IR 05000529/1985044
| ML20234D528 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, 05000000 |
| Issue date: | 11/27/1985 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20234D050 | List: |
| References | |
| FOIA-87-279 NUDOCS 8707070246 | |
| Download: ML20234D528 (1) | |
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'o UNITED STATES E ) [r ( ' p, NUCLEAR REGULATORY COMMISSION Yn }., y
REGION V
% 'A g 1450 MARIA LANE, SUITE 210 %, Y ,o' WALNUT CREEK, CALIFORNI A 94596
% . NOV 2 7 1985 { i MEMORANDUM FOR: Dennis W. Crutchfield l Assistant Director for Safety Assessment Division of Licensing FROM: D. F. Kirsch, Deputy Director Division of Reactor Safety & Projects SUBJECT: COMPARISON OF AS-BUILT PLANT WITH THE PALO VERDE UNIT 2 TECHNICAL SPECIFICATIONS , i Region V has completed its review of the proof copy of the Palo Verde Unit 2 Technical Specifications.
The details of this review will be reflected in l Inspection Report 50-529/85-44 (in preparation).
IE Inspection Procedure ' 71301, " Technical Specification Review", dated March 22, 1985, was used as i guidance for this review. This review concluded that the proposed Technical ] Specifications were sufficiently clear and enforceable, and adequately J reflected the installed referenced systems (the " s-built plant"). ' u a.
. F. Kirsch,- Deputy Director Division of Reactor Safety & Projects cc: J. B. Martin G. W. Knighton, Licensing Branch No. 3 > R. Zimmerman, Resident Inspector C. Sorensen L. Miller l-5 .
i 8707030246870512 - PDR P R BERB -279 . -
_ - _ - ., -. -., .. . . ! NOV 271985 - . . .. , HEMORANDUM FOR: Harold R. Denton, -Director ~ Office of Nuclear Reactor Regulation FROM: J. B. Martin, Regional Administrator ~ Region V _ SUBJECT: PALO VERDE NUCLEAR GENERATING STATION UNIT 2 OPERATIONAL READINESS REPORT (MC 94300) li This letter transmits the final Region V report summarizing the readiness of Palo Verde Unit 2 for issuance of a Low Power Operating License. Region V recommends the issuance of a low power operating license for Palo Verde 2, subject to the conditions in Attachment 1, and any other conditions which seem appropriate to NRR.
This recommendation presumes the satisfactory completion of required construction and preoperational testing by the licensee. As of the date of this report, the licensee has committed to complete these by December 2, 1985.
Original Signed br John B. MarU_n , J. B. Martin Regional Administrator
Enclosure:
As stated
REGION V== NOVEMBER 26, 1985
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Summary Status 1.
Applicant's current estimated licensing date: 12/2/85 - _1 2.
Inspection Program: Completed for low power licensing.
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Review of Actions on Generic Correspondence: ' Completed for low power licensing.
4.
Reportable 10 CFR 50.55e Events: All 10 CFR 50.55(e) reportable { Deficiency Evaluation Reports (DERs) have been reviewed by RV as of the date of this report. Licensee action to replace deficient bolts on NSSS line stops (DER 85-39) remains outstanding and is a recommended license condition.
5.
Preoperational Testing: As of 11/25/85, the licensee had completed 173 of 184 required preoperational tests.
Preoperational testing will be completed on all safety related or important to safety j systems prior to fuel load, with the exception of the tests listed in Section h to be completed after initial fuel load.
6.
Significant System Performance Deficiencies: All system performance deficiencies appear to have been satisfactorily resolved by the licensee.
7.
System Turnovers: 5 of 457 safety related or important to safety subsystems have not been turned over to the operations department.
Approximately 275 construction deficiencies remain as of 11/22/85.
Region V has reviewed this list, and concluded that Palo Verde 2 is substantially completed, and ready for operation. However, to . provide additional assurance, Region V recommends license condition 1.a of Attachment I to require licensee certification that all systems required for operation in an operating mode are operable prior to entering that mode for the first time.
