ML20126L925

Technical Evaluation Rept, Environ Qualification of Safety- Related Electrical Equipment to Harsh Environs

ML20126L925
Person / Time
Site:	Rancho Seco
Issue date:	12/15/1980
From:	Dodds R, Elin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML18086B701	List: ML18086B700 ML20126L919 ML20126L925
References
IEB-79-01B, IEB-79-1B, TAC-42507, NUDOCS 8106100318
Download: ML20126L925 (103)

Text

{{#Wiki_filter:C e-TECHNICAL EVALUATION REPORT ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT TO HARSH ENVIRONMENTS IEB 79018 RANCHO SECO DOCKET NO.: 50-312 LICENSE NO.: DPR-54 LICENSE: SACRAMENTO MUNICIPAL UTILITY DISTRICT 6201 SOUTH STREET P. O. B0X 15830 SACRAMENTO, CALIFORNIA 95813 ~ B&W PWR (2772 MWT/918 MWE NET) PREPARED BY /25C /E,/78d ' O. Elin, Reactor Inspector RV Date SicJned /1-APPROVED BY R.' T. Dodds, Chief, Reactor Engineering Date Signed Support Section RV M 7,.' a ~ ' ' ~ Mf6'610 0 Yu ~ ~~ ~~ ~ x..

w: c. e. CONTENTS Section Ti tle 1.0 IffTRODUCTI0tl 1.1 General Issue Background 1.2 Specific Issue Background 1.3 Purpose 1.4 Scope 2.0 EVALUATION OF HARSH ENVIRONMENT OVALIFICATION AT RANCHO SECO 2.1 Identification of Safety Related Electrical Eouipment Recuired to Function in a Harsh Environment (Master List) 2.2 Accident Environment Definition (service condition profiles) 2.2(a) Inside Containment (LOCA/MSLB) 2.2(b) Outside Containment (HELB/RECIRC.) 2.3 Eouipment/ Component Evaluation Worksheet Review 2.3(a) Ecuipment Qualified for Plant Life 2.3(b) Eouipment Qualified with Restrictions 2.3(c) Eouipment Listed but Exempt from Oualification 2.3(d) Equipment with Unresolved Oualification 2.3(e) Eouipment Not Qualified 3.0

SUMMARY

4.0 PEFERENCES ATTACHMENT 1 OVALIFICATION TEST REPORTS ATTACHMENT 2 COMPONENTS REQUIRittG QUALIFICATION ATTACHMENT 3 HARSH ENVIRONMENT AREAS ATTACHMENT 4 LICENSEE EVENT REPORT NO. 80-20 LICENSEE EVENT REPORT NO. 80-43 LICENSEE EVENT REPORT NO. 80-44 LICENSEE EVENT REPORT NO. 80-45 LICENSEE LETTER OF APRIL 23, 1980 DELETING LER 80-20 .s., -w o e.+-*ww en= -a +-mi-eam poweat-4--e..i-e .me y w. -e --9 w gy+...-.m-y p,-n_- --+--new. ,. "g-----= - - * ^ ---

