time delays is currently checked during the logic system functional tests required by Technical Specifications 4.3.2.2 and 4.3.5.2.
- 3. Anticipated Resolution:
Perform an evaluation of the additional time delays in the RCIC actuation
, logic and RCIC isolation logic and confirm that Technical Specification changes are unnecessary.
- 4. NRC Response to Item ( m /II): ,
NRC Notified: / -
Individual Notified .Date Time
, O.
I Rev. 26, 4/24/84 1
Plsd277
l Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 362 Priority: 2B
- 5. Disposition:
1 Items closed: (How) 1 Date Time cc: J. E. Cross R. F. Rogers i
e f
l 4
I Eav. 26, 4/24/84 i Pisd278 1 -. T:' 1 1 __.__ _ _ _
. _ . ___.._a___________ ,, _ _ _ _ _
I 1
. i TECHNICAL SPECIFICATION PROBLEM SHEET 1 Ites Number: 367 Priority: 2D F. A. Russell / 3/20/84 Identified By Date Responsible Supervisor Tech Spec
Reference:
3.3.7.5 Tech Spec Page: 3/4 3-70, 3-71 Problem
Title:
Action Statement Not Consistent with Table 1.
Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
Item 13, contain= ant /drywell area monitors, of Table 3.3.7.5-1 references Action 81.
Action 81 addresses only operation with less than the " minimum
, channels operable".
The Action Statement for item 13 should address "Raquired number of channels," as well as the " minimum channels operable"; therefor Action 81 is inappropriate for item 13. ,
Duplicate cf Problem Sheet #328.
I
- 2. Safety Significance:
None.
As long as the minimum operable channel requirement of Action 81 is met, 1::id=n: _: nit:rin; cap n ili:7 is pre 71ded.
- 3. Anticipated Resolution:
k Evaluate changing Action Statement to Action 80 for item 13 .
- 4. NRC Response to Item (NRR/IE):
NRC Notified:
/
i Individual Notified Date
- 5. Time Disposition: _ Refer to Problem Sheet #328.
I Items Closed: (How)
/
Date Time cc: J. E. Cross R. F. Rogers
/
Rev. 26, 4/24/84 Plad283.1
l TECHNICAI, SPECIFICATION PROBLEM SHEET l
Item Number: 368 Priority: 3B W. A. Russell / 3/20/84 Identified By Date Responsible Supervisor Tech S,pec
Reference:
3.3.7.5 Tech Spec Page: 3/4 3-70 Problem
Title:
Incorrect Nomenclature i
, 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
Table 3.3.7.5-1 and 4.3.7.5-1, Items 13 through 18, should be revised to read
" radiation monitor" instead of " monitor". *
- 2. Safety Significance:
Resolved as part of Problem Sheet Itaa 329.
3i Anticipated Resolution:
l Resolved as part of Problem Sheet Item 329.
. = - . . ..
l 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Tina
- 5. Disposition: Refer to Problem Sheet # 329.
Items Closed: (How)
.i i
I /
Date Time i e cc: J. E. Cross ,,
R. F. Rogers i
j i
s Eav. 26, 4/24/84 Plsd283.2
~ 1 1
1 TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 369 Priority: 2D W. A. Russell /3/19/84 Identified By Date > Responsible Supervisor Tech Spec
Reference:
3.3.1 Tables 3.3.1-1 and 4.3.1.1-1 Tech Spec Page: 3/4 3-2, 3, 7 and 8 ,
Problem
Title:
Applicable Operational Condition Inconsistencies
- Table 3.3.1-1 specifies applicable operational conditions for reactor protection system instrumentation and several items have footnotes describing exceptions to these operational conditions. Table 4.3.1.1-1 specifies Surveillance Requirements for the instrumentation listed in Table 3.3.1-1, but' does not contain the same footnotes for the affected items. This in effect requires Surveillance to be performed when the instrumentation is not required to be operable.
- 2. Safa:y Significance:
Mene. Curra:Eidi:2 ~inisiib5 '326tsillif.ie' ?.q lisn' eel re nora c: .s*- ::10 than the operability requirements.
- 3. Anticipated Resolution:
!' Evaluate to determine if appropriate footnotes should be added to Table 4.3.1.1-1, to make it consistent with Table 3.3.1-1. ,
- 4. NRC Response to Item (NRR/IE):
NRC Notified: _
/
Individual Notified Date Time 4
I l Rev. 26, 4/24/84 Pisd283.3
Page 2 l
TECHNICAL SPECIPICATION PROBLEM SEEET (CONT'D) l
' l i
Item Number: 369 Priority: 2D ,
4
- 5. Disposition:
i Items Closed: (How)
I Data Time cc: J. E. Cross R,. F. Rogers f
J i
l l
4 l
Rev. 26, 4/24/84
, Pisd283.3.1 l
l j=___.__.._.
j .
I & S g
TECHNICAL SPECIFICATION PROBLEM SHEET l
Item Number: _ 372 Priority: 3B S. Loeper
/ 4/16/84 Identified By Data .
Responsible Supervisor Tech Spec
Reference:
Tables 3.3.2-1
- Iach Spec Page: 3/4 3-10 Problem
Title:
Manual Initiation of Valve Group 6A 1.
Problem Description (Iech Spec, FSAR, SER, GE Design, Other):
According to Isolation Actuation Instrumentation Technical Specification Table 3.3.2-1, valve group 6A receives a closure signal from manual initiation (item 1.h) of primary containment isolation. Eight valves in group 6A do not close I
from the.sanual initiation of primary containment isolation. These valves isolate chilled water to the drywell coolers (P44-7070, 744-7069, P44-F053, P44-7076, P44-F074 and P44-7077) and the auxiliary building floor and equipment drain tanks line to the suppression pool (P45-F273 and P45-F274).
_ O _
2.
91?atv Ete-tiin
- _ _ _ _ - n... .., .
.__._. 3 _
he accident analysis does act take credit fsr enn nanual initiation fun:cien .
for primary containannt isolation.
Automatic isolation signals are assumed to provide the necessary isolation function.
Emergency and off-normal procedures
.for the plant do not taka credit for the manual initiation of primary containment isolation.
Since the automatic isolation signals close all group 6A valves, the subject problem description is not safety significant.
However, Technical Specification Table 3.3.2-1 is currently misleading and can .
lead to mintnterpretation as to which valves receive manual initiation isolation signals, a
- 3. Anticipated Resolution: dP Evaluate the problem to determine if a plant design change or Technical Specification change is required.
. 4. NRC Response to Item (NRR/II):
NRC Notified:
/
Individual Notified Date Time Rav. 26, 4/24/84 Plad283.4.3
1 .
- 1 1
i l
s Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D)
Item Number: 372 Priority: 3B
- 5. Disposition:
4 Items Closed: (How)
/
Date Time ec: J. E. Cross R. F. Rogers
.- .A - ...
?
1 l -
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i, i
']
Rev. 26, 4/24/84 l
P1sd283.4.4
. . . - . . _ - - . - _ - . .- ..-- -. . . , -. - . A
., s
" TECH SPEC PRIORITY" v MEMO TO: Tech Spec Review Personnel ,
FROM: C. L. Tyrone -
1 l
SUBJECT:
Rev. M to Technical Specificatien Problem Sheet TSRT: 84/ D h o DATE: % c's\ M i NGA-The following changes / additions are to be incorporated into the Tech Spec i
Problem Sheets:
ITEM hTM3ER CHANGES /ADDITICN D AS OtM' , Remove Rev.\f. Insert Rev. Q y
19u(1%D -
s .
Remove Rev.A$ Insert Rev. M Remcve Rev. , Insert Rev.
Remove Rev. . Insert Rev.
O Remove Rev. , Insert Rev.
O Remove Rev. . Insert Rev. _
Pemove Rev. . Insert Rev.
Remove Rev. , Insert Rev.
Remove Rev. , Insert Rev. .
4 l
Remove Rev. , Insert Rev.
i Remove Rev. . Insert Rev. .