8.
Procedures: The surveillance procedures, and with minor exceptions, the operating procedures to be used at Unit 2 are the same as those for Unit 1 except for Unit designation. One surveillance procedure remains to be converted for Unit 2 use.
. 9.
TMI Action Plan Items - The following items remain open: (a) II.B.I. - Pressurizer vent valve HV-108 still needs to be tested for operability.
-E (b) II.D.3 - The pressurizer safety valves acoustic monitoring ! system has been calibrated, however, the licensee has not yet - made available the completed test procedure for Region V review.
(c) II.F.1 2.E. - The containment water level monitoring system has , not been preoperationally tested and the licensee does not plan to test it until prior to Mode 3 entry.
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Facilities Radiological Protection Section (a) The radiation monitoring systern (RMS) test program will not be substantially complete by the projected fuel load date.
The .l RMS is described in the FSAR (14.B.26) as a phase I ~ (preoperational) test. The licensee's test schedule shows that testing will be phased in as monitors are required by technical specifications.
It is not clear when the non-technical _ specifications process radiation monitor test program will be complete. We suggest this issue be addressed in a license condition.
(b) The radiation exposure management system described in the FSAR (12.5) will not be operational. The licensee is implementing compensatory measures.
(c) Testing of the solid radioactive waste system (SR) will be ' delayed pending resolution of problems experienced at Unit 1.
l The licensee will rely on a solidification contractor if necessary.
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Proposed License Conditions ' Region V recommends the following license conditions be incorporated into the low power operating license: See Attachment I c.
hTC Inspection Activities , MC 2512 Program Status Priority 1 Complete MC 2513 Program Status. Complete with the exception of the radiation . monitoring areas not completed by the licensee.
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MC 2514 Program Status This program is current. Limited inspection has been performed for the' startup testing phase. The startup test procedures for Unit 2 are substantially the same as those used in Unit ? Special Inspection Activities j Region V conducted an annual team inspection during the period October 28 ~! - November 8, 1985. This inspection concentrated on the operation, - maintenance, operations engineering and quality assurance aspects of Unit 1.
The team identified no weaknesses which would affect the low power licensing of Unit'2.
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Gene ~ric Correspondence
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- ) $ The licensee has satisfactorily responded to all applicable Bulletins and Circulars.
e.
Enforcement History _ _i There are no outstanding licensee responses to violations, d,e.viations or - '1 ] ~ unresolved items which will require licensee action prior to issuance of a low power operating license.
f.
Part 21 Notification Potentially Defective TEC Model 914-1 Valve Flow Monitor Modules - The licensee has identified where the potentially defective flow modules are
utilized in plant systems, principally as direct flow indicators from i pressurizer and steam generator safety valves. The licensee has stated j that such applications are not safety significant, and that they have { tested the modules similar to the way the vendor recommends, but have not . yet provided supporting documentation for Region V review, as of the date of this letter, j . g.
Construction Status (1) The remaining construction is reportedly relatively minor in nature, ' consisting mainly of efforts to complete corrective actions identified as a result of testing, Deficiency Evaluation Reports, walkdown punchlist items, etc.
(2) The construction punchlist contained approximately 275 items as of November 25, 1985. Region V review of this list indicated that these items are being properly dispositioned and issuance of a low . power operating license for Palo Verde 2 is warranted.
h. Preoperational Test Results (1) Preoperational Testing - Preoperational testing will be completed on all safety related or important to safety systems prior to fuel load, except as noted below. The current status is as follows: > Total Tests Test Complete T_est Results Approved , 184 173 144 The remaining 11 tests that are not complete are listed below.