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INTRODUCTION l . ] 1.1 - 3eneral Issue Backoround Fundamental to NRC regulation of nuclear power reactors is the , rinciple that safety systems must perform their intended function j nin soite of the environment which may result from postulated l - accidents. Conformation that these systems will remain functional under postulated accident conditions constitutes environmental cualification. 'The current legal requirements for cualification are'found on General Design Criteria 1 and 4 of Appendix A, - 10 CFR 50; Criterion III and XI of Appendix B,10 CFR 50; and l 10 CFR 50.55a (h). These are general reauirements restatino the principle that licensees should have environmentally qualified l eauipment. 1 : The NRC has used a variety of methods to assure that these neneral legal recuirements are met for electrical safety equipment (Class 1E). In the oldest plants, qualification was based on the fact that electrical comoonents were of Ligh industrial cuality. For the newer plants af ter 1971, qualification was judged on the basis of IEEE-323-1971. -No regulatory guide was ever issued adopting the 1971 IEEE-323 standard, however, many plants referenced IEEE-323-1971 in their licensing submissions to the Comrission. IEEE-323-1971 was written as a trial use standard; a document that briefly and broadly described how to qualify any eauipment, electrical or I otherwise. -This standard did not specify the accident conditions which electrical eauipment must meet. There were no specific recuirements to maintain document files and no specific requirements concerning margin, aging, and other needed equipment specifications. For the newest plants whose Safety Evaluation Reports were issued af ter July 1,1974, the Commission issued Regulatory Guide 1.89 which in most respects adopted the most recent standard, IEEE-323-1974. - In 1977, the NRC staff instituted the Systematic Evaluation Program (SEP) to determine the degree to which the older operating nuclear plants deviated from current licensing criteria. The subject of electrical equipment environmental qualification was selected for accelerated evaluation as part of this program. In December, 1977 the NRC issued a general letter to all SEP plants requesting that licensees initiate reviews to determine the adecuacy of existing equipment qualification documentation. The review of SEP licensee responses indicated certain deficiencies, within the scope of the equipment addressed, such as inadeouate definition of hostile environments, and lack of complete supporting documentation. On May 31, 1979 the NRC issued IE Circular 78-08 " Environmental Oualification of Safety-Related Electrical Equipment at Nuclear Power Plants" which required all licensees to examine installed safety-related electrical equipment, and assure appropriate documentation of it's qualification to function under postulated accident conditions. ewegu =- - m --4-F "+ e v -e 4 .-g,,49 ,g

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( y. 2-- On February 8,1979 the NRC. issued.IE Bulletin 79-01 which was . intended to raise'the threshold of IE Circular 78-08 to the level 'of a Bulletin; i.e., action requiring a licensee response. This bulletin required a complete re-review of equipment e.nvironmental qualification as described -in IE Circular 78-08 within 120 days of. receipt of the bulletin for operating fccilities. It recuired that the licensee provide written evidence of the cualification -of electrical equipment required to function under accident conditions including. (1) Comoonent description, (2) description of

the accident environment, (3) the environment to which the component is cualified,-(4) the manner of. qualification including test methods, and (5) identification of the specific supporting' qualification documentation.

As part of the program to reevaluate the environmental qualification of safety-related electrical eouipment the NRC staff developed more definitive criteria. The Division of Operating Reactors' " Guidelines for Evaluating Environmental Oualification of Class 1E Electrical Equipment in Operating Reactors" (DOR Guidelines) were completed in November,'1979. The 00R guidelines were intended as a screening device to catch those equicment items which might have cualification problems.in operating reactors. In addition, for reactors under licensing review, the NRC staff has issued NUREG-0588, " Interim Staff-Position on Environmental Qualification of Safety-Related Electrical Equipment." On January 14, 1980, the NRC issued IE Bulletin 79-01B which expanded the scope of IE Bulletin' 7901 and requested additional 1 - infor ation on environmental qualification of class 1E electrical ecuipment at operating facilities, excluding the 12 facilities undergoing Systematic Evaluation Program (SEP) review. This bulletin stated that the guidelines and criteria to be used in evaluating the adequacy of class IE equipment qualification would be the 00R guidelines provided as enclosure 4 to the Bulletin. The. intent was to evaluate the qualification of all electrical safety-related equipment subject to harsh environments during postulated accidents in operating plants pursuant to the 00R guidelines. Any problems arising from this review were to be resolved using NUREG 0588 as a guide. The 00R guidelines and NUREG-0588 substantially imorove upon the IEEE-323-1971 standard and provide a level of confidence essentially eouivalent to that which would be achieved from the application of IEEE-323-1974 and Regulatory Guide 1.89. The Nuclear Regulatory Commission, by order (CLI-80-21), directed on May 27, 1980 that the 00R Guidelines and NUREG 0588 form the reouirements which licensees and applicants must meet in order to satisfy those aspects of 10 CFR 50, Appendix A, General Design Criteria (GDC) 4, which relate to environmental oualification of safety related electrical equipment. Licensees of operating reactors were to comply with these reouirements so that the aoplicable ecaipment in all operating plants shall meet the DOR guidelines or MUREG-0588. The JRC staff 4 ap-"W