6 Remove Rev. . Insert Rev.
Remove Rev. . Insert Rev.
i wC C. L. Tyrone ,
4 CLT: sad Attachment ec: 5. H. Hobbs (w/1) -
File (Tech Spec Ree rds) (v/1)
_ _ _ . _ _ . ~. .-
l l ,
TSRT-84/ D 4%b l .
l PROBLEM SHEET LISTING AS OF h n%ss,, h\k%
Date ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 001 X IB 45, 3/29/84 t
002 X 2D 26, 4/24/84 1
003 X 2D 17, 4/01/84 004 X 2E 22, 4/09/84 005 X IB 15, 3/29/84 006 K 2D 21, 4/08/84 007 X 2F 15, 3/29/84 008 X 2H 17, 4/01/84
- 009 X 2B 25, 4/16/84 010 X 2B 15, 3/29/84 011 X 2B 15, 3/29/84 012 X 2B 26, 4/24/84 013 X 2D 26, 4/24/84 014 X 2B 21, 4/08/84 015 X 1B 17, 4/01/84 0 016 X IB 15, 3/29/84 017 K 2D 15, 3/29/84 018 X 38 15, 3/29/84 019 X 2B 25, 4/16/84 020 X 2B 17, 4/01/84 021 X IC 15, 3/29/84 022 X 2A 17, 4/01/84 023 X 2B 15, 3/29/84 024 X 2B 18, 4/02/84 0_25 X 35 26, 4/24/84
] 026 X 2D 15, 3/29/84 027 X 2E 15, 3/29/84 028 X 2B 15, 3/29/84 029 X 3B 26, 4/24/84 030 . K 2D 17, 4/01/84 031 X 2D -
17, 4/01/84 O 032 X 2B 21, 4/08/84 V 033 X IB 18, 4/02/84 034 X IC 18, 4/02/84 035 X 2C 15, 3/29/84 L26sd1 4
- PROBLEM SHEET LISTING PRIORITY REVISION, DATE REVIEWED BY RPD ITEM NUMBER X 2D 26, 4/24/84 036 X IC 15, 3/29/84 037 X IC 15, 3/29/84 038 X 2G 17, 4/01/84 039 X 2F 17, 4/01/84 040 X 2B 21, 4/08/84 041 X 3B 26, 4/24/84 i 042 X 2D 15, 3/29/84 I 043 X 2B 26, 4/24/84 044 X 2B 17, 4/01/84 045 X 2F 15, 3/29/84 046 X 2B 15, 3/29/84 047 X 2H 27, 4/26/84 048 X 2B 18, 4/02/84 049 X 2B 17, 4/01/84 050 X D 15, 3/29/84 051 X 2E 15, 3/29/84 052 053 X 2E 17, 4/01/84 054 X IB 21, 4/08/84 055 X 2D 15, 3/29/84 X 35 21, 4/08/84 056 i
057 X 2B 17, 4/01/84 X 2D 17, 4/01/84 058 059 X 2D 17, 4/01/84 060 X 2B 15, 3/29/84 X 2D 15, 3/29/84 061 X 2E 18, 4/02/84 062 063 X 2E 17, 4/01/84 X 35 26, 4/24/84 064 065 X 38 26, 4/24/84 066 X 2D 22, 4/09/84 X 2D 15, 3/29/84 067 068 X 35 15, 3/29/84
. 069 X 3B 26, 4/24/84
\
070 X 3B 26, 4/24/84 071 X 2D 26, 4/24/84 072 X 2D 17,'4/01/84 L26sd2
_ ~ _ - _ . - - . - - . = _ - - - . . . .. _ - ... . - - - - _.._ _- - -. - - .. . _ _ _ . _
PROBLEM SHEET LISTING l ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 073 X 2B 18, 4/02/84 074 X 2D 17, 4/01/84 l 075 *I 2B 17, 4/01/84 1
! 076 X IB *18, 4/02/84 077 K 2B 21, 4/08/84 f
j 078 I IB 15, 3/29/84 j 079 X 2E 15, 3/29/84 i i 080 X N/A (Resolved) 15, 3/29/84 081 X 3A 15, 3/29/84 l
) 082 X 3A 15, 3/29/84
) 083 X 2B 22, 4/09/84
) 084 I 3A 15, 3/29/84 085 X 2D 20, 4/06/84
[
086 X 2D 18, 4/02/84
]
087 X 2D 17, 4/01/84 j 088 X 2D 17, 4/01/84
{ 089 X 2D 15, 3/29/84 090 X 2D 17, 4/01/84 091 X 2D 15, 3/29/84 l
j 092 X 2D 18, 4/02/84 i 093 X 2E 22, 4/09/84 094 I 35 26, 4/24/84 l 095 X 2E 22, 4/09/84 l 096 X 2E 25, 4/16/84
) 097 X 2E 15, 3/29/84 098 I 2G 15, 3/29/84 099 X 2G 21, 4/08/84 :
100 X 25 25, 4/16/84 ,
l 101 X 2E 15, 3/29/84
! 102 X 2B 15, 3/29/84 103 X 15 18, 4/02/84
) 104 X 2E 17, 4/01/84 l 105 - X 2E 25,.4/16/84 106 I 2E -
25, 4/16/84 107 X 2E 18, 4/02/84 1 108 I 2C 15, 3/29/84 1
109 X 2D 45, F/29/84 L26sd3
! l
.-.:-.-=-.. _ - - . - . - . _ -. - _. -. : --...- - a , .
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
. 110 X 2B 17, 4/01/84 111 X 2D 18, 4/02/84 112 X 2A 15, 3/29/84 I 113 X N/A (Resolved) 15, 3/29/84
- 114 X 2B 18, 4/02/84 115 X 2D 17, 4/01/84 116 K 2B 15, 3/29/84 117 X N/A (Resolved) 18, 4/02/84 118 X 2D 16, 3/31/84 l
119 X 2B 15, 3/29/84 120 X 2B 25, 4/16/84 121 X N/A (Resolved) 15, 3/29/84
! 122 X 2D 17, 4/01/84 123 X 2D 18, 4/02/84 124 X 2C 18, 4/02/84-125 X N/A (Resolved) 18, 4/02/84 126 X 2D 15, 3/29/84 l 127 I 2G 17, 4/01/84
! 128 X 2E 26, 4/24/84 129 X 2B 15, 3/29/84
! 130 X N/A (Resolved) 15, 3/29/84 131 X 2B 26, 4/24/84 l 132 X 2B 15, 3/29/84 133 X 2D 18, 4 02/84
- 134 X 2D 17, 4/01/84 i 135 X N/A (Resolved) 18, 4/02/84 136 X 2D 15, 3/29/84
! 137 X 2B 15, 3/29/84
! 138 K 2D 15, 3/29/84
! 139 X ic 15, 3/29/84 140 X 2D 18, 4/02/84 141 X 2F 17, 4/01/84 i 142 - X 2F 15, 3/29/84
! 143 X 2G -
15, 3/29/84-144 X 2B 15.-3/29/84 l 145 X 2F 17, 4/01/84 l 146 X 2E 15, 3'/29/84 L26sd4
PROBLEM SHEET LISTING
, ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 147 X 3B 16, 3/31/84 148 X 3A 17, 4/01/84 149 .I 3B 18, 4/02/84
~150 X 2G 1-7, 4/01/84 151 X 3B 25, 4/16/84 152 X 2E 16, 3/31/84 153 I 2H 17, 4/01/84 l
154 X 2D 16, 3/31/84 155 K 2D 18, 4/02/84 156 X 2D 17, 4/01/84 157 X 2D 17, 4/01/84 158 X 2D 17, 4/01/84 159 X 2D 16, 3/31/84 160 X 2E 21, 4/08/84 161 X 2E 18, 4/02/84 162 X 2D 16, 3/31/84 163 X 2D 16, 3/31/84 164 X 2B 18, 4/02/84 i
O 165 X 2D 17, 4/01/84
) 166 X 2H 26, 4/24/84 167 X 2B 17, 4/01/84 t
168 X 2B 21, 4/08/84 169 X 2D 18, 4/02/84
]
.l 170 X 2E 16, 3/$1/84 171 X 2D 16, 3/31/84 172 X 2B 17, 4/01/84 l
173 X 2D 21, 4/08/84 l
174 X 2E 17, 4/01/84 175 X 3B 21, 4/08/84 176 X 2B 17, 4/01/84
- 177 X 2D 25,-4/16/84 178 X 2D 17, 4/01/84 179 _
X 2D 16, 3/31/84 180 X 2A 17, 4/01/84 j 181 X 2A 26, 4/24/84
! 182 X 2D 17, 4/01/84 183 X 2D 18, 4/02/84 L26sd5
, - - - - - - ,-. v m,y. ,y, - -