TESTS TO BE PERFORMED AFTER INITIAL ITEL LOAD .,_ l (To Be Performed Per FSAR 14.2.5 as Phase I Tests) '" : i The Following Tests Have Not Been Performed 91PE-2LR02 Liquid Radwaste Evaporator Test 92PE-2QF06 In Plant Communications (Safety Frequency Radio - Frequency 92PE-2SB20 DNBR Calculator to PMS Data Link
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. . . - 92PE-2SB15 Core Operating Limit Supervisory System (COLSS) Test 92PE-2SQO2 Post Accident Radiation Monitor 92PE-2SQO3 Digital Radiation Monitoring System 92PE-2SQ04 Safety Related Radiation Monitoring -- 73HF-2ZZ11 Pressurizer / Reactor Vent System , 91PE-2SS02 Gas Analyzer Test .. 93PE-2QD02 Modular Emergency Lighting Units - _ (2) System Acceptance - The licensee has reconfirmed that all safety related or important to safety systems and areas will be accepted by operations to ensure drawings up-to-date and system completion prior to fuel load. The latest status is as follows: Total Subsystems Accepted 457 452 Total Areas Accepted
64 (3) Surveillance Test Procedures - The surveillance test procedures to be used at Unit 2 are the same as those currently being used at Unit 1 except for unit designation.
One procedure remains to be corrected for Unit 2.
(4) Operations Procedures - With minor exceptions the operating procedures to be used at Unit 2 are the same as those for Unit 1 errept for Unit designation. All operating procedures have been converted for Unit 2 use.
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. ATTACHMENT 1 PALO VERDE NUCLEAR GENERATING STA. TION, UNIT 2 OPERATING LICENSE NPF-46 - .. _ This attachment identifies items which Region V recommends for consideration by NRR as license conditions for Palo Verde 2.
- 1.
Prior to entering a'ny operational mode for the first time, including initial fuel loading, ANPP shall a.
Have completed a review of the surveillance procedures applicable to the change of mode, and determined that the procedures demonstrate the operability of the required systems with respect to all acceptance criteria defined in the Technical Specifications.
b.
Have dispatched written notification to the NRC Regional Administrator, Region V, that the action defined in (a), above, has
been completed for the mode or modes to be entered.
2.
ANPP shall test Reactor Coolant Gas Vent Valve 2J-RCB-HV-108 and demonstrate its operability during Mode 3 and prior to entering Mode 2.
3.
ANPP shall shim all " proximate" supports (e.g. pipe supports located near a critical component such as a pump nozzle) adjacent to rotating and reciprocating equipment to a 1/16 inch gap prior to entering Mode 2.
4.
ANPP shall test the containment water level monitoring system prior to entering Mode 3.
, 5.
ANPP shall enlarge the pipe penetration where the Reactor Coolant Gas Vent piping passes through the pressurizer compartment blowout panel, as stated in EER 85-RC-200, prior to entering Mode 4.
6.
ANPP shall complete power ascension testing in Unit 1, with the exception of the Natural Circulation Cooldown Test, prior to entering Mode 2 in Unit.. 7.
ANPP shall replace deficient bolts on NSSS line stops as discussed in . DER 85-39, unless exempted by NRR.
Safeguards Program j
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Prior to February 16, 1986, ANPP shall .? a.
Replace coaxial wiring to the security radio antennas in the . Radwaste and Auxiliary Buildings.
b.
Relocate the security radio base stations from the 160-foot level of the Corridor Building to a more central location, ~ Install and evaluate a passive antenna system on the 74-foot level e.
of the Control Building.
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Prior to initial criticality of Unit-2, ANPP shall a.
. Evaluate the effectiveness of the above changes (to be completed prior to February 16, 1986).
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If the results of this evaluation determine that significant deficiencies still exist, establish an action plan to provide ~ , adequate security communications, including interim measures.