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r ' B B was directed to complete its review of environmental qualificaticn based on licensee responses to IE Bulletin 79-01B and publish safety evaluation reports on each operating facility by February 1, 1981. By June 30, 1982 all safety-related electrical equipment in all operating plants shall be qualified to the DOR guidelines or NUREC-0588. In order to ccmply with this directive, the Nuclear Regulatory Commission, Operating Reactors Branch, Division of Licensing issued to all operating reactors, on August 29, 1980, an order for i modification of license to provide that "information which fully 1 and completely resconds to the...(IEB-79018)...shall be submitted... not later than November-1, 1980." l 1.2. Soecific Issue Backoround IE Bulletin 7901B of January 14,1980, " Environmental Oualification of Class iE Eouipment", recuired submission within 45 days of (1) A " Master List" of all engineered safety feature systems required i to function under postulated accident canditions, (2) written evidence of environmental. qualification of class 1E electrical ecuitment to function during LOCA conditions and (3) service condition profiles for Loss of Coolant Accident (LOCA), Main Steam Line Breaks inside containment (MSLB), and High Energy Line Breaks outside containment (HELB). IEB-7901B also reauired further evaluations to be made and submitted within 90 days of the bulletin issue date. lhese evalations included (4) written evidence of envi-onmental qualification of all safety related electrical eouincent, both inside and outside containment, to harsh environments per the DOR Guidelines and (5) an evaluation of eouipment location with respect to expected accident flood l evel s. In response to these requirements, Sacramento Municiple Utility District submitted information pertaining to the Rancho Seco facility on March 3, 1980 (45 day response submittal). Further updates of information was made by letter on May 5,1980. The licensee's final submittal of information recuired by IEB-79018 l was made on Octcber 31, 1980 (90 day response). This submittal i was provided in accordance with the reporting requirements of I the Order for Modification of License, dated August 29, 1980. 1 i The licensees' submittal of October 31, 1980 together with information provided during a site visit on December 1-5, 1980, provided the basis for this technical evaluation report. l L3 Purcose This report was submitted in accordance with TI 2515/41 for use as an input to the Safety Evaluation Report (SER) on qualification of Class 1E electrical equipment installed in potentially harsh environments areas of the Rancho Seco facility. The objective was l u mamp4sedulisme ___-__m-.-_-- .__oum___ i_-_..__.m______ .-m

s, to review the licensee's October 31, 1980 submittal and to verify that the licensee has adequately evaluated safety related electrical equipment at the Rancho Seco facility for environmental qualification per the D0R Guidelines. Components detailed in the licensee's submittal were itemized in five categories; (1) ecuipment qualified for plant life, (2) equipment qualified with restrictions, (3) equipment exempt from qualification, (4) eouioment whose qualification is unresolved, and (5) equipment not qualified. In each case reference is made to the components description and function along with the licensee's plans or schedule for qualification or replacement and justification for continued operation. 1.4 Scope The scope of this report is limited to that ecuipment that must function in order to mitigate the consequences of a Loss of Coolant Accident (LOCA) or a Main Steam Line or High Energy Line Break (MSLB/HELB), and whose environment is adversely affected by those-accidents or tne recirculation of fluid from inside containment to outside containment to accomolish long-term cooling following a LOCA. For this reason, qualification aspects not included within the scope of this evaluation are: Seismic qualification. Equipment protection against natural phenomena. Equipment operation service conditions '(for example vibration, voltage, and frequency deviations). Ecuipment exposure to weather. Equipment qualification for " mild" environments. This report included the following service condition criteria as defined in the 00R auidelines: Inside Containment Loss of Coolant Accident (LOCA). Main Steam Line Break (MSLS). Outside Containment High Energy Line Break (HELB). Areas where fluids are recirculated from inside containment to accomplish long-term emergency core cooling following a LOCA. e . ~ -.