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PROBLEM SHEET LISTING ITEM ND!BER REVIEWED BY RPD PRIORITY REVISION, DATE 184 X 2D 16, 3/31/84 185 X 2B 18, 4/02/84 186 .X N/A (Resolved) 18, 4/02/84 187 K 2G 18, 4/02/84 188 X 3B (Resolved) 15, 3/29/84 189 X 2H 18, 4/02/84 190 X 2D 20, 4/06/84 191 X 2D 18, 4/02/84 192 X 2D 16, 3/31/84 193 X 2D 16, 3/31/84 194 X 2D 13, 4/02/84 195 X 2D 26, 4/24/84 196 X 2B 16, 3/31/84
~
197 X 2B 26, 4/24/84 198 X IC 16, 3/31/84 199 X 3B 18, 4/02/84 200 X 2G 18, 4/02/84 201 X 2B 22, 4/09/84 202 X 3B 18, 4/02/84 203 X 2D 22, 4/09/84 204 X 2H 18, 4/02/84 205 X 2H 16, 3/31/84 206 X 2G 16, 3/31/84 207 X 2H 18, 4/62/84 208 X 2H 18, 4/02/84 209 X 2H 15, 3/29/84 210 X 2G 18, 4/02/84 211 X 3B 26, 4/24/84 212 X 2D 18, 4/02/84 213 X IC 16, 3/31/84 214 X 3B 21, 4/08/84 215 X 3B 16, 3/31/84 216 _
X 33 18, 4/02/84 217 X 3B . 21, 4/08/84 218 X 2H 26, 4/24/84 219 X 2I 16, 3/31/84 220 X 3A 18, 4/02/84 l L26sd6 l
t
PROBLEM SHEET LISTING ITEM NL'MBER REVIE'a'ED BY RPD PRIORITY REVISION, DATE 221 X 2D 16, 3/31/84 222 X 3B 26, 4/24/84 223 'X '2B 18, 4/02/84 224 X 3B 16, 3/31/84 225 X 2D 25, 4/16/84 226 X 3A 18, 4/02/84 227 X 3B 21, 4/08/84 228 X 3B 26, 4/24/84 229 X 2B 21, 4/08/84 230 X 2B (Resolved) 15, 3/29/84 231 X 3B 17, 4/01/84 232 X 3B 17, 4/01/84 233 X 2E 25, 4/16/84 234 X 3A 25, 4/16/84 235 X 2B 18, 4/02/84 2.' 6 X 2B 17, 4/01/84 2J7 X 2D 18, 4/02/84 238 X 2D 18, 4/02/84 239 X 2D 18, 4/02/84
_2fo X 2D 17, 4/01/84 241 X 2D 26, 4/24/84 242 X 3B 18, 4/02/84 243 X 3B 18, 4/02/84 2_44 X 2B 18, 4 02/84 245 X 2B 17, 4/01/84 246 X 2B 18, 4/02/84 247 X 2B 18, 4/02/84 248 X 2D 18, 4/02/84 l 249 X 2D 22, 4/09/84 250 X 2B 18, 4/02/84 251 X 2F 18, 4/02/84 252 X *3B 18, 4/02/84 ,
l 253 - X 2C 18, 4/0:/84 254 X 3B -
18, 4/02/84
- Prioritv chanced fres IA per J. C. Roberts 3/27/84.
Jo L26sd7
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 255 X 2E 18, 4/02/84 256 X 2E 27, 4/26/84 256-1 X Sub, 2E 18, 4/02/84 257 x 2B 17, 4/01/84 258 X 3B 18, 4/02/84 259 X 3B 26, 4/24/84 260 X 3B 18, 4/02/84 261 X 3A 18, 4/02/84 262 X IC 16, 3/31/84 263 X 2D 17, 4/01/84 264 X 2B 17, 4/01/84 265 X 2D 18, 4/02/84 266 X 2B 17, 4/01/84 267 X 2B 18, 4/02/84 268 X 2F 18, 4/02/84 269 X 2D 18, 4/02/84 270 X 2E 22, 4/09/84 271 X 3B 26, 4/24/84 272 X 2D 22, 4/09/84 273 X 3B 26, 4/24/84 274 X 2D 18, 4/02/84 275 X 2B 18, 4/02/84 276 X 2D 18, 4/02/84 277 X 2B 18, 4/02/84 278 X 2D 18, 4/02/84 279 X 2D 17, 4/01/84 280 X 2D 18, 4/02/84 281 X 2E 25, 4/16/84 282 X 2E 17, 4/01/84 l
283 X 2E 17, 4/01/84
{
284 X 3B 26, 4/24/84 285 X IC 18, 4/02/84 286 . X 2P 18, 4/02/84 287 X 2D - 18, 4/02/84 288 X 2D 18, 4/02/84 b 289 X 2E 18, 4/02/84 l 290 X 'I 18, 4/02/84 l
l L26sd8
. _ _ 1_ _ _. __ - . _ . __ __. . -
PROBLEM SHEET LISTING l -
ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE l 291 X *3B 18, 4/02/84 292 X 1B 18, 4/02/84 293 X 1B 18, 4/02/84 294 X 2B J8, 4/02/84 295 X 3B 26, 4/24/84 296 X 3B 26, 4/24/84 297 X 2E 26, 4/24/84 298 X 2E 18, 4/02/84 299 X 2B 25, 4/16/84 300 X 3A 18, 4/02/84 301 X 2E 18, 4/02/84 302 X 2D 26, 4/24/84 303 X 2B 18, 4/02/84 304 X 2D 21, 4/08/84 305 X 3B 26, 4/24/84 306 X IB 26, 4/24/84 307 X 2B 18, 4/02/84 308 X IB 18, 4/02/84
() 309 310 X
X 2A 2A 18, 4/02/84 18, 4/02/84 311 X 2E 18, 4/02/84 312 X 2B 22, 4/09/84 313 X 2B 18, 4/02/84 314 X 2B 18, 4/02/84 315 X 2B 18, 4/02/84 316 X 21 26, 4/24/84 317 X 2E 18, 4/02/84 318 X 3B 18, 4/02/84 319 X 2E 21, 4/08/84 320 X 2E 18, 4/02/84 321 X 3B 26, 4/24/84 322 X 2E 18, 4/02/84 323 X 2B 18, 4/02/84 324 X 2E 18, 4/02/84 325 X 3B 26, 4/24/84 O
- Priority chanced from 1A per J. C. Roberts 3/27/84. ,,
126sd9
PR03*EM SHEET LISTING
' . l
- ITEM NWBER REVIEWED BY RPD PRIORITY REVISION, DATE
! 326 X 3B 26, 4/24/84 327 X 3B 18, 4/02/84 f
5 328 .X 2D 26, 4/24/84 329 X IC 18, 4/02/84 330 X 3B 26, 4/24/84
} 331 X 3B 26, 4/24/84 332 X 3B 21, 4/08/84 I 333 X 3B 26, 4/24/84 334 X 2D 18, 4/02/84 I 335 X 2B 18, 4/02/84 336 X 2D 18, 4/02/84 l 337 X 2D 18, 4/02/84 338 X 2B 18, 4/02/84 l ~
I 339 X 3B 26, 4/24/84
, 340 X 3B 26, 4/24/84 341 X 3B 18, 4/02/84
! 342 X 2B 19, 4/05/84 l 343 X 3B 26, 4/24/84 344 X IB 19, 4/05/84 345 X 2B 21, 4/08/84 346 X 2D 26, 4/24/84 347 X 2B 21, 4/08/84 348 X 2D 26, 4/24/84 349 X 2D 21, 4/D8/84 i 350 X 2B 21, 4/08/84 351 X 2D 21, 4/08/84 1
352 X 2D 21, 4/08/84 353 X 2D 21, 4/08/84-354 X 2D 21,'4/08/84 355 X 2D 21, 4/08/84 356 X 2D 21, 4/08/84 I 357 X' 2B 21, 4/08/84
! 358 X 2D 21, 4/08/84 q 359 X 2B 21, 4/08/84
~
360 X 2B 21, 4/08/84 361 X 2D '21, 4/08/84 j 362 X 2B 26, 4/24/S4 c 363 X 2D 21, 4/08/84
! L26sd10 t
_ ..-..._,x.. . . . _ _ . - . .__.,._-i _
PROBLEM SHEET LISTING ITEM ND'3ER REV'_F.iED BY RPD PRIORITY REVISION, DATE 364 X 2B 21, 4/08/84 365 X 2D 24, 4/13/84 366 .X 2D 24, 4/13/84 367 X 2D (Resolved) 26, 4/24/84 368 X 3B (Resolved) 26, 4/24/84 369 X 2D 26, 4/24/84 370 X 3A 24, 4/13/84 371 X 2D 24, 4/13/84 372 X 3B 26, 4/24/84 800 X 3B 18, 4/02/84 801 X 3B 18, 4/02/84 802 X 3B 18, 4/02/84 803 X 3B 18, 4/02/84 804 X 3B 18, 4/02/84 805 X 3B 24, 3/13/84 806 X 3B 18, 4/02/84 807 X 3B 18, 4/02/84