Radiation Monitoring System 10. With respect to this system, ANPP shall perform compensatory measures, complete testing and make operable all elements of the radiation-
monitoring system in accordance with the schedule and commitments approved by NRR, presented in the licensee's submittal dated . -i i
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Director of Wrlear kractor Regulatir.n Attentloat Mr. George W. Knighton. Project 1 rector PWR Pro jec t Directorate #7 i Division of Pressurizec Water 'eactor I.icensing - h j l'. S. heleer Regulat ory Come1maton ' hahimston, D.C.
20555 'lu b )we t Pelo Verde Nuclear Gen. ating Station (PVNGS) thnit 2 Docket No. STN 50-529
Justification for Interim Operation related to the Radistica Monitors Ptle: 85-056-026: C.I.01.10 References letter to C.
W. Knighton, NRC, from E.
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Van Brunt, Jr., ANPP, dated Novembe r 8, 1985 (ANPP-33965); Subject: Supplement I to WUILEG-0737 Schedule Omar Mr. Knighton '" Per telecom on Novembe r 27, 1985 ANPP agreed to provide information and + justifications for interis ope ra t ion conce rning the Radiation Monitors for Outt 2.
The schedule for the Radiation Monitors la as follows: (1) Monitors which are sub }er t to Technical Specification requirements will be operable prior to the mode f or which t tw y are required without entering a technical s pec i f i ca t i on-i actica statement; (2) Regulatory Guide 1.97 monitorn will be operable per the commitmenta in the referenced letterg Mont*t ,wg , 5' 'r'in m"ae' , j t i-this letter also provides compensatory measures and l i justifications for interim operation for those monitors which will not be completed Prior to initial criticality.
l no reactivity in e t, system.
Prior to inital criticalltv, there is ! . ., , f . .. : .- eff , .. . ? . ng ', l* f t'. ,
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k.n i g t. t on . Justificat ion f or Interim Operation of . kadia t ion Moni t or ing Svu t es AhPP- %,, . Page Two ' - Several factors, as discussed below, have contributed to the Unit 2 r4diation monitora being inoperable at this time.
Meae.ures have been take'n to correct these cond 'tions.
1.
Vendor Support Vendor support is needed in design.trens primarily for lla rdwa re Deafgn Chantes. Software Design Changes and Technical Cla ri f ica t ion.
This support free the vendor has historically been slow and, in nome cases, . . lacked clarity.
To resolve these problems, ANPP has contracted the services of two vendor engineering personnel to work strictly for this project.
We overall level of support has increased and has indications of continuing to increase.
In addition, the project has con t rac t ed for two technicians from the vendor on a ahort duratton basis.
This is to facilitate more rapid t roubleshoot ing and increase the PVNGS personnel knowledge of the systen.
2.
Maintenance (I!.C) Knowledge le vel As with all highly technical systems, it takes time for personnel to learn the systes.
In the 3 months of intense concentration nn this particular system, the technicians have progressed significant4v.un the Laatsing curve.
This, of course, v111 continue to laprove with time, 3.
Spa re Pa rt s > Spare, parts la an industry wide probles, not s pe c i f i ca l l y ansociated with this s ys tem but definitely a factor.
Due to the complexi t y of the system, most failures have to be resolved on 4 etreuit boa rd level, rault y circuit boe r.is are removed and then sent back t e, the factory tvendor) for repair.
In June, 1985, an order to inventory by approrisately $01 was placed with the vendor.
Ihse to long increase the s pa re pa rt n lead times, the bulk of this order is just beginning to become nya!!nble on site.
he vendor has also committed to increase production for PVNG<i to a ppros taa tel y 50% of fartory ou t pu t. To .in t e, the espected delivery dates ranging f rom the present pro ject has to 6 montha trom now.
FVNCE Unit i Support Ike to rossitments for Unit 1 radia t ion monit or from t, nit 2 for upe in Unit 1.
These parts, f or t f.epartM were transfar a<! rep 1.a ed in Unit / a n ti, ii the nee.1 srisen, Unit I pa r e n will te owed mont p4 rt, have b.
i aupport hnits ! dnd. '. Alan.,s" N ** 1 for upare pa r t u in Unit ! 'I f o p p*'I off a.lgniffrant1y.