f The specific parameters reviewed for conformance with D0R guidelines were: Temperature. Pressure. Radiation. Chemical Spray. Humidity. Submergence. Aging. Coerating Time. The succorting qualification tests reports were not reviewed as part of this report but are listed in Attachment 1 to this report. This listing was prepared from information supplied on the conponent evaluation worksneets submitted as part of the October 31, 1980 response. 4 l e ,-y,~

e 2.0 Evaluation of Harsh Environment Qualification at Rancho Seco This section details the environmental qualification program and equipment cualification status of Rancho Seco Nuclear Generating Station in accordance with IEB-79018 based on the licensee's information submittal of October 31, 1980, and a site visit by regional inspection personnel on December 1-5, 1980 (Inspection Reoort 50-312/80-37). Several modifications to the October 31, 1980 submittal were discussed during the site visit and are incorporated in this report. 1 t .n- ,-,,-,,-,-,--n-- -,-v ,-a, ce,-, --,-,r~~--..--n-- -w.no.- a

. l ~ 2.1 Identification of Safety Related Electrical Eouionent Required to Function in a Harsh Environment (Master List). The licensee enclosed a " Master List" of systems and components required to function while subjected to the defined harsh environments with the 90 day response submittal of October 31, 1930. The steps the licensee recorted as having been taken to ensure a complete and accurate master list were; a) Develoo a list of systems and electrical equipment required to mitigate an accident by l reviewing the FSAR, 00R Guidelines, and Answer 5 in Supplement No. 2 to IE Bulletin No. 79-018. b) Ccmoare tne list of mitigating systems and electrical ecuipment to plant emergency procedures. c) Determine what equipment is on the list and not in tne emergency procedures. d) Add the equipment from (c) to the emergency procedures. e) Determine what equipment in the emerg 'cy procedures is required to mitigate an accident or achieve cold shutdown. (f) Add the equipment in (e) to the list. (g) Determine wnat equipment in the emergency procedures is not required to mitigate an accident or acnieve cold shutdown. (h) Modify procedures to: (i) Indicate equipment is not required for accident mititation. (ii) Identify required equipment that can perform function. (i) Define harsh environments. J (j) Determine if equipment on list generated in (f) is in a harsh environment. (k) All equipment identified in (j) is the master list for this report. The references used in preparing the master list were reported as the FSAR, Administrative Procedure-3, and Emergency Procedures D.5, 0.10, 0.13, and C.47.

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a - The licensee reported in the October 31, 1980 submittal that a field verification of the manufacturer, model number, location and orientation of eouipment was incomplete. Correct installation of eouipment as indicated by the test reports and the use of appropriate sealing devices also remained to be verified in some cases. A regional based NRC inspector reviewed the Containment Isolation System listing in April,19?0 (Inspection Report 50-312/80-12). At that time several discrepancies were noted between the master list prepared for the 45 day submittal (March 3,1980) and installed equipment, particularly with solenoid pilot valves and limit switches. Solenoid pilot valves and limit switches appear to be correctly listed on the October 31, 1980 submittal. The Containment Isolation System outside containment was reviewed and compared to the October 31, 1980 master list by a NRC resident inscector. No problem areas were noted. During the December 1-5, 1980 site visit the licensee stated that P&ID's had been reviewec and that verification of nameplate data of ccmoonents on the October 31, 1980 master list had been performed. The licensee plans to perform furtner walkdowns of the systems to (1) insure proper installation and use of sealed connectors where recuired, and (2) verify the listing of solices, cable, and terminal blocks. This walkdown would start in January,1981 for systems outside containment and would be comolete for all systems Dy the end of the spring refueling outage in May,1981. The licensee stated that the October 31, 1980 master list included all components required to take the plant to Cold Shutcown condition. The October 31, 1980 submittal did not include ccmponents installed per TMI lessons learned requirements. These items will be reported by February 1,1980. Three items were identified by the licensee as missing from the Octcber 31, 1930 master list: 1. Pressurizer Vent Valve HV 21505, 2. Terminal Block, Square D. 3. Cable, Ckonite SKV. These items are discussed in the Equipment with Unresolved Qualification section of this report. i 1 .I