\ 208 X 3B 18, 4/02/84 j 809 X 3B 18, 4/02/84 810 X 3B 18, 4/02/84 811 X 3B 18, 4/02/84 812 X 3B 23, 4/10/84 813 X 3B 22,4/b9/84 31 t. X 3B 22, 4/09/84 815 X 3B 22, 4/09/84 816 X 33 23, 4/10/84 517 X 3B 23, 4/10/84 518 X 3B 23, 4/10/84 819 X 3B 23, 4/10/84 820 X 3B 23, 4/10/84 821 X 3B 24, 4/13/84 S22 _ X 3B 24, 4/13/84 323 X 3B . 24, 4/13/84 32.4 X 3B 24, 4/13/84
%d !;5 : 3B 24, 4/12/S4
- . isa..
. PROBLEM SHEET LISTING ITEM NUMBER RE'.'IEWED BY RPD PRIORITY REVISION, DATE 826 X 3B 25, 4/16/84 827 X 3B 25, 4/16/84 828 X 3B 25, 4/16/84 829 X 3B 25, 4/16/84 830 X 3B 25, 4/16/84 831 X 3B 25, 4/16/84 832 X 38 25, 4/16/84 1
4 O
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l
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~ . _ _ _ _ _ _ .
of TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 048 Priority: 2H Rav Patterson /
- i Identified By Date Responsible Supervisor Tech S'pec
Reference:
3.2.2, 3/4.3.6 Tech Spec Page: 3/4 2-5, 3/4 3-49 Problem
Title:
Maximum Extended Operating Domain j 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):
j Technical Specification 3.2.2 contains the limits on the APRM flow-biased scram and rod block setpoints. GE is performing Maximum Extended Operating Domain (MEOD) and Increased Core Flow (ICF) analyses which are expected to allow these APRM setpoints to be revised to accommodate operational
~
enhancements.
l 2. Safety Significance:
None. The extension of the operating domain which includes the MEOD and ICF analyses will remain within the established design criteria.
O
- 3. Anticipated Resolution: ,
A Technical Specification revision will be prepared to incorporate the ME0D
. and ICF requirements when these analyses are completed. GE is expected to l
provide the NRC with a licensing topical report to support the analyses and l Technical Specification submittal.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: / l Individual Notified Date ' Time i
- O Rev. 27, 4/26/84-Misd86
.- *- - , ,_ - - - , w-- . --
-$ w
e 1
4
- f
)
- Page 2 TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) j Item Number 048 Priority 2H l
1
- 5. Disposition:
1 Items Closed: (How)
/
l Date Time 1
i c: J. E. Cross i R. F. Rogers j
i 1
i.
1 I -
1 l
I l
4 1
i I
k I -
i Rev. 27, 4/26/84
,,, . n -.
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- . . .- - --- - =- -- . - _ - -. . - . - -
TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 256 Priority: 2E _
- /3-15-64 f Identified By Date Responsible Supervisor
! Tech Spec
Reference:
3.7.4, Bases 3/4.7.4. 3/4.5.1, 3/4.5.2, and 2.2.1
, Tech Spec Page: 3/4 7-13, B3/4 7-2, and B3/4 5-1 Problem
Title:
Generic Bases Problems
! 1. Problem Description (Tech Spec. FSAR, SER, GE Design, Other):
Minor typographical errors were found and identified on pages 3/4 7-13 and B 3/4 7-2 of the GGNS Technical Specifications. Also, the values for high i pressure core spray (HPCS) operating pressures were not revised in Bases 3/4.5."1 and 2 when those values were changed in Technical Specification 4.5.1 i by Amendment 9.
l
} 2. Safety Significance:
l None: These are minor typograp'tical errors and inadvertent omissions which do affect plant safety or operational requirements.
4 l 3. Anticipated Resolution:
I PropeseaTechnicalSpecificationchangetocorrectthetypographica$erroron page 3/4 7-13 from "maintanence" to "naintenance" and page B3/4 7-2. from i "enusre" to " ensure." Also propose a change to correct the HPCS operating '
1 pressures in Bases 3/4.5.1 and 2 to be consistent with the values in Technical i Specification 4.5.1 if necessary.
t i 4 NRC Response to Item (NRR/IE):
1 NRC Notified: /
}
Individual Netified Date Time 4
i e
t-s.
Rev. 27, 4/24.5 i 's ).
. (E e- -
, - e. . - . ' _ _ _ - - . ,_ , .
- J~ k ,
. (-
9
(
. Page 2 TECHNICAL SPECIPICATION PROBLEM SHEET (CONT'D)
Item Number: 256 Priority: 2E
- r
- 5. Disposition
i Items Closed: (How) t
/ ,
Date Time
References:
TSRT-84/0143, Page 9
- TSRT-84/0447, Pages !. - 9 TSRT-84/0649, Page 11 ,
TSRT-84/0651, Pages 12 and 13 TSRT-84/055i., Page 5 and 6 I TSRT-84/OSS2, Page 1 cc: J. E. Cross R. F. Rogers i
I s
1
, V
' O, i
- 9, \'s.
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- Rev. 27, 4/26/84
- _.,y,.
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i ,
ia
- " TECH SPEC PRIORITY" ;
l (O MEMO TO: Tech Spec Review Personnel e
i FROM: C. L. Tyrone
SUBJECT:
Rev. M to Technical Specification Problem Sheet TSRT: 84/ 0 %AA
(.
)i DATE: hqi\ 1R \0SA 4
The following changes / additions are to be incorporated into the Tech Spec Problem Sheets:
ITEM NUMBER CHANGES / ADDITION
%% Remove Rev.~ . Insert Rev. A 6 MA Remove Rev. ,* Insert Rev. A B
- 395 Remove Rev. , Insert Rev. A S
%% Remove Rev.4 , Insert Rev. A b
!(O Am ae= ave Rev - tasert "ev a s hS6 Remove Rev. . Insert Rev. A B bSh Remove Rev. . Insert Rev. - A6 3 go Remove Rev. , Insert Rev. g g 3Sg Remove Rev. , Insert Rev. g 6 36A Remove Rev.- , Insert Rev. g g j Ch h3 Remove Rev.". Insert Rev. 36 1 Remove Rev. . Insert Rev.
1-Remove Rev. , Insert Rey, ie i-4
- C. L. Tyrone g
b CLT: sad Attachment
. cc: S. H. Hobbs (w/1)
- File (Tech Spec Records) (w/1)
M2sd1 1
, -.___ _ _ _ _ . . . . . _ _ . . . . . _ . . . , . , _ . , , _ , . . . . _ , , _ _ . , _ __......r.
.,_...-..-..i
TSRT-84/ D 4 %
PROBLEM SHEET LISTING AS OF h o b s M % %%
(O ITEM NUMBER REVIEWED BY RPD PRIORITY
' o =-
REVISION, DATE 001 X IB 15, 3/29/84 002 X 2D 26, 4/24/84 003 X 2D 17, 4/01/84 004 X 2E 22, 4/09/84 i
005 X 13 15, 3/29/84 006 X 2D 21, 4/08/84 007 X 2F 15, 3/29/84
! 008 X 2H 17, 4/01/84 009 X 2B 25, 4/16/84 010 X 2B 15, 3/29/84 011 X 2B 15, 3/29/84 012 X 2B 26, 4/24/84 013 X 2D 26, 4/24/84 014 X 2B 21, 4/08/84 015 X 1B 17, 4/01/84
{ ~ 016 I 1B 15, 3/29/84
(
017 X 2D 15, 3/29/84
~
018 I 3B 15, 3/29/84 019 I 2B 25, 4/16/84 i
020 X 2B 17, 4/01/84 021 X IC 15, 3/29/84 022 X 2A 17, 4/01/84 023 X 2B 15, 3/29/84 024 X 2B 18, 4/02/84 025 I 3B 26, 4/24/84~
i 026 X 2D 15, 3/29/84 027 X 2E 15, 3/29/84 I
'028 X 2B i 15, 3/29/84 029 I 3B 26, 4/24/84 030 X 2D 17, 4/01/84 I 031 X 2D 17, 4/01/84 l
032 X 2B 21, 4/08/84 033 X IB 18, 4/02/84 (O o3' x tc 18. '/o2'a' 035 I 2C 15, 3/29/84 L26sd1 n-
'~
._.._ ___ ____; _ .1- - . _ -
s PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 036
(
( X 2D 26, 4/24/84 037 I IC 15, 3/29/84 038 X IC 15, 3/29/84 039 X 2G 17, 4/01/84 040 X 2F 17, 4/01/84 041 X 2B 21, 4/08/84 042 X 3B 26, 4/24/84 043 X 2D 15, 3/29/84 044 X 2B 26, 4/24/84 045 X 2B 17, 4/01/84 046 X 2F 15, 3/29/84 047 X 2B 15, 3/29/84 048 X 2H 27, 4/26/84 049 I 2B 18, 4/02/84 050 X 2B 17, 4/01/84 051 X 2D 15, 3/29/84 052 X 2E 15, 3/29/84 053 X 2E 17, 4/01/84 i i 054 X IB 21, 4/08/84 055 X 2D 15, 3/29/84
- 056 I 3B 21, 4/08/84 057 I 2B 17, 4/01/84 058 I 2D 17, 4/01/84 059 I 2D 17, 4/01/84 060 X 2B 15, 3/29/84 061 X 2D 15, 3/29/84 062 X 2E 18, 4/02/84 063 X 2E 17, 4/01/84 064 X 3B 26, 4/24/84 4 065 I 3B 26, 4/24/84 066 X 2D 22, 4/09/84 067 I 2D 15, 3/29/84 068 X 3B 15, 3/29/84 069 X 3B 26, 4/24/84 070 X 3B 26, 4/24/84
(} 071 072' X
X 2D 2D 26, 4/24/84 17, 4/01/84 L26sd2
i -
i -
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
( 073 X 2B 18, 4/02/84 074 I 2D 17, 4/01/84 075 I 2B 17, 4/01/84 1
076 X IB 18, 4/02/84 077 I 2B 21, 4/08/84 078 X in 15, 3/29/84 079 I 2E 15, 3/29/84 4
080 I N/A (Resolved) 15, 3/29/84 081 X 3A 15, 3/29/84 l 082 I 3A 15, 3/29/84 083 I 2B 22, 4/09/84 l 084 I 3A 15, 3/29/84 085 I 2D 20, 4/06/84 086 X 2D 18, 4/02/84 087 I 2D 17, 4/01/84 088 I 2D 17, 4/01/84 089 X 2D 15, 3/29/84 090 X 2D 17, 4/01/84
(( I 091 X 2D 15, 3/29/84 092 I 2D 18, 4/02/84 3
093 I 2E 22, 4/09/84 094 I 3B 26, 4/24/84 095 I 2E 22, 4/09/84 096 X 2E 25, 4/16/84 097 X 2E 15, 3/29/84 098 I 2G 15, 3/29/84 099 I 2G 21, 4/08/84 i 100 X 2B 25, 4/16/84 j 101 1 2E 15, 3/29/84 102 X 2B 15, 3/29/84 103 I 1B 18, 4/02/84 104 X 2E 17, 4/01/84 4
105 X 2E 25, 4/16/84 ;
106 X 2E 25, 4/16/84
-107 I 2E 18, 4/02/84 108 I 2C 15, 3/29/84
) 109 I 2D 45, S/29/84 L26sd3 i
il '
I PROBLEM SHEET LISTING i*
j . ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE l
( 110 X 2B 17, 4/01/S4 111 X 2D 18, 4/02/84 112 X 2A 15, 3/29/84 113 X N/A (Resolved) 15, 3/29/84 .
114 X 2B 18, 4/02/84 115 I 2D 17, 4/01/84 116 I 2B 15, 3/29/84 117 X N/A (Resolved) 18, 4/02/84 118 X 2D 16, 3/31/84 119 X 2B 15, 3/29/84 120 X 2B 25, 4/16/84 121 X N/A (Resolved) 15, 3/29/84 !
122 X 2D 17, 4/01/84 123 X 2D 18, 4/02/84 124 X 2c 18, 4/02/84 125 I N/A (Resolved) 18, 4/02/84 126 X 2D 15, 3/29/84 127 I 2G 17, 4/01/84 k 128 X 2E 26, 4/24/84 129 X 2B 15, 3/29/84 ,
130 X N/A (Resolved) 15, 3/29/84 131 X 25 26, 4/24/84 132 X 2B 15, 3/29/84 133 I 2D 18, 4/02/84
, 134 X 2D 17, 4/01/84 135 X N/A (Resolved) 18, 4/02/84 136 X 2D 15, 3/29/84 137 X 2B 15, 3/29/84 138 X 2D 15, 3/29/84 139 X 1C 15, 3/29/84 140 X 2D 18, 4/02/84 141 X 27 17, 4/01/84 142 X 2F 15, 3/29/84 143 X 2G 15, 3/29/84 144 X 2B 15, 3/29/84 145 X 2F 17, 4/01/84
- 146 X 2E 15, 3/29/84 L26sd4 I n l
-.. - - _ . . .=.. ,. ... . .. .. - .. . ... ~ .... . -... .- . - . - . - - - -. . - . - . -
PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 147 X 35 16, 3/31/84
() 148 I 3A 17, 4/01/84
- 149 X 3B 18, 4/02/84
'150 X 2G 17, 4/01/84 151 1 3B 25, 4/16/84 152 X 2E 16, 3/31/84 153 X 2H 17, 4/01/84 154 X 2D 16, 3/31/84 155 X 2D 18, 4/02/84 156 X 2D 17, 4/01/84 157 X 2D 17, 4/01/84 158 X 2D 17, 4/01/84 159 X 2D 16, 3/31/84 ,
160 X 2E 21, 4/08/84 161 X 2E 18, 4/02/84 162 X 2D 16, 3/31/84 163 X 2D 16, 3/31/84 i 164 X 2B 18, 4/02/84
(( ) 165 166 1
I 2D 2H 17, 4/01/84 26, 4/24/84 167 1 2B 17, 4/01/84 168 I 2B 21, 4/08/84 f 169 I 2D 18, 4/02/84 170 X 2E 16, 3/31/84 171 X 2D 16, 3/31/84 172 X 2B 17, 4/01/84 l
173 I 2D 21, 4/08/84 174 X 2E 17, 4/01/84 175 I 35 21, 4/08/84 176 I 2B 17, 4/01/84 I 177 X 2D 25, 4/16/84 l 178 I 2D 17, 4/01/84 179 X 2D 16, 3/31/84 180 X 1A 17, 4/01/84 181 X 2A 26, 4/24/84 182 X 2D 17, 4/01/84
(() 183 I 2D 18, 4/02/84 l
L26ed5 i
. i
{:
i PROBLEM SHEET LISTING
, ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 184 X
( 2D 16, 3/31/84 185 I 2B 18, 4/02/84 186 X N/A (Resolved) 18, 4/02/84 187 X 2G 18, 4/02/84 188 I 3B (Resolved) 15, 3/29/84 j 189 I 2H 18, 4/02/84 4
7 190 X 2D 20, 4/06/84 3
191 X 2D 18, 4/02/84 192 X 2D 16, 3/31/84
{
193 X 2D 16, 3/31/84
- 194 X 2D 18, 4/02/84 195 1 2D 26, 4/24/84
! 196 X 2B 16, 3/31/84 1
- 197 I 2B 26, 4/24/84 l 198 X IC 16, 3/31/84 i 199 I 3B 18, 4/02/84
) 200 X 2G 18, 4/02/84 201 X 2B 22, 4/09/84
( 202 X 3B 18, 4/02/84 l 203 X 2D 22, 4/09/84
, 204 X 2H 18, 4/02/84 205 X 2H 16, 3/31/84 l 206 I 2G 16, 3/31/84 207 I 2H 18, 4/02/84
! 208 X 2H 18, 4/02/84 i
209 I 2H 15, 3/29/84 210 X 2G 18, 4/02/84 j 211 X 35 26, 4/24/84 1
212 X 2D 18, 4/02/84 213 X IC 16, 3/31/84 214 X 3B 21,~4/08/84'
! 215 X 38 16, 3/31/84 ,
216 X 35 18, 4/02/84 217 I 35 21, 4/08/84 218 I 2H 26, 4/24/84 219 I 21 16, 3/31/84 O. 220 X 3A 18, 4/02/84 L26sd6 n
. ~ - . , . . , - . . . - . . - - -. .-. -- . . . - + -- . a . s -.
1 PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE 221 (O 222 X
X 2D 3B 16, 3/31/84 26, 4/24/84 223 X 2B 18, 4/02/84 224 X 3B 16, 3/31/84 l 225 I 2D 25, 4/16/84 !
226 X 3A 18, 4/02/84 !
i 227 I 3B 21, 4/08/84
! 228 I 3B 26, 4/24/84 j 229 I 25 21, 4/08/84 230 X 2B (Resolved) 15, 3/29/84 231 X 35 17, 4/01/84 l 232 X 35 17, 4/01/84 l 233 X 2E 25, 4/16/84 234 X 3A 25, 4/16/84 235 I 2B 18, 4/02/84 236 I 2B 17, 4/01/84 ;
- 237 X 2D 18, 4/0
- '/84 t
238 X 2D 18, 4/02/84 239 I 2D 18, 4/02/84 240 X 2D 17, 4/01/84 241 X 23 26, 4/24/84 242 I 3B 18, 4/02/84 243 X 3B 18, 4/02/84 244 I 25 18, 4/02/84 245 I 2B 17, 4/01/84 246 1 2B 18, 4/02/84 1 247 I 25 18, 4/02/84 f 248 I 2D 18, 4/02/84 l 249 I 2D 22, 4/09/84 250 X 2B 18, 4/02/84 l 251 X 2F 18, 4/02/84 l 252 X *3B 18, 4/02/84 i
1 253 I 2C 18, 4/02/84 254 X 3B 18, 4/02/84 l
- Priority changed from 1A per J. C. Roberts 3/27/84.
L26sd7
- . . _ . .------..,0
, PROBLEM SHEET LISTING i
. ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE l
( 255 X 2E 18, 4/02/84 256 X 2E 27, 4/26/84 4
256-1 X Sub, 2E 18, 4/02/84 1 257 X 2B 17, 4/01/84 258 I 3B 18, 4/02/84 259 I 3B 26, 4/24/84 260 X 3B 18, 4/02/84
- 261 X 3A 18, 4/02/84 262 X IC 16, 3/31/84 263 X 2D 17, 4/01/84 264 X 2B 17, 4/01/84 265 X 2D 18, 4/02/84 266 I 2B 17, 4/01/84 1
267 X 2B 18, 4/02/84 268 X 2F 18, 4/02/84 l 269 I 2D 18, 4/02/84 270 X 2E 22, 4/09/84 271 X 3B 26, 4/24/84 272 X 2D 22, 4/09/84 273 I 3B 26, 4/24/84 274 X 2D 18, 4/02/84 l
275 I 2B 18, 4/02/84 276 I 2D 18, 4/02/84 277 I 2B 18, 4/02/84 i
278 I 2D 18, 4/02/84 279 I 2D 17, 4/01/84-280 X 2D 18, 4/02/84 281 X 2E 25, 4/16/84 282 X 2E' 17, 4/01/84 i 283 X 2E 17, 4/01/84 284 X 3B 26, 4/24/84
$ 285 I IC 18, 4/02/84 l 286 X 2D 18, 4/02/84 287 I 2D 18, 4/02/84
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288 I 2D 18, 4/02/84 I l
( 289 I 2E 18, 4/02/84 '
~290 X 2E 18, 4/02/84 L26sd8 m
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1 PROBLEM SHEET LISTING l
1
{ ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
( 291 I *3B 18, 4/02/84 J
292 I IB 18, 4/02/84 j 293 X IB 18, 4/02/84 294 I 2B 18, 4/02/84 295 I 3B 26, 4/24/84 296 I 3B 26, 4/24/84 l l 297 I 2E 26, 4/24/84 298 I 2E 18, 4/02/84 299 I 2B 25, 4/16/84 300 X 3A 18, 4/02/84 301 X 2E 18, 4/02/84 302 I 2D 26, 4/24/84 303 I 2B 18, 4/02/84 '
304 X 2D 21, 4/08/84 305 I 3B 26, 4/24/84 306 I 1B 26, 4/24/84 307 X 2B 18, 4/02/84 j 308 X IB 18, 4/02/84
( 309 X . 2A 18, 4/02/84 310 X 2A 18, 4/02/84 311 X 2E 18, 4/02/84 312 _
X 2B 22, 4/09/84 313 I 2B 18, 4/02/84 314 I 2B 18, 4/02/84 315 1 2B 18, 4/02/84 316 I 2I 26, 4/24/84 317 I 2E 18, 4/02/84 318 I 3B 18, 4/02/84 j 319 X 2E 21, 4/08/84
) 320 X 2E 18, 4/02/84 l
. 321 X 3B 26, 4/24/84
) 322 X 2E 18, 4/02/84
.l 323 X 25 18, 4/02/84 324 X 2E 18, 4/02/84 325 I 3B 26, 4/24/8'4 (O P 1 1ev es....d 1.e. ii.. 2. c. mes re 3/27/84.