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- Mr. George W.
Knighton Justification for Interim Opetation or Radiation Monitoring System ANPP- !!. l.") Page Three .
The projected completion dates discussed in the.i t t.ac hmen t 1rn the. ' '.' N ' W commitment for completion.
If, for any untoreseeable reason we cannot .ee t this commitment, we will discuss it w?t! the.; t a t : at that time.
If you have any further questions. please contact Mr. Wil; lam '. =.ti i nn. =. Verv trilv voors, ' ?,.. Y l.
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) to v. v v F.. E. Van iiri.r.t..f r. Execut Ive Vice Pres t f eiit Project Di re c t r. r EEVB/WFQ/JK0/ dim cc: E. Licitra M. I.ey
R. P. Zimmerman .,,. A. C. Gehr .: -- E.. _ @
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j;MMMMMND E N M G M kt*V M 6N M E N M'M%mMyIndffd'fW Attathment t<> ~ l ANPP 34129 . j ATTACliMEN; .~ FROCESS MONITORS - f.IOl'ID ^ HONITOR PK OJ hCT H' NUMBER DESCRIPTIR i ""I F T :.N " RU-4, 5 Steam Generator Blowdown Monitors lune M.
I'*n Ju=tification for Interim Operation (J10): e Steam Generators will be sampled every 72 hours while in Mu ! 1 to 4 for gamma isotopic activity. The condenser vent effluent monitors (RU-141/142) must be on line for Mode 4 entry and these will indicate in the event of coitamination in the secondarv system.
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.__ .. wonitors .inne 30, 1986 RU-2, 3, Essential Cooling Water RU-6 Nuclear Cooling Water Monitor JIO: Prior to these monitors becoming fully operable, but only after initial criticality and: when the applicable train / system is in o,>eration, the applicable train will be sampled on a weekly basis for gamma isotopic activity.
These cionitors are for trend indication only and the buildup of radioactivity in these trains is slow and significant leakage would be identified via water balance inventories on affected system.
-___________________________ .___ _________ RU-7 Aur111ary Steam Condensate '-'-Initial Criticality RU-204 Process Radiation Monitor Initial Criticality RU-265 Cas Stripper Monitor Initial Criticality . -5l NOTE: ! Samples will be taken in accordance with Station Procedures.
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, I dfaibYribfiiW$CY*MhWdtt' - Attachment to i ANPP 341,29,. ,l - ATTACHMENT s (Continued) - PROCESS MONITORS - ATMOSPHERE
) MONITOR PROJECTED NIMBDL DESCRIPTION COMPLETION { _ l 10-8 Auxiliary Building Ventilation Exhaust June 30, 1986 RU-9 - Auxiliary Building Iower Level Vent Exhaust June 30, 1986 RU-10 Auxiliary Building Upper Level Vent Exhaubt June 30, 1986 Ru-14 Radwaste Building Vent Exhaust June 30, 1986 ) JIO: -) Prior to these monitors becoming fully operable, but only after initial criticality, the j ascociated sample stream will be monitored via a continuous air monitor (CAM).
These CAM's will be of a portable type with pre,et alarus and recorder.
These CAM's wil'1 be checked daily. The atmosphere that these monitors sample during normal operation is the exhaust through the PJant Vent which is sampled by Technical Specification Monitor EU-143.
These monitors are used to localize the source of the contamination and the CAM's will provide similar indication.
.------------------------------------------- 10-15 Waste Gas Vent Exhaust June 30, 1986 & Na compensatory measures will be taken.
The atmosphere that this conftor would normally , - sample is additionally sampled by the following Technical Specification. Monitors RU-12 ' cpetream and RU-143 downstream.
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10-34 Refueling Purge Exhaust Monitor June 30, 1986 JIO: , No compensatory measures will be taken.