.g. 2.2 Accident Environment Definition (Service Condition Profiles For the purpose of the IEB-7901B resconse, a harsh environment location was defined as an area that would be subject to significantly higher than normal levels of temperature, pressure, chemical spray, humidity, or radiation, as a result of LOCA or MSLB inside the containment structure and HELB or recirculation of fluids following a LOCA. 2.2(a) Inside Containment (LOCA) 0 Temperature FSAR Fig. 14.4-2 (286 max, returns to ambient in 24 HR. ) Pressure FSAR Fig. 14.4-3 (52 psig max, returns to atmospheric in 2a HR.) Humidity 100% Chenical Spray PH = 9.3 to 9.5 (FSAR Table 7.1-1 and answer to Ouestion 6A.1) 3 Radiation 1 X 10 Rads E (Bechtel Calculation 2211-1-0 dated 10/11/80) 0 4 X 10 Rads Y (FSAR page 14.3-11 paragraph 2)*

• This includes a 1 X 10 Rad 40 year service dose.

The flood level following a LOCA was stated as 8 feet above the containment floor (16 feet below grade). Water will raise to this level in 40 minutes. (SMUD letter of fiRC, Director of Reactor Regulation, November 17, 1975). 2.2(b) Inside Containment (MSLB) All reouired electrical equipment has been compared to LOCA conditions to determine qualification. Additional reouirements of tne MSLB environment have not been defined as of the October 31, 1980 submittal date. The licensee plans to perform an analysis to determine if the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLS conditions. The methods described in Section 1.2 for category II plants in NUREG-0588 will be used to perform the aualification. The licensee stated that the analysis will be completed by April,1980 and all equicment will be qualified or replaced with qualified equipment by June 30, 1982. FSAR (Section 14.2.2.1.5) defines peak reactor building pressure as 56 psi for a steam line break with a concurrent active failure of a turbine stop valve. 6 ~

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'. s: e s.., e ~. un' i 2.2(c) Outside Containment (HELB)_ The service conditions defined for a HELS were based on the HELB review in (1) the Rancho Seco Nuclear Generating Unit No.1, Final Safety Analsysis Report Volume VI, Apoendix ldA, page 14A-40, and additional analysis provided in (2) the Bechtel Power Corporation Calculation No. 991-1-0, Ecuionent Qualification P-7 Profiles Cutside Containment of October 23, 1980. These conditions were defined as: Temterature Table 2.2 and orofiles provided Pressure A tmos pheric . Humdi ty 100% Chemical Spray None Radiation See recirculation of fluids 2.2(d) Outside Containment (Recirculatjen of Fluids) The same documents also define service conditions for areas where fluids are recirculated from inside containment to accomolish icng terms cooling following a LOCA as: O Tempera tu re idO F max. Pressure Atnoscheric Humidi ty 1003 Chenical Spray None Radi a ti on Table 2.2 TABLE 2.2 HARSH Et"1IRONMENTS IN ROOMS WITH REQUIRED EQUIPMENT ROOM NUMBER ROCM NAME 200 DAY DOSE PROFILE 001 West Decay Heat Pump Rocn 5.5 x 10 Rads 5.0 002 East Cecay Heat Pump Room 5.5 x 10 Rads 6.0 043 HPI Pumo Room B 2 x 10 Rads 7.0 6 044 Make Uo Pump Rocm 3 x 10 Rads 8.0 046 Seal Return Cooler Room 2 x 10 Rads 051 East Penetration Room 2 x 10 Rads 9.0 052 West Penetration Room 1.3 x 10 Rads 10.0 053 HPI Pump Room A 3 x 10 Rads 11.0 The levels are base on the criteria defined in NUREG 0578. It was noted during the site visit on December,1980 that the environment profile number 11.0 provided for Room 053 does not included the effects of a break within the rocm of a steam line passing through the room. It is an analysis of the transient within the room due to a break external to the room. Further data will be provided by the licensee. The equipment effected are HPI pumps and succorting equipment. 4

