ML19250C107
| ML19250C107 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/01/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-02-02.B, TASK-02-04.D, TASK-03-08.A, TASK-05-04, TASK-05-06, TASK-06-06, TASK-06-09.A, TASK-15-02, TASK-15-10, TASK-15-11, TASK-15-12, TASK-15-13, TASK-15-14, TASK-15-2, TASK-15-21, TASK-2-2.B, TASK-2-4.D, TASK-3-8.A, TASK-5-4, TASK-5-6, TASK-6-6, TASK-6-9.A, TASK-RR NUDOCS 7911080235 | |
| Download: ML19250C107 (13) | |
Text
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NORTHEAST IFFIEJTIES 1
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November 1, 1979 Docket Nos. 50-245 50-213 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Reference:
(1)
D. L. Ziemann letters to W. G. Counsil (NNECO and CYAPCO) dated April 16, 1979.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit No. 1 Systematic Evaluation Program (SEP)
In Reference (1), the NRC Staff transmitted to Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) listings which indicated the SEP topics deemed, 1) not applicable to the particular facility's design and 11) part of ongoing generic issue reviews. The NRC Staff requested that CYAPCO and NNECO review these listings for their factual correctness and provide any additional comments.
In response to that request, the attached information is provided for both the Haddam Neck Plant and Millstone Unit No. 1.
We believe that the draft listings for both of these facilities should be re-vised in their final form to incorporate the considerations identified in the Attachment. In addition, we continue to believe that it is important as part of the basic objectives of the SEP to delineate and document in detail the process and bases by which these SEP topics were put in the indicated categories.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY W
W. G. Counsil Vice President Attachment i 7 911080 a 3 r
DOCKET NOS 50-213 50-245 ATTACHMENT HADDAM NECK PLANT MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 SYSTEMATIC EVALUATION PROGRAM (SEP) 1274 088 NOVEMBER, 1979
1 i
ENCLO5URE 1 MADOAM hfCK SEP TOPICS NOT REQu! RING REV!EW DUE TO On:Orac GE=Eart tiCEnsi=G ACirvri:Es CYAPC0 Coments TR topic v-i:
Cm Pt:AnCE W TN CODES ANO sTAnnAnos o Refer to CYAPC0 submittals dated 6/29/77, S/26/78, MUM, MUM, aM WUM wmMD de (d
CanEnts:
The tagineering Branch. 00R is performing a re,te.
of all plants for compliance with inspection require-NRC Staff review, ments of 10 CF4 50.55a(g).
TOPIC v-3:
OVERPRESSURE PROTECTION Ca nENTS:
Listed as TASK A-26 in NuREG-Om,
- TASK ACTION PLANS o Refer to CYAPC0 submittal dated 3/6/78, which M
FOR GtNtRic ACTiv T Es, Pubitshed date November 1978.
identifies the proposed resolution of this issue.
Generic letters issued to PWR factittles in August 1976. Specific criteria has been identified to bc used in the design of modtf tcations intended to preclude esceeding the itetts of 10 CFR 50. Appendia G.
i TOPIC V-7:
REACTOR COOLANT PUMP OVERSPEED CGutENTS:
itsted as TASK 8-68 in NUREG-0371. dated November y
1978. At this time no (riteria has been developed for this task.
TOPIC V-8:
$ TEAM GENERATOR INTEGRITY COMMENTS:
Listed as TASK A-3, 4. 5 of hUREG-0317. dated November.
1978. The TASK ACTION PLAN completely envelopes the scope of this topic review.
TOPIC y-13:
WATER NA*1MER CenENis:
Listed as TASK A-i in NuREG-Om. " TASK ACTION PLANS o Refer to CYAPC0 submittal dated 1/3/78, currently FOR GENERIC ACTIVITIES *. Published date November 1978.
under NRC Staff review, which identifies proposed Generte letters sent to this factitt, na, is75.
AdaMGbhwo TOPIC Y!-2-8:
SU8CCMPARTMENT AhAlfSIS CmMENTS:
itsted as TASK A-2 in NUREG-0311. " TASK ACTION PLANS FOR GENERIC ACTit! TIES *. Published dated hovember 1978.