The atmosphere that this monitor would normally __ E l sample is additionally sampled by the following Technical Specification Monitors RU-1 - (containment atmosphere) upstream and RU-143 (plant vent ) downstream.
- NOTE: 'emples will be taken in accordance with Station Procedures.
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, .., it t ac h:.,en t tu' j 6NPP ~)4129 ~ I R !! A TTAci!M FJT rj E (Continued) - (I ARF.A RADIATION MONITORS ( ~ i }- .. 10NITOR PROJECTFD l ' IUMBFR DESCRIPTION COMPI.FTION .u-16 Containment Operating Level Monitor Initial Criticality h
- U-17 Containment Incore Area Monitor Initial Criticality j
!U-33 Refueling Machine Area Monitor Initial Criticality l- [ tU-18 Control Room Area June 30, 1986
tU-20 Solid Waste Processiig June 30, 1986 i LU-21 Solid Waste Storage Aree.' June 30, 1986 [. LU-22 Loading Bay Area June 30, 1986
LU-23 Radiochemical lab area June 30, 198t, l (U-25 Controlled Machine Shop Area June 30, 1986 ? . ! LU-26 Sample Room Area June 30, 1986 LU-27 Waste Solidification Area June 30, 1986
(U-28 Waste Solidification Area June 30, 1986 110.
! - Th2ce areas will be monitored via Portable Area Monitors af ter initial criticality with i praset local alarms and will be checked on a daily basis.
These monitors are utilized f ' for area radiation levels for personnel working in the area and this indication will be =cvared by the use of the portable area monitors.
NOTE: . S;2ples will be taken in accordance with Station Procedures.
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' UNITED STATES
NUCLEAR REGULATORY COMMISSION a $ ,E
REGION V
g 1450 MARIA LANE, SUITE 210 ,e WALNUT CREEK, CALIFORNI A 94596 i '
February 19, 1987- ,, q ~, . - , .- . . MEMORANDUM FOR: Frank J. Miraglia, Director Division of PWR Licensing - 8, NRR FROM: Dennis F. Kirsch, Director Division of Reactor Safety and Projects SUBJECT: ARIZONA PUBLIC SERVICE COMPANY, PALO VERDE UNIT 3, DOCKET N0. 50-530, STATUS OF FACILITY COMPLETION, UPDATE (MC 94300) This memorandum is forwarded to provide you with an update on the preparedness j for licensing of Palo Verde Unit 3.
Enclosures 1 through 4 include items I requiring inspection and resolution before Region V can recommend a low power operating license.
The licensee currently estimates a request for a low power license about March 16, 1987. Region V does not consider this time frame to be realistic for a licensing decision unless an exemption is granted for emergency diesel generator 38.
If you have any questions, please contact myself or Stuart Richards of my staff.
lc d . . F. K rsch Director Division of Reactor Safety and Projects Enclosures: 1.
Status of Inspections Required by MC 2512, MC 2513, MC 2514 2.
Preoperational Testing Status 3.
Construction Status j 4.
Open Items .: cc: J. Taylor, IE ~! G. Knighton, NRR - E. Licitra, NRR R. Zimerman J. Martin i s W .
_ '.. ;. , i . -. Enclosure 1-Status of Inspections Required by MC-2512, MC-2513, and MC-2514 , , 1.
MC-2512 Program ~ ,. All priority 1 modules are complete. "' Follow-up of CAT open items and I construction deficiency reports is ongoing and will be completed prior to issuance of a low power license.
2.
MC-2513 Program ~ The preoperational inspection program is curren't and consistent with the licensee's test program status.
3.
MC-2514 Program The licensee has yet to approve and issue, for Region V review, applicable.startup test procedures for Unit 3.
However, the startup test procedures for Unit 3 will be substantially identical-to those used.in Units 1 and 2.
Region V will review these procedures as the licensee issues them.
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The following preoperational tests have not been completed as of ~ February 17, 1987.
.., 91PE-3HP01 Containment Hydrogen Control System Test ~ 91PE-3SR01 Resin Transfer Dewatering System Test 91PE-3SR02 Solid Radwaste System Test 91PE-3HF05 Refueling Machine Test 91PE-3FH06 Reactor Core Indexing Test 91PE-3FH09 Fuel Assembly Core Position Trial Fit-91PE-3FH01 Refueling Machine Underwater Television System Test-73TI-3SS01 PASS 73PE-3SA01 Load Group Assigned Verification (B Train Diesel) 73PE-3DG01 Diesel Testing (B Train Diesel) 73PE-3SQ01 RMS Minicomputer Software / Communications Verification Procedures 73PE-35002 Post Accident Radiation Monitoring Test Procedure 73PE-35003 Radiation Monitoring Systems Test Procedure 73PE-3SQ04 Safety Related Radiation Monitoring Test Procedure . .. .t ~ .
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270 of which are targeted for resolut, ion prior to fuel load. A number of these items include problems with radi'ation monitors.
In addition, approximately 200 of these items have been targeted for resolution. prior- , to initial criticality. Region V will continue to review the punchlist to ensure that items are being properly dispositioned.
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Of 516 total subsystems in the unit, approximately 510 have been accepted by operations. The remaining subsystems entail portions of the polar crane, containment hydrogen analyzing and purge systems, one safety injection subsystem, and emergency diesel generator 38.
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. . , -1-Enclosure 4' -. Open items Including Enforcement and Unresolved Items The following items will be addressed and the impact considered by Region V " prior to issuance of a low power operating license.
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Violation Masonry block walls incorrectly classified as 86-03-25 Quality Class S.
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Violation Numerous deficiencies in vendor supplied components 86-03-26 and materials.
3.
Violation As-builts not in accordance with design and 86-03-27 installation.
4.
Unresolved Item Radiograph adequacy due to poor quality 86-03-19 5.
Unresolved Item Masonry block wall adequacy - This issue was 86-03-20 transferred to NRR under a Task Interface Agreement.
6.
Followup Item Review licensee's action with respect to radwaste building HVAC.
7.
Followup Item Review licensee's action concerning high antimony concentrations in Units 1 and 2 RCS.
8.
Followup Item Review LER involving licensee identification of falsified Technical Specification required surveillances in Unit 2 with respect to licensee followup actions in Unit 3.
9.
Followup Item Review' licensee's corrective actions to assure onshift dose assessment capability.
. Construction Deficiency Reports The following 50.55(e) reports have been evaluated as reportable, or potentially reportable, by the licensee.
Region V will address these items prior to issuance of a low power license.
DER 85-38 Deficiencies identified during audit of GE Company DER 86-29 Crack in a nozzle of the letdown heat exchanger (Potentially Reportable) .j DER 86-30 EQ problems with various fuses, terminal blocks and wiring - (Potentially Reportable) DER 86-31 Loose DG windings (Potentially Reportable) DER 86-32 Discrepancies found between pipe support designs and stress analysis calculations (Potentially Reportable) .
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' . - -2-DER 86-41 Required DCP's may not have been incorporated on some - limitorque operators (PotentiallyReportable) ~ DER 86-47 Diesel Generator engine failure (Potentially Reportable) The following allegations are under review and, to date, none of the issues would impact the issuance of a low power license.
RV-86-A-009 Appendix R concern RV-86-A-019 Appendix'R concern RV-86-A-047 Possible. sabotage - RV-86-A-077 Concerns with system engineers RV-86-A-102 Hot functional testing concern TMI Action Plan Items The following TMI Action Plan Items required for fuel load will be addressed by Region V prior to issuance of a icw power license.
II.B.3 Post Accident Sampling II.E.4 2 Containment Isolatica Dependability II. F.1 Accident Monitoring II.F.2 Instrumentation for Detection of Inadequate Core Cooling III.D.3.3 Inplant Radiation Monitoring .: -t . L }}