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. 2.3 Ecuiorent/Comoonent Evaluation Worksheet Review The licensee's response of October 31, 1980 contained approximately 200 ecuicment/ccmponent environmental qualification worksheets submitted to detail, in accordance with IEB-79018, qualification recuirements and qualification supoorting documentation for components subject to harsh. environments. The worksheets were reviewed and the components were itemized in five categories: (a) Ecuipment Oualified for Plant Life. (b) Equipment Oualified with Restrictions. (c) Equipment Exempt from Qualification. (d) Equipment wnose Qualification is Unresolved. (e) Ecuipment not Oualified. The ecuionent in each category was reviewed with the licensee during a regional based insoeccion on Decemoer 1-5, 1980 (Insoection Report 50-312/80-37). Licensee clarifications and modifications made during that inspection are incorporated in this listing. l l l I l 4 2.3(a) Ecuioment Oualified for Plant Life Review of the licensee's October 31, 1980 submittal and l modifications to that submittal discussed during the December 1-5, 1980 site visit (Inscection Peport 50-312/80-37), disclosed t'ne following comconents whose cualification meets l all apolicable requirenents of the DOR guidelines or flVREG 0588. For each of these items the reviewer has attached notes to sketch information either erroneously recorted or lacking i n the Octooe,* 31, 1980 submittal. The licensee stated that data is available in these areas and will be included on a future submittal in preparation during the December site visit. (9 Items)

22-1. Motor, Joy, 45-26-1170/45.25-26.5-80 Function: R, B..Brergency Coolers, Uoper Dome Air Circulating Units. (Containment) Test Reoort: Joy Manufacturing Company, Summary and Discussion of Design Consideration and Simulated Environmental Testing.

Reference:

(a) Comconent evaluation worksheet pages: B-90, B-91, B-92, B-93, B-94, B-95, B-96, B-97. (b) October 31, 1980 submittal page 4-18 Reviews Note: Comoonent worksheet does not soecify range of DH for chemical soray test. It is not clear thac testing evelooed required pH range. 1 l i 4 ,c - -. -. _ _ ~ -,

- 2.3 - . 2. Motor, Westinghouse, ABW1 Function: Reactor Building Spray Pumps (Room 001, 002). Test Recort: Westinghouse Environmental Qualification of Class IE Motors for Nuclear Out-of-Containment Use, June 1976.

Reference:

(a) Comconent Evaluation Worksheet Pages B-123, B-129 (b) October 31, 1980 submittal page 4-28. Reviewers. Note: Qualified life not defined on conganent worksheet. 9 ...,..,,,,.r. c w n..., -,

24 3. Motor Operated Valve, Limitorque, SMB-3 0 Function: Decay-Heat Removal (Containment) Insulation - 115 C Test Report: Limitorque Report 600376A Limitorcue Report 600198

Reference:

(a) Comconent Evaluation Worksheet Pages B-67, 8-68 (b) October 31, 1980 submittal page 4-12 Reviewers Note: (a) pH of chemical spray test not specified on worksheet. It is not clear t' at testing r enveloped pH range. ,9... I be o 8 w.-m., .~.e., 4. Penetration, Conax Function: Containment Electrical Penetration (Containment) Test Recort: Conax IPS-26, IPS 27, IPS 49, IPS 30, and IPS 375

Reference:

(a) Component Evaluation Worksheet page B-197. (b) October 31, 1980 submittal page 4-45 Reviewers Note: -(a) Reauired coerating time not provided on ccmconent worksheet. (b) Chemical spray qualification data on comconent worksheet did not define DH. (c) Radiation cualification not defined on worksheet, licensee stated that documentation was available to show aualification to 1 X 10" rad. (d) No age data qualification reference on worksheet, licensee stated that data was available to support a 40 year life (IPS 30 and IPS 375). 4 "Y 5. Motor Operated Valve, limituraue, SMB-00 Function: Containment Isolation (Containment) Insulation Class H ' Test Report: Limitorque Test Reoort 600376A and limitoraue test recort 600198.