L26sd9
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- PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
( 326 I 3B 26, 4/24/84 j 327 I 3B 18, 4/02/84 328 I 2D 26, 4/24/84 329 I 1C 18, 4/02/84 330 I 3B 26, 4/24/84
- 331 I 3B 26, 4/24/84 332 I 3B 21, 4/08/84 333 1 3B 26, 4/24/84 334 I 2D 18, 4/02/84 335 1 2B 18, 4/02/84 336 I 2D 18, 4/02/84 337 I 2D 18, 4/02/84 338 I 2B 18, 4/02/84 339 I 3B 26, 4/24/84 340 1 3B 26, 4/24/84 341 I 3B 18, 4/02/84 342 I 2B 19, 4/05/84 343 I 3B 26, 4/24/84
( 344 x 1B 19, 4/05/84
- 345 1 2B 21, 4/08/84 346 I 2D 26, 4/24/84
- 347 I 2B 21, 4/08/84 4
- 348 I 2D 26, 4/24/84 349 I 2D 21, 4/08/84
- 350 I 2B 21, 4/08/84 351 I 2D 21, 4/08/84 352 I 2D 21, 4/08/84 353 I 2D 21, 4/08/84 354 I 2D 21, 4/08/84 355 I 2D 21, 4/08/84 356 I 2D 21, 4/08/84 357 I 25 21, 4/08/84 358 I 2D 21, 4/08/84 359 I 25 21, 4/08/84 1
i 360 I 2B 21, 4/08/84 361 I 2D 21, 4/08/84
( 362 I 2B 26, 4/24/84 363 I 2D 21, 4/08/84 L26sd10 t
_ _ - = - _ __ __ _.
i i.. .
PROBLEM SHEET LISTING l 1
, ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE
( 364 X 2B 21, 4/08/84 I 365 X 2D 24, 4/13/84 366 X 2D 24, 4/13/84
! 367 X 2D (Resolved) 26, 4/24/84 368 X 3B (Resolved) 26, 4/24/84 l 369 X 2D 26, 4/24/84 370 X 3A 24, 4/13/84 371 X 2D 24, 4/13/84 372 X 35 26, 4/24/84 373 X 2G 28, 4/28/84 374 X 2B 28, 4/28/84 375 X 2E 28, 4/28/84 376 X 38 28, 4/28/84 377 X 38 28, 4/28/84 378 X 3B 28, 4/28/84 379 X 2E 28, 4/28/84 380 X 2D 28, 4/28/84 381 X 2D 28, 4/28/84
(
382 X 2H 28, 4/28/84 ;
I i 800 X 38 18, 4/02/84 801 X 3B 18, 4/02/84 j 802 X 3B 18, 4/02/84 803 X 38 18, 4/02/84 4
804 X 38 18, 4/02/84 805 X 3B 24, 3/13/84 l
- 806 X 3B 18, 4/02/84 807 X 38 18, 4/02/84 l
808 X 38 18, 4/02/84 l
809 X 35 18, 4/02/84 810 X 38 18, 4/02/84 l
i 811 X 35 18, 4/02/84 I 812 X 35 23, 4/10/84 813 X 3B 22, 4/09/84' i -
814 X 35 22, 4/09/84 815 X 35 22, 4/09/84 i
{
! 1,26sd11 l l
l PROBLEM SHEET LISTING ITEM NUMBER REVIEWED BY RPD PRIORITY REVISION, DATE i() 816 817 X
X 3B 3B 23, 4/10/84 23, 4/10/84 818 X 3B 23, 4/10/84 819 X 3B 23, 4/10/84 820 X 3B 23, 4/10/84 821 X 3B 24, 4/13/84 822 X 3B 24, 4/13/84 823 X 3B 24, 4/13/84 824 X 3B 24, 4/13/84 825 X 3B 24, 4/13/84 826 X 3B 15, 4/16/84 827 X 3B 25, 4/16/84 828 X 3B 25, 4/16/84 829 X 3B 25, 4/16/84 830 X 3B 25, 4/16/84 831 X 3B 25, 4/16/84 832 X 3B 25, 4/16/84
(( ) 833 X 3B 23, 4/28/84 (A)
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( TECHNICAL SPECIFICATION PROBLEM SHEET i I j Ites Number 373 Priority: 20 j I
NRR/PSB / f Identified By Date Responsible Supervisor l j Tech Spec
Reference:
Table 3.3.3-2 f
Tech Spec Page: 3/4 3-29 ,
1 Probles
Title:
Division 3 Undervoltaae Level (s) t
Division 3 bus does not have the same degraded voltage protection compared with Divisions 1 and 2. Only one level is provided, for Division 3 (72 percent). Divisions 1 and 2 have 90, 80, and 70 percent. f t
- i j 2. Safety Significance
(
l None. Design is in accordance with FSAR s.3.1.1.2.2, 8.3.1.1.4.2, Q4R 040.90, f and NEDO 10905.
l
- 3. Anticipated Resolutions
!M Ensure all auxiliary equipment can operate at 72 percent destaded voltage.
Consider design change and Technical Specification change if appropriate.
.k
{ 4. NRC Response to Ites (NRR/IE):
j NRC Notified: /
l Individual Notified Date Ties
- 5. Disposition:
}
l .
1 i
I '
j Itess Closed: (Now) I
- o
. l i
I
/ '
! Date Time j t l cc J. E. Cross l R. F. Rogers !
I j Rev. 2s, 4/2s/s4 .
4 i
F1sd283.4.5
l
( TECHNICAL SPECIFICATION PROBLEM SHEET Ites Number 374 Priority: 28 NRR/ICSB /
Identified By Date Responsible Supervisor Tech Spec
Reference:
Table 3.3.7.5-1 Tech Spec Page: 3/4 3-70 Frobles
Title:
Catesory 1 Accident Monitorina Instrumentation
I For NRR/ICSB, all Category 1 Accident Monitoring Instrumentation as identified by MP&L should be in the Technical Specifications.
- 2. Safety Significance:
None. Proposed change updates Technical Specification to latest commitments associated with Regulatory Guide 1.97 Revision 2. .
- 3. Anticipated Resolutions i
({} Determine from MP&L submittals to NRC on implementation of Regulatory Guide 1.97 Revision 2, which variables are Category 1. Revise Technical Specifications accordingly.
- 4. NRC Response to Ites (NRR/IE):
NRC Notified /
Individual Notified Date Time h
l l
Rev. 28, 4/28/84 l
F1sd283.4.6 , ,
j
i .
i I.
i f* !
( Page 2 I
a
._. . . _ . .s I
TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) j Item Nu'abdr - ' 374
- Priority: 2B l t j
- 5. Pisposition:
i 1
, Items closed: (How)
/
Date , Time 1
i
References:
AECM-82/0078 AECM-82/0317 AECM-82/0563 j- AECM-83/0286
(' O AECM-83/0486
4 cc: J. E. Cross j R. F. Roge:s i
1 f
i i
i j
i t
1 (O
i Rev. 28, 4/28/84 s
Plad283.4.7 .
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. - _ _ _ _ _ _ _ . . _ _ . _ . . _ - - - . ~ . _ _ . . _ , _ . . _ . . - _ . -
_._-_ _ - , - . . . . ,, _-- _. ___,. , , _ - - , _ . - . - - , - . . - - . . - _ - . _ . __1
i
(() TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 375 Priority: 2E NRR/CPB /
Identified By Date Responsible Supervisor Tech Spec
Reference:
B3/4.2.3 Tech Spec Page: B3/4 2-5 Problem
Title:
MCPR Bases Reference
j No reference is given in the Bases Figures 3.2.3-1 and 3.2.3-2. Probably 2
should reference NEDO-24011, Revision 4 (January 1982).
I i
j 2. Safety Significance:
i
, Not applicable.
- 3. Anticipated Resolution:
Determine reference and add to Bases.
.! (
j, 4. NRC Response to Item (NRR/IE)s
)
NRC Notified: /
i Individual Notified Date Time
- 5. Disposition:
i
! Items Closed: (How) l i ,
i l l 4
Date Time l l
Reference:
4/3/84. NRC Handout from Capra j cc: J. E. Cross R. F. Rogers l
(C:)
Rev. 28, 4/28/84 P1sd283.4.8 - .
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{'
Item Number: 376 Priority: 3B
- NRR/CSB /
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.6.6.1 Tech Spec Page: 3/4 6-46 i
i Problem
Title:
- NRC recommended changing 4000 cfm to 2300 cfm for Standby Gas Treatment Flow.
- 2. Safety Significance:
{ None. Technical Specification is correct.
I i
3.
Anticipated Resolution:
- No action is required.
II
- 4. NRC Response to Item (NRR/IE):
((}
- NRC Notified
- /
i Individual Notified Date Time
+
- 5. Disposition:
t Items Closed: (How) i i /
j -
Date Time i
Reference:
4/3/84, NRC Handout from Capra i
cc: J. E. Cross i
R. F. Rogers
(
Rev. 28, 4/28/84 l P1sd283.4.9 l
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' TECHNICAL SPECIFICATION PROBLEM SHEET
( (2) i 1
- Item Number
- 377 Priority: 3B '
NRR/RAB /
l Identified By Date Responsible Supervisor I
Tech Spec
Reference:
3/4.7.2 Tech Spec Page: 3/4 7-5 1
.1 Problem
Title:
Control Room In-Leakage
NRC noted that post-licensing tests indicate excessive control room in-leakage.
4
- 2. Safety Significance:
i Not applicable.
- 3. Anticipated Resolution:
This issue is associated with License Condition (Attachment 1, Item 3). No Technical Specification change is required.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
3 Items Closed: (How) i l
J
/ -
Date Time i
Reference:
4/3/84 NRC Handout from Capra 1 cc: J. E. Cross R. F. Rogers
!O
- Rev. 28, 4/28/84 i
Plad283.5
_,_ _;_., =
( TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 378 Priority: 3B
/
! Identified By Date Responsible Supervisor
)
Tech Spec
Reference:
3/4.6.6.1 and 3/4.6.6.3 Tech Spec Page: 3/4 6-46 and 3/4 6-55 f Problem
Title:
SBGT Flow Ambiguity
l 3/4.6.6.1 lists a flow rate not to exceed 4000 cfa. 3/4.6.6.3 lists a flow j rate of 4000 plus or minus 10 percent.
l 2. Safety Significance:
i None. Both Technical Specifications are correct.
I.
i
- 3. Anticipated Resolution:
The lower limit of 3/4.6.6.1 is based on dose vs. in-leakage. 3/4.6.6.3 is based on HEPA Filter efficiency testing. No action is needed.
l
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
) Individual Notified Date Time j 5. Dispositions i
i Items Closed: (How)
)
i l l Date Tims
Reference:
4/3/s4 NRC Handout from Capra t
ect J. E. Cross R. F. Rogers
!O Rev. 2s, 4/2s/s4 i
P1sd2s3.6 1
f l'
(, TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 379 Priority: 2E I
MP&L/IE /
Identified By Date Responsible Supervisor i Tech Spec
Reference:
3/4.6.2.3.d.3 and 3/4.6.1.3.d.3 Tech Spec Page: 3/4 6-16, 6-6; B3/4 6-1, 6-3 Problem
Title:
Air Lock Seal Decay Test
l Technical Specification specifies the leakage rate acceptance criteria in j terms of a 2 psig pressure drop in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.
- 2. Safety Significance:
j None. Clarification only.
I
- 3. Anticipated Resolution:
Modify Bases to clarify that a shorter time period may be used if it can be
! justified given instrument accuracies. This is in accordance with ANSI i N45.4-1972.
I 1
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
l l
i Items Closed (How) i
/
{ Date Time
! cc J. E. Cross R. F. Rogers i
] Rev. 28, 4/28/84 Pled 283.7 , ,
~ ~ ~
l i
( TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 380 Priority: 2D NRC/IE /
)
Identified By Date Responsible Supervisor
, Tech Spec
Reference:
3/4.10.1 Tech Spec Page: 3/4 10-1 Problem
Title:
Low Power Physics Test
l Technical Specification allows low power physics tests to be conducted with
-i the head removed and containment /drywell integrity not established. Region II states Technical Specification only allows low power physics tests as a part of open vessel testing.
- 2. Safety Significance:
i None. Clarification only.
4 3. Anticipated Resolution:
t i
I Discuss with NRR the purpose of this specification and revise Technical Specification as necessary.
- 4. NRC Response to Item (NRR/IE):
j NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (How) l 1 /
j Date Time 4
i cc J. E. Cross R. F. Rogers 1 ,
i
(
Rev. 28, 4/28/84 P1sd283.8 l
~_ _
l
- l l
s TECHNICAL SPECIFICATION PROBLEM SHEET Item Number: 381 Priority: 2D
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.3.1 Tech Spec Pager 3/4 3-1 4 Problem
Title:
Confusing Terms -
The terms " redundant channel" and " monitoring that parameter" result in some 1
confusion due to their use:
f
- a. Technical Specifications 4.3.1.3 (page 3/4 3-1), 4.3.2.3 (page 3/4 3-9),
and 4.3.3.3 (page 3/4 3-24) use the words " redundant channel" with
{
relation to response time testing. What does " redundant" mean? This is particularly critical to IRM, APRM, Main Steam Isolation Valve-Closure, Main Steam Line Flow-High, Main Steam Line Radiation-High, etc.
- b. Surveillance intervals of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> are allowed on some Technical
'(O Specifications, but not others. When the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is allowed, it is tied to the term " channels monitoring that parameter." The terminology is confusing and implies surveillance outage intervals are not allowed on equipment like Main Steam Line Radiation-High, APRM, IRM, Main Steam Line Isolation Valve-Closure, etc.
1 i 2. Safety Significance:
None. Technical Specification is confusing, but would not lead to non-conservative operation.
l
- 3. Anticipated Resolution:
Evaluate options of (a) rewording the individual Technical Specifications, or l
(b) defing the terms.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
(
Rev. 28, 4/28/84 l P1sd283.9 .
e Page 2 i %./
i TECHNICAL SPECIFICATION PROBLEM SHEET (CONT'D) l Item Number: 381 Priority: 2D 4
1 5. Disposition:
4 Items Closed: (How)
- i l
l l
1 Date Time 1
cc: J. E. Cross
- R. F. Rogers
-l(O i
i i
.i ii i
i i
i l
i
)
i r0 l Rev. 28, 4/28/84 i
! F1sd283.9.1 *
. - . ~ _ _ - . - . __- ._ . . - _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _
6 .
+
e TECHNICAL SPECIFICATION PROBLEM SHEET
' C:)
Item Number: 382 Priority: 2H I :
Identified By Date Responsible Supervisor Tech Spec
Reference:
3/4.4.1.1 Tech Spec Page: 3/4 4-1 .
Problem
Title:
Hydraulic Instability
GE, NRC, and BWR Owners are presently proposing resolutions to the hydraulic instability concerns associated with single recirculation loop operation.
- 2. Safety Significance:
GE is preparing a SIL to alert plants to the new data and recommend actions to avoid and control abnormal neutron flux oscillations, t
- 3. Anticipated Resolution:
Evaluate the concerns and propose Technical Specification change if
( .
appropriate.
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Notified Date Time
- 5. Disposition:
Items Closed: (Hov)
/
Date Time
Reference:
4/3/84, NRC Handout from Capra ces J. E. Cross j R. F. Rogers Rev. 28, 4/28/84 Plsd283.9.2 . .
-. 1 l
~
6, a i -
i lt i
TECHNICAL SPECIFICATION PROBLEM SHEET i
Item Number: 833 Priority: 3B
/
Identified By Date Responsible Supervisor Tech Spec
Reference:
4.8.1.1.2.d.2; FSAR Table 8.3-1, 8.3-2, 8.3-3 Tech Spec Page: 3/4 8-4; FSAR Tables 8.3-1, 8.3-2, 8.3-3 Problem
Title:
Reject of Diesel Generator largest Single Load i
AECM-83/0356, item 5 corrected the Technical Specification load reject values to conform with testable KW values associated with maximum pump loads.
- 2. Safety Significance:
Not applicable.
- 3. Anticipated Resolution:
Update FSAR tables to list the testable load reject values in addition to the motor nameplate ratings.
(O
- 4. NRC Response to Item (NRR/IE):
NRC Notified: /
Individual Hotified Date Time
- 5. Disposition:
Items Closed: (How)
/
Date Time
(
cc: J. E. Cross R. F. Rogers l
(
Rev. 28, 4/28/84 Pisd326