Guidance letters issued to PWR licensees October 1975.
N N TOPIC III-10.B PUMP FLYWHEEt INTEGRITY o
Topic resolution addressed as part of ISI program (Topic V-1).
@ TOPIC V-4 PIPING ANJ SAFE END INTEGRITY o Topic resolution addressed as part of ISI program e
(Topic V-1).
TOPIC V-6 REACTOR VESSEL INTEGRITY o Topic resolution addressed as part of ISI program (Topic V-1) and Tech. Spec. 3.4.
April 16,1979
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uncom htC,.CYAPC0 COMMENTS T
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TOPIC V!!-1-8:
TR]P UNCERTAINTV 2)
C3mENTS:
Staff evaluations. Issued Agust 1978, state that review is being pursued independent of SEP to deteruf ne tapact of instrument error and drift upon safety margins of trip setpoints, and that appropriate actions util be taken to assure that
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adequate safety margins are maintained.
L TOPIC VII-4:
FAILURES OF NON-5AFETY SYSTDt1 AND SELECTED ESF'S CDtMENTS:
The scope of this topic is contataed in TASK A-17 of NUREG-0371. November 1978. The staff is developino a method of review. Criteria has not been estabW.*+d for implementation.
TOPIC VII-5:
INSTRUMENTS FOR MONITORS.N ACCIDENTS C0pt1ENTS:
TASK A-34 of NURIG-0371. November 1978. Criterta i
(j under develo;meent.
TCP!C VII-6:
FREQUENCY DECAY COPMENTS:
The scope of this topic is completely addressed in TASK A-35 (2.C-10) of NUREG-0371. November 1978.
TOPIC VI!!-1-4:
EFFECTS OF DIGRADED GRID VOLTAGE CGtMENTS:
The scope of this topic is contained in TASK A-35 (C-2, 3. 4. and 5) of NUREG-0371. November 1978.
Initial letters sent to Itcensee August 1976.
TOPICS IX-1, o
CYAPC0 has submitted information (1/13/78, 3/21/78,
'IX-2, XV-20, 10/14/78) deemed sufficient to resolve these fuel XV-21 storage / handling related topics in response to NRC Staff reviews of plant modifications and/or generic y
letters.
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CYAPC0 COMMENTS
,3, TOPIC IX-6:
FIRE PRGTECTION
)
COnnENis:
This topic is being revte.ed outside the sEP8 as o Safety Evaluation issued by NRC Staff in September, f3 part of the ongoing Itcensing review taplemented 1978 Amendment #28.
as a result of the Browns Ferry incident.
TOPIC Il-1:
APPEND!I I
(
3 COtMENTS:
This topic is part of an ongoing Itcensing review for all facilities to implement the 11alts of the Appendix I to 10 CfR 50.
TOPIC XI-2:
RADIOLOGICAL MONITORING SYSTDiS tb COMMENTS:
Listed in NUREG-0371. November 1978, as TASK 8-67 criteria and scope of review under development.
TOPIC I!!!-2:
$ATEGUAROS/ INDUSTRIAL SECURITV b
Ongoing incensing review to 1. pie...t the require _
o Security Plan Evaluation Report issued by NRC Staff ConnENTs:
.ents of 10 Crt 73.ss.
dated March 5,1979, Amendment #30.
TOPIC IV-22:
ANTICIPATED TRANSIENTS WI.'HOUT SCRAM C091ENTS:
TASL A-9 of NUREG-0371. November 1978, criteria for implementation under development.
TOPIC XV-23:
STEAM GEhERATOR MULTIPLE TU8E FAILURES COtMENTS:
This topic is being considered in conjunction with TASK A-2, 3. 4 of NUREG-0371. No criteria has been estabitthed on this topic.
TOPIC II-2.B ONSITE MET MSMT PROGRAM o This topic review, according to NRC Staff topic description, is included in Topic XI-1.
TOPIC VI-2 RADIOLOGICAL MONITORING SYSTEMS o T0pic resolution addressed within the context of Topic XI-l and NRC Staff review of augmented rad-N waste systems.
N TOPIC VI CONTAINMENT LEAK TESTING o Separate licensing action, o<
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g ENCLOSURE 2 HADoAM NtCK lte fortCs nor AretrCAstr To naccan nECx CYAPC0 Comments p T.
toric no.
Titt e Comt=Ts II-4-E oam Integrity N/A to this ritt site f
')
III-3-8 ranure of underdrain systems N/A to inis unit o The resolution of this topic was discussed'with NRC W
III-7-C n iamination of rrestressed Concrete RfA this unte contain,,cnt Staff during site visits on 9/13 - 14/78.
Containment III-lo-C survettlance Requirements on M/A 8WR Safety Topic SWR Recirculation Pumps IV-3 8WR Jet Pro Operating Indications N/A SWR Safety Topic r
Applicability of Code Cases N/A at this time. To V-2 be reviewed for any future modtrications using references to Code Cases, y
V-9 Reactor Core Isolation Cooling N/A 8WP Safety Topic System V-12-A Water Purity of BWR Primary Coolant N/A BWR Safety Topic VI-2-A Pressure-Suppression BWR Contatrument N/A 8WR Safety Topic VI-2-C Ice Condenser Containment N/A to this unit containment design v!-7.A.2 upper rievu,'aJection n/A to this catt's desina o As noted in our letter dated 11/20/78, CYAPC0 believes that additional documentation regarding this conclusion VI-7-A-4 Core Spray h te Effectiveness N/A BWR Safety Topic is necessary to make a final disposition.
vi-i.o ton, Term Cooitas assive rattures N/A no curreat criteria r
o Resolved per NRC letter dated 8/17/78; refer to CYAPC0 s
rv VI-7-r ECCs Accumulator oesign N/A to this unit's design letter dated 11/20/78 for additional comments.
VI-9-A Main Steam Line Isolation Seal N/A BWR Safety Topic
-h System VI-lo-8 Shared Engineer $afety Features N/A to this unit site g
g VII-7 Accetability of 1 sing Bus Design N/A BWR Safety Topic y
on BWR-4 Plants sV-11 ruei Asseneiy nisioadtag Review on a routine basis o Note that this topic is reviewed whenever a request for 85 P*rt of reioad amendment as a part af a reload is submitted.
II -8s Loose ' art.s Monitoring N/A to this unit's design.
Sys tr.m 111-8-B Control Rod Drive N/A BWR Safety 0 NRC Staff topic description dated 3/7/78 suggests tiech.anism Integrity Topic that experience on PWR's has indicated lack of generic 7g3 g_
i 2-HADCAM mfCK (Continued)
TOPIC NO.
TITLE COMMENTS IV-13 Rod Drop Accfdent (BWR)'
N/A SWR Safety Topic Group I (BWR)
All N/A BWR D8E Review DBE Group VI DBE Topic IV-13 (Only) Uncontrolled N/A BWR D8E Revtem Rod Asses 61y Withdrawal at Power.
Low Power Startup. Rod Drop Accident XV-24 Loss of All AC Power N/A No Current Criteria N
4 CD U
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ENCLOSURE 3 HADDAM NECK SEP TOPICS PREVIOUSLY RESOLVED Topic No.
Title CYAPC0 Comments II-1.A Exclusion Area Authority and Control y Refer to CYAPC0 Proposed Il-1.B Population Distribution I
Resolution dated 3/21/78 II-2.C X/Q j
III-5.B Pipe Break Outside Containment Refer to Resolution described in License Amendment #16, dated 7/14/77.
III-7.D Containment Structural Integrity Tests (SIT)
VI-7.A.1 ECCS Reevaluation to Account Refer to Resolution described to UHFT in Tech. Spec. 3.7.
XIII-1 Conduct of Operations CYAPC0 Operations are periodically reviewed by NRC Staff as part of Tech. Spec. Section 6.0 reviews.
In addition, this topic is related to Topic XVII, which per NRC letter dated 11/20/78 has been resolved for all SEP plants; see CYAPC0 letter dated 11/20/78 for additional coninents.
1274 094
l 1
ENCLO5URE 1 MitL5 TONE 1
$[P TOPICS NOT REQUIRING REVIEW DuE TO i
OncolNG GENERIC LICENSING ACTIVITIES b
9 EEEl I0_Plc IV-3:
BWR JET P W OPERATING IN0lt,All0h5 CapetENTS:
This topic is being reviewed generically, by DOR, for all jet pump plants.
TOPlcv.1:
COMPLIMCE Nm CODE 5 AND STMDARDS COPetENTS:
The Engineering Branch, DOR, is performin a generic review of all plants for compitance with aspection requirements of 10 CFR 50.55a(9).
- M TOPIC V-13:
NATER NAPMER COPelENTS:
Listed as TASK A-1 in NUREG-0371, 'iASK ACTION PLANS
[J FOR GENERIC ACTIVITIE5*, Published date November 1978.
Gwric letter sent to PWR factittles, requirements not estabitshed for SWRs.
TOPIC VI-2-A:
PRES 5URE-SUPPRESSION SWR CONTAINMENT $
Liste'd as TASK A-7 and A-39 in NUREG-0371 " TASK COPE (NTS:
ACTION PLAN 5 FOR GENERIC ACTIVITIE5*, PubItshed dated November 1978. Appites to MARK I factittles (Dresden 2 Millstone 1, and Dyster Creek). Safety objective of Topic VI-2.A is entirely within the scope of these activities.
TOPIC V[ 2-8:
SU8 COMPARTMENT ANALYSIS COMMENTS:
Listed as TASK A-2 in NUREG-0371,
- TASK ACTION PLANS FOR GENERIC ACTIVITIE5*, Pubitshed date Novescer 1978. Guidance letters issued to PWR licensees October 1975. The staff is current!y developing plans for expand 6ng this activity to resolve this issue for SWR factittles (NUREG-C510).
N Spectf te requirements and scope have not been estabitshed.
N A
TOPIC VI-7-A-4:
CORT SPRAY N0ZZLE EFFECTIVENESS COMMENTS:
Listed as TASK A-16 in NUREG-0371, " TASK ACTION g
PLANS FOR GENERIC ACTIvlTIE5", Published date W
November 1978. December 1976 - letter issued to Itcensee.
(y April 16,1979 s
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MILL 5'.)NE 1 TOPIC VII-t-8:
TRIP UNCERTAINTY CDPHENTS:
Staff evaluations, issued Asgust 1978, state that review is being pursued independent of $[P to determine 1spect of lastrument error and drift upon safety margins of trip retpoints and that appropriate actions will be taken to assure that adequate safety margins are maintained.
TOPIC VII-4:
FAILURES OF NON-5AFETY SYSTDt1 AND SELECTED ESF's Cort lENTS:
The scope of this topic is contained in TASK A-17 of NUREG-0371. November 1978. The staff ts developing a method of review. Criteria has not been established for taplementation.
TOPIC VII-5:
INSTRUMENTS FOR MONIT0EING ACCIDENTS Cr--
COWENTS:
TASK * *4 of NUREG-C371 hovember 1978. Criteria und velopment.
TOPIC VII-6:
FREL. if DECAf COtMENTS:
The scope of this topic is completely addressed in TASK A-35 (2.C-10) of NUREG-0371. November 1978.
TOPIC VIII-1-A:
EFFECTS OF ERAXD GAID VOLTA &E C09 TEN 15:
The scope of this t spic is contained in TASK A-35 (C-2. 3. 4. and 5) of NUREG-0371. November 1972.
Initial letters sen to Ifcensee August 1976.
TOPIC II-6:
FIRE PROTECTION C0mENTS:
This topic is being reviewed outside the SEPB as part of the ongoing licensing review implemented as a result of the Browns Ferry incident.
rv y-TOPIC V-4 PIPING AND SAFE END INTEGRITY o Topic addressed as part of ISI program p
(Topic V-1).
O TOPIC V-6 REACTOR VESSEL INTEGRITY o Topic addressed as part of ISI program W
(Topic V-1).
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~3*
NNECO COMMENTS topic tl-1:
APPINDII I CDP 9 TENTS:
This topic is part of an ongoing Itcen Ing review
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for all factittles to toplement the Ilmits of the h
Appendia I to le CFR 50.
TOPIC II-?:
RADIOLOGICAL NJNITORING ST5 tdt 3 COMMENTS:
Listed in NUREG-0371. November 1978, as TA5K 8-67 Criteria and scope of review under develogment.
M TOPIC I!!I-7:
SAFIGUARD5/ INDUSTRIAL SECURITV COMMENTS:
Ongoing Itcensing review to taplement the reptre.
a d/
ments of 10 CTR 73.55.
TOPIC IV-22:
ANTICIPATED TRANSI[NTS WITHOUT SCRAM COMMENTS:
TASK A-9 of NUREG-0371. November 1978, criteria for taplementation under development.
TOPIC II-2.B ONSITE MET. MSMT. PROGRAM o Topic review addressed within the context of Topic XI-1.
-TOPIC VI-2 RADIOLOGICAL MONITORING o Topic review addressed within tne SYSTEMS context of Topic XI-1.
N N
TOPIC VI-6 CONTAINMENT LEAK TESTING o Separate Licensing Action.
4 CD N
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ENCLOSURE 2 MILLSTONE UNIT I SEP TOPICS NOT APPLICASLE TO MILLSTONE UNIT 1 TOPIC NO.
TITLE COMMENTS b
Il-4-E Das lategrity N/A to this lite Ill-7-C Delamination of Prestressed Concrete N/A to this cetatnaent g
Contatament design III-10-B Pump flywheel lategrity N/A PWR Safety YeSic V-2 Appitcability of Code Cases N/A at this time. To be reviewed for any ftture modifications EC Ca e gg V-3 Overpressure Protection N/A PWR Safety Topic V-7 Reactor Coolant Pump Overspeed N/A PWR Safety Topic
["
V-8 Steam Generator lategrity N/A PWR Safety Topic V-9 Reactor Core Isolation Cooling System N/A to this facility design VI-2-C Ice Condenser Containment N/A to this fact 11ty design VI-7-A-1 Increased, Vessel Head Temperature N/A PWR Safety Topic VI 7-A-2 upper Plenan Injection N/A PWR Safety Topic VI-7-8 ESF settchover From Injection to N/A PWR Safety Topic Rectrculation VI-7.C.3 PWR Loop Iso'.ation valve Closure N/A PWR Safety Topic VI-7.0 Long Term Cooltag Passive failures N/A Ptst Safety Toote VI 7-E ECCS Swap Design N/A PWR Safety Topic VI-7 F ECC5 Accoulator Design N/A PWR Safety Topic VII-7 Acceptability of Swing Bas Design N/A to this facility design on BWR 4 Plants IX-4 BoronAdditionSystem(PWR)
N/A PWR Safety Topic A
X Aust11ary Feedwater System N/A PWR 5afety Topic XV-11 Fuel Assembly Misloading Reviewed on routine basis Note that this topic is reviewed whenever a request
]
85 part of reload for amendment as part of a reload is submitted.
IY-17 Steam Generator Tube failure (PWP)
N/A PWR Safety Topic II-4-D
~ Stability of Slopes N/Atotb[sfacilitydesign III-8-A Loose Parts Moni-N/A to tnis facility design toring System VI-9-A MSLISS N/A to this facility design
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XV-2 Steam System Piping N/A to this facility design Failures
g i
q-3 RILL 5 TONE UNIT 1 V2)
(Continued)
TOPIC No.
TITLE ColetuTS CS-IV-23 Steam Generator Italtiple Tube R/A M Safety Topic failures Group B (PWR)
All N/A M DBE Review DBE Group II DBE T plc V-(Only) Feedwater Systes N/A PWR DBE Review b'
Group III DBE All N/A M OSE Review Group VI 08E Topic IV-8. IV-12 (Only). Control R/A M DBE Review Rod Misoperation. Spectrum of Rod Ejection Accidents Grous X DSE All N/A PWR DSE Review e
XV-24 Loss of All AC Power N/A No Current Criteria XV-13 Spectrum of Rod Drop Reviewed on routine nasis Accidents as part of reload.
XV-10 CVCS Malfunction M/A PWR Topic XV-12 Spectrum of Rod N/A PWR Topic Ejection Accidents XV-14 EdCS/CVCS Malfunction N/A PWR Topic c3 w
XV-21 Spent Fuel Cask Drop Resolved in Separate Licensing Actions.
Accident h ast