Reference:

Comoonent evaluation worksheet pages B-6 October 31, 1980 submittal page 4-4. Reviewers Note: (a) Licensee erroneously reported as not qualified for radiation on page 4-4 of October 31, 1980 submittal. i 6 ,. -,. ~.,

27 + 6. Motor Coerated Valve, Limitorcue, SMB-00 Function: H'l 26046 and HV 26047, decay heat crossities (Room 051, 052) Insulation Class H Test Report: Limitorque Report 600A56

Reference:

October 31, 1980 submittal page 4-12. Revisaers Notes: (a) '/alves are on naster list but no compcnent evaluation'sorksheet was provided. The licensee stated that the valves are fully qualified per the referenced test report. 6 e,w e y y e .,p-e-- u,,, w e ,-r-a e .7. ' Cable, Cerro (Rockbestos), Firewall III, PYR0 TROL III 1 Function: Electrical Conductor (Containment) j Test Recort: FIRL Recort F-C2857, 9/70 Cualification of Firewall III Class IE Electric Cables, Rockbestos Company, July 7,1977

Reference:

(a) Comconent evaluation worksheet page: B-193 (b) October 31, 1980 submittal cage 9-45. Reviewers Notes: (a) Chemical spray data on component worksheet does not state pH rance. (b) No age data cualification reference on worksheet. (c) No submergence data reference on worksheet. 1 4 e - - 8. Cable, Contental Wire Function: Electrical Conductor (Containment) Test Report: FIRL Report F-C2935, 10/70

Reference:

(a) Comconent Evaluation Worksheet page 8-199 (b) October 31, 1930 submittal page 4-45. Reviewers Note: Component evaluation worksheet shows cualification to 100% humidity for 24 hr. The qualification of the cable to submergence, chemical spray, temperature, pressure, radiation and aging was not provided on the worksheet. The licensee stated this data was available. l ) 'i l

4 e. 9. Control' Rod Drive, Babcock & Wilcox Function: Control Rod Drive (Containment) Test Report: -8AW tonical recort 10007

Reference:

No component evaluation worksheet provided, alth3 ugh com00nent listed on naster list. Licer.see stated comconent was qualified cer COR guidelines. b e- ~.n,, ,w ,,-en,,. ,-,,+,m-,,n.,,. ---w-r,---.,, -e,.., r,- -, nn.,.+,..... >, -

' ' 2.3(b) Eouitment Oualified with Restrictions Review of the licensee's October 31, 1980 submittal and modifications to that submittal discussed durina the Decemoer 1-5, 1980 site visit (Inspection Recort 50-312/80-37), disclosed the following components qualified to the 00R guidelines with certain exceptions 'such as equicment cualification for service life less than plant life (40 years) or equipment recairing modifications to meet qualification requirements such as relocation or shielding. For these components the licensee's schedule for resolution (submitted with October 31, 1980 response or detailed to the reviewer during the December site visit), is summari zed. For several of these items the reviewer has attached notas to sketch information either erroneously recorted or lacking in the October 31, 1980 submittal. The licensee staced that data is available in these areas and will be included on a future submittal in preparation during the Decemoer site visit. (7 items) e t o w< 1. Flow Transmitter, Bailev, BY8X30XA Function: Cecay Feat Pemoval Crosstie Flow (Room 051, 052) Problem: Age testing not performed. Resolution: 31W analysis of age performance is to be cecoleted by June, 1981. Test Report: Topical Report BAW-10003, Revision 4

Reference:

(a) Component Evaluation Worksheet Pages B-65, B-66 (b) October 31, 1980 submittal page 4-15 Reviewers Note: (a) Accuracy recuirements not addressed on ccmconent worksheet. (b) Operating time recuirements not provided on cccoonent evaluation worksheet. Tested for LOCA environment for i day. 1 ~ +, ,.rme. ,~ -~. -. w. i .2L Pressure Transmitter, Foxboro, EllGM 1 Function: Reactor Building Pressure EFAS Actuation (Roct 051, 052) Problem: (a) No-age data Resolution: B&W analysis of age performance is to be ccmoleted by June, 1981. Test Reocrt: (a) Tooical Report BAW - 10003, Revision a, (b) Foxboro Concany Test Report No. T2-1075 August, 1973

Reference:

(a) Comcenent Evaluation Worