ML17324B001
| ML17324B001 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/11/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| CON-FIN-A-6483, RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51080, TAC-51081, NUDOCS 8608050042 | |
| Download: ML17324B001 (15) | |
Text
0 Docket Nos.:
50-315 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216 11 JUL 1986
Dear Mr. Dolan:
Subject:
Conformance to Regulatory Guide 1.97, Revision 2 for D.
C.
Cook By letters dated February 28, 1985 and October 15, 1985, the Indiana and Michigan Electric Company provided detailed descriptions of conformance to Regulatory Guide 1.97, Revision 2 for the Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2.
Our contractor, EGSG Idaho, Inc., has performed a pre-liminary evaluation of the Cook submittals; the informal report is enclosed.
In this review, some exceptions to Regulatory Guide 1.97, Revision 2 have been found acceptable, some additional information is necessary for us to complete our review; and a number of exceptions are unjustified at this time.
It is requested that IMEC review the EGtIG informal report and pro-vide a response to the open items within 60 days of. receipt of this letter.
It is also requested that IMEC provide comments if the enclosed report in-cludes any incorrect assumptions or reflects a commitment which is beyond the intent in the above letters.
If there are any questions in this regard, please let us know.
Sincerely, B. J.
Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A
Enclosure:
As stated cc:
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Mr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Coomission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, DC 20036 Mayor, City of Bridgeman Post Office Box 366 Bridgman, Michigan
. 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
EGG-NTA-7282 CONFORMANCE TO REGULATORY GUIDE 1.97 DONALD C.
COOK NUCLEAR PLANT, UNIT NOS.
1 AND 2 A. C. Udy Pub11shed June 1986 EGhG Idaho, Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Comkss1on Mash)ngton, D.
C.
20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6483
ABSTRACT
~ Th1s EG&G Idaho, Inc., report rev1ews the subm1ttals for Regulatory Gu1de 1.97, Rev1s1on 3, for the Donald C.
Cook Nuclear Plant, Un1t Nos.
1 and 2, and 1dent1f1es areas of nonconformance to the regulatory gu1de.
Except1ons to Regulatory Gu1de 1.97 are evaluated and those areas where suff1c1ent bas1s for acceptab111ty 1s not prov1ded are 1dent1f1ed.
FOREWORD Th1s report 1s'suppl1ed as part of the "Program for Evaluat1ng L1censee/App11cant Conformance to RG 1.97,'e1ng conducted for the U.S.
Nuclear Regulatory Como1ss1on, Off1ce of Nuclear Reactor Regulat1on, D1v1s1on of PWR L1cens1ng-A, by EG&G Idaho, Inc.,
NRR and I&E Support Branch.
The U.S. Nuclear Regulatory Coma1ss1on funded the work under author1zat1on B&R 20-19-10-11-3.
Docket Nos.
50-315 and 50-316 TAC Nos.
51080 and 51081
CONFORMANCE TO REGULATORY GUIDE 1.97 DONALD C.
COOK NUCLEAR PLANT UNIT NOS. l AND 2
~ 1.
INTRODUCTION On December l7, l982, Gener1c Letter No. $2-33 (Reference l) was 1ssued by D.
G. E1senhut, 01rector of the D1v1s1on of L1cens1ng, Nuclear Reactor Regulat1on, to all 11censees of operat1ng reactors, appl1cants for operat1ng 11censes and holders of construct1on perm1ts.
Th1s letter 1ncluded add1t1onal clar1f1cat1on regard1ng Regulatory Gu1de 1.97, Rev1s1on 2 (Reference 2), relat1ng to the requ1rements for emergency response capab111ty.
These requ1rements have been publ1shed as Supplement No.
1 to NUREG-0737,
'THI Act1on Plan Requ1rements'Reference 3).
Ind1ana and H1ch1gan Electr1c
- Company, the 11censee for the Donald C.
Cook Nuclear Plant, prov1ded a response to Sect1on 6.2 of the gener1c letter on February 28, 1985 (Reference 4).
Th1s was rev1sed on October 15, 1985 (Reference 5).
These subm1ttals address Rev1s1on 3 of Regulatory Gu1de 1.97 (Reference 6).
Th1s report prov1des an evaluat1on of the mater1al subm1tted by the 11censee.
th1s report only addresses except1ons to Regulatory Gu1de 1.97.
The follow1ng evaluat1on 1s an aud1t of the l1censee's subm1ttals based on the rev1ew pol1cy descr1bed 1n the NRC reg1onal meet1ngs.
~
I 4.
Conta1nment sump level 5.
Steam generator level - narrow range 6.
Pressurizer level 7.
Conta1nment area rad1ation monitor - h1gh range 8.
Containment pressure - narrow range 9.
Auxiliary feedwater flow 10.
Refuel1ng water storage tank level ll.
Degrees of subcooling l2.
Core ex1t thermocouples 13.
Reactor coolant pump breaker status 14.
Safety in)ection pump breaker status 15.
Safety in)ection pump flow 16.
Steam generator blowdown radiat1on These var1ables meet the Category 1 'recomnendations cons1stent w1th the requ1rements for Type A variables, except as noted 1n Sect1on 3.3.
I 3.3 Exce tions to Re ulator Guide 1.97 The licensee 1dentif1ed the follow1ng deviat1ons and except1ons to Regulatory Gu1de 1.97.
These are d1scussed 1n the follow1ng paragraphs.
s1ngle fa1lure cr1ter1a.
The 11censee stages that th1s 1s acceptable because these recommendat1ons are not requ1red by NUREG-0737.
Me f1nd these dev1at1ons unacceptable for Type A var1ables.
NUREG-0737 does not requ1re th1s 1nstrumentat1on to be Type A.
The 11censee has determ1ned that th1s 1nstrumentat1on 1s Type A.
Therefore, the 11censee should prov1de Category l channels of 1nstrumentat1on for th1s var1able.
'3.3.4 Conta1nment Isolat1on Valve Pos1t1on Regulatory Gu1de l.97 receanends Category 1 1nstrumentat1on for th1s var1able.
Thus, th1s 1nstrumentat1on should be env1ronmentally qual1f1ed.
The l1censee 1dent1f1es valves VCR-ll, VCR-2l, and QCN-250 as be1ng 1ns1de conta1nment and not qual1f1ed for a des1gn bas1s event.
The l1censee states that the pos1t1on 1nd1cat1on for the redundant valves (VCR-l0, VCR-20 and QCH-350 respect1vely) can be used to ver1fy the 1solat1on funct1on as these are located 1n an access1ble m1ld env1ronment.
An operator can ver1fy the valve pos1t1on of any of these three redundant valves (VCR-lO, VCR-20 and QCH-350); however, QCN-350 does have the appropr1ate ind1cat1on 1n the control room.
Me f1nd th1s unacceptable.
Should a s1ngle fa1lure occur, the operator could not ver1fy conta1nment 1sola t1on.
Env1ronmental qual1f1cat1on has been clar1f1ed by the Env1ronmental Qual1f1cat1on Rule, 10 CFR 50.49.
The 11censee should therefore prov1de 1nstrumentat1on for th1s var1able that 1s env1ronmentally qual1f1ed 1n accordance w1th the prov1s1ons of 10 CFR 50.49 and Regulatory Gu1de 1.97.
3.3.5 Rad1at1on Level 1n C1rculat1n Pr1mar Coolant The 11censee 1nd1cates that rad1at1on level measurements to 1nd1cate fuel cladd1ng fa1lure are prov1ded by the post-acc1dent sampling system, wh1ch 1s be1ng rev1ewed by the NRC as part of the1r rev1ew of NUREG-0737, Item II.B.3.
3.3.8 Conta1nment H dro en Concentrat1on Regulatory Gu1de 1.97 recomnends 1nstrumentat1on for th1s var1able w1th a range of 0 to 30 percent for Cook's 1ce condenser conta1nment.
The 11censee has not 1dent1f1ed the range of the 1nstrumentat1on prov1ded for th1s var1able.
The NRC rev1ewed the acceptab111ty of th1s var1able as part of the1r rev1ew of NUREG-0737, Item II.F.l.6 and found 1t acceptable; however, the l1censee should 1dent1fy the range of th1s 1nstrumentat1on as requ1red by Sect1on 6.2 of Supplement No. l of NUREG-0737.
3.3.9 Rad1at1on Ex osure Rate Regulatory Gu1de 1.97 recoaeends 1nstrumentat1on for th1s var1able w1th a range of 10 to l0 R/hr.
The 11censee's 1nstrumentat1on for
-l 4
th1s var1able has a range of 10 to l0 mR/hr.
The l1censee states 1
4 that th1s range 1s adequate to mon1tor plant operat1on.
The 11censee has not shown an analys1s of rad1at1on levels expected for the mon1tor locat1ons.
The 11censee should show that the rad1at1on exposure rate mon1tors have ranges that encompass the expected rad1at1on levels 1n the1r locat1ons.
3.3.10 Residual Heat Removal Heat Exchan er Outlet Tem erature Regulatory Gu1de 1.97 reconmends 1nstrumentat1on for th1s var1able w1th a range of 40 to 350'F.
The 1nstrumentat1on prov1ded by the 11censee has a range of 50 to 400'F.
Thus, the range does not meet the recommended lower 11m1t.
Th1s deviat1on 1s 2.5 percent of the max1mum range.
Cons1der1ng 1nstrument accuracy and overall range, we cons1der th1s dev1at1on m1nor and, therefore, acceptable.
over 96 percent of the total pressurizer.
volume, not indicat1ng the volume 1n the hemispherical ends of the vessel.
The level 1ndicat1on covers the entire cyl1ndrical portion of the pressurizer.
Outside of the supplied instrument range, 1n the hemispherical vessel
- ends, the volume to level rat1o 1s not linear (approximately 4 percent of the total volume).
Me f1nd this dev1ation minor and, therefore, acceptable.
3.3.l4 Pressur1zer Heater Status Regulatory Guide 1.97 recommends mon1tor1ng the pressur1zer heater current w1th Category 2 1nstrumentation.
The 11censee mon1tors the heater c1rcuit breaker pos1tion.
Sect1on II.E.3.1 of NUREG-0737 requires a number of the pressur1zer heaters to have the capab111ty of be1ng powered by the urgency power sources.
Instrumentation 1s to be provided to prevent overload1ng an emergency power source.
Also, techn1cal specificat1ons are to be changed accord1ngly.
The Standard Technical Spec1fications for-Westinghouse
- reactors, Section 4.4.3.2, require that the emergency pressur1zer heater current be measured quarterly.
These emergency power suppl1ed heaters should have the current 1nstrumentat1on recomended by Regulatory Guide 1.97 or an alternate means of determ1ning the current be1ng drawn by the pressur1zer heaters.
3.3.15 3
Regulatory Gu1de 1.97 recommends 1nstrumentat1on for this var1able w1th a range from the top to the bottom of the tank.
The licensee's 1nstrumentation covers 74 percent of the total tank volume, stating that this 1s adequate to safety mon1tor the operation of this tank.
The 11censee d1d not relate the existing range to the range that needs to be ava1lable 1n the post-acc1dent cond1t1on.
The range should be adequate to (1) ensure that the sparger 1s covered and that suff1cient flu1d volume ex1sts to quench a des1gn bas1s pressurizer
- release, (2) to
3.3.17 Containment S ra Flow Regulatory Gu1de l.97 recomnends instrumentation for this variable with a range of 0 to ll0 percent of design flow.
The Cook stat1on has upper containment spray flow instrumentation,
- however, the licensee monitors the spray pump discharge pressure and the conta1nment
- pressure, stat1ng that with this instrumentation, the operator w111 be able to determ1ne adverse conta1nment cond1t1ons.
The alternate 1nstrumentation provided by the licensee sounds 11ke a reasonable approach; however, the 11censee should prov1de the NRC w1th the relat1onship between the pump discharge pressure and the pump flow rate as a bas1s for th1s dev1ation.
3.3.18 Conta1nment Sum Hater Tem erature Regulatory Guide l.97 recomnends Category 2 instrumentat1on for th1s variable w1th a range of 50 to 250'F.
The 11censee does not have 1nstrumentat1on for this variable, saying it would g1ve no 1nformat1on relat1ve to m1tigat1ng or determin1ng the consequences of an accident.
Containment sump level, conta1nment atmosphere temperature and conta1nment pressure are used by the operator to determ1ne containment condit1ons.
However, these w1ll not provide a quantitat1ve measure of heat removal from conta1nment.
Th1s 1s 1nsuff1c1ent )ustificat1on for th1s exception.
The 11censee should prov1de the recomnended 1nstrumentat1on for the funct1ons outl1ned in the Regulatory Gu1de 1.97 or 1dent1fy other instruments that prov1de the same 1nformat1on (such as the res1dual heat removal heat exchanger 1nlet temperature) and sat1sfy the regulatory gu1de.
3.3.19 Volume Control Tank Level Regulatory Guide 1.97 recommends instrumentation for th1s var1able with a range of top to bottom.
The l1censee's 1nstrumentat1on has a range 13
3.3.22 Vent from Steam Generator Safet Rel1ef Valves Regulatory Guide 1.97 recomnends 1nstrumentat1on for th1s var1able with a range of 10 to 10 yC1/cc.
The 11censee's 1nstrumentation
-l 3
has a range of 3 to 20 x 10 yC1/cc.
The lower limit of the 5
receanended
- range, 10 to 3 yC1/cc, is not detected by the 1nstrumentation.
The 11censee provided no Justification for th1s deviat1on from the recommended release assessment capabilit1es.
The licensee should e1ther expand the range to that recommended by the regulatory gu14e or show that the ex1sting range 1s adequate during all acc1dent and post-accident con41t1ons.
3.3.23 Plant and Env1rons Radioact1vit Regulatory Gu1de 1.97 recoi.nds portable 1nstrumentat1on for isotop1c analys1s for th1s variable.
The 11censee has not prov1ded the information requ1red by Sect1on 6.2 of Supplement No.
1 of NUREG-0737.
The 11censee should prov1de the requ1red 1nformat1on, 1dentify any deviation from Regulatory Gu1de 1.97 and prov1de supporting )ustification or alternat1ves for those dev1ations.
3.3.24 Accident Sam lin Pr1mar Coolant Containment A1r and Sum Regulatory Gu1de 1.97 reconeends sampling and on-s1te analys1s capability for the reactor coolant system, conta1nment
- sump, emergency core cooling system pump room sumps, and other s1milar aux1liary building sump 11qu1ds and containment a1r.
The 11censee's post-acc1dent sampl1ng system prov1des sampl1ng and analyses as reconeended by the regulatory gu1de, except for the follow1ng dev1at1ons.
o Gross act1v1ty - the range is not identif1ed o
Gamna spectrum - the range 1s not 1dent1f1ed 15
4.
CONCLUSIONS Based on our rev1ew, we f1nd that the 11censee either conforms to or is )ustified in dev1ating from Regulatory Gu1de 1.97, with the following except1ons:
l.
Neutron fluxthe 11censee should prov1de 1nstrumentat1on for th1s variable that is environmentally qualified 1n accordance
-w1th the prov1s1ons of 10 CFR 50.49 and Regulatory Gu1de 1.97 (Section 3.3.l).
2.
Reactor coolant system soluble boron concentrat1on the l1censee should identify the range as requ1red by Sect1on 6.2 of NUREG-0737, Supplement No. 1, ident1fy any dev1at1on from the regulatory gu1de and )ustify that dev1ation (Section 3.3.2).
3.
Oegrees of subcool1ng the licensee should provide Category l instrumentation for th1s variable (Sect1on 3.3.3).
4.
Conta1nment isolation valve positionthe licensee should prov1de instrumentation for 3 remaining penetration 11nes that 1s env1ronmentally qual1f1ed in accordance with the prov1s1ons of 10 CFR 50.49 and Regulatory Gu1de 1.97 (Section 3.3.4).
5.
Radiat1on level in circulating primary coolant the licensee should ident1fy the range of the alternat1ve instrumentat1on as requ1red by Sect1on 6.2 of NUREG-0737, Supplement No. l, 1dent1fy any deviat1on from the regulatory gu1de and )ustify that deviat1on (Sect1on 3.3.5).
6.
Analysis of pr1mary coolant the 11censee should ident1fy the range of th1s 1nstrumentation as required by Sect1on 6.2 of NUREG-0737, Supplement No. l, ident1fy any deviation from the regulatory gu1de and )ustify that deviation (Sect1on 3.3.6).
l5.
Volume control tank levelthe licensee should e1ther prov1de the recommended range or provide add1t1onal )ustification for the range dev1at1on (Section 3.3.19).
l6.
Condenser air removal system exhaust - noble gases the 11censee should supply the recommended range or prov1de addit1onal Justification in support of the ex1sting range (Section 3.3.2l).
17.
Vent from steam generator safety rel1ef valves the licensee should supply the recomnended range or prov1de add1tional Justification 1n support of the ex1sting range (Section 3.3.22).
18.
Plant and env1rons radioact1vitythe licensee should prov1de the 1nformat1on requ1red by Sect1on 6.2 of NUREG-D737, Supplement No. 1, identify any dev1ation and )ustify any deviat1on ident1f1ed (Section 3.3.23).
19