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d 475 ALLENDALE ROAD KING oF PRUSSIA. PENNSYLVANtA 19 0 6 1415 i
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' its fo wup of twgaeneerns that you brought to our n of these concems is disemed below.
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attention on.-
r 2 meter Display System is inopersle since i
You asserted that the M.
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ave made the data in the system invalid, i
VU responded with the following
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We referred these concem information:
7t vision 4 of the BWR Owner's (1)
The reviseo v,
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. were implemented after the SPDS l
f Emergency Gru
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. t change was the addition of 1
became operable.
containment control; i mility to monitor secondary variables, while not required by vas considered an enhancement.
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Prior to the implemenu
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the associated EOP chai
.sc,,cluded that with minor changes the SPDS
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j system would remain p
,nal wiu. espect to the original provisions of E
'7 and the revised EOPs. Various changes were $ $
l Supplement 1 of N'i "
made on the SPDS and v, tors were trained on any anomalies.
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(3)
Although new EOP entry conoitions have been added to the data these f
variables are not required to be part of the data. De fact that this data has s%t not been added to the SPDS does not effect the operability of the SPDS.
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l E 54 (4) A long term improvement in the SPDS is being planned, however, the $6h operation of the SPDS and nuclear safety is not compromised by use of the is 5 5.; l present EOPs and the SPDS. Es M _: s p..> f spps wo-s d 2& d t J 2. '" ' i ( $(m k l \\ g gi s m s - y " f W' ' "t " v " a ~37 j n Po&A~ A - ~ ?7 ~ 3-4 \\ pm \\ nA L M.MA Q n-4 e M ;gp h e92nos
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i Dt HUBBARD92-162 PDR 1
We have evaluated the licensee's response and conclude that the use of the SPDS has not been compromised by the issuance of new EOPs. Therefore, we consider your concern not l 4 substantiated and this issue closed. k Tnother concern expressed by you on June 11, 1991 was that there were cracks in the Millstone Unit 2 steam generator. On May 25,1991, Milhtone Unit 2 detected a significant primary to secondary leak and on May 26,1991 went into cold shutdowTi to repair leaks. g nis action was prior to your expressed concern on June 11, 1991. Derefore, we consider / this issue appropriately identified and handled by the licensee, and therefore, your concern closed. 3 i i ~ We appreciate you informing us of your concerns and feel that we have been responsive to ,p))/[%' / those concerns. Should you have any additional questions regarding these matters, please call me collect at (215) 337-5225. ff, ) et,,jkf ' g [ sw W 'Y Sincerely; t l - - qA y' n[ \\. I,,' n Edward Wenzinger, Chief g j p$ (D Reactor Projects Branch 4 h ^ yv < ec #p M(/RI-90d-0116-3/4 [t Allegation e, E. Conner l k' d E. Kelly 1 V W. Raymondfr. Shediosky EG&G Idaho Representative (roberts \\ frost) !f7 [ % p's 1% 4 u,r p 4, l i 4 M~d)sM y,9 i I
l ^ pMCuq +# ~k UNITED STATES i 8 NUCLEAR REGULATORY COMMISSION g 1; j REGloN I t g 475 ALLENDALE ROAD %g / KING oF PRUSSIA, PENNSYLVANIA 19406 1416 2"* SEP 0 51991 The NRC Region I office has completed its followup of two concerns that you brought to our attention on June 11,1990, and our resolution of these concerns is discussed below. You assened that the Millstone Unit 2 Safety Parameter Display System is inoperable since the revision of emergency operating procedures have made the data in the system invalid. We referred these concerns to the licensee, and NU responded with the following information: (1) The revised set of EOPs, based on Revision 4 of the BWR Owner's Emergency Group Guidelines (EPGs), were implemented after the SPDS became operable. The most significant change was the addition of containment control guidance. The ability to monitor secondary variables, while not required by NUREG-0737, was considered an enhancement. (2) Prior to the implementation of the new EOPs NU reviewed the SPDS agamst the associated EOP changes and concluded that with minor changes the SPDS system would remain operational with respect to the original provisions of Supplement 1 of NUREG-0737 and the revised EOPs. Various changes were made on the SPDS and operators were trained on any anomalies. (3) Although new EOP entry conditions have been added to the data these variables are not required to be part of the data. The fact that this data has not been added to the SPDS does not effect the operability of the SPDS. (4) A long term improvement in the SPDS is being planned, however, the operation of the SPDS and nuclear safety is not compromised by use of the present EOPs and the SPDS. b:e.,1c..a it:. :::r1 we de:ej in a;;r:.:cce wla De F:ceCgti ;r.ictmahon Act, excmgions.I2I 7 f0lA-7 dzd&_
e 2 We have evaluated the licensee's response and conclude that the use of the SPDS has not been compromised by the issuance of new EOPs. Therefore, we consider your concern not substantiated and this issue closed. Another concern expressed by you on June 11,1991 was that there were cracks in the Millstone Unit 2 steam generator. On May 25, 1991, Millstone Unit 2 detected a significant primary to secondary leak and on May 26,1991 went into cold shutdown to repair leaks. This action was prior to your expressed concem on June 11, 1991. Derefore, we consider this issue appropriately identified and handled by the licensee, and therefore, your concern closed. ] We appreciate you informing us of your concems and feel that we have been responsive to those concems. Should you have any additional questions regarding these matters, please call me collect at (215) 337-5225. I [f Edward Wenzinger, Chief cf Reactor Projects Branch 4 i bec: Allegation file, RI-90-A-Oll6-3/4 E. Conner E. Kelly W. Raymondfr. ShedlosL7 EG&G Idaho Representative (roberts \\ frost) i I 4 4 e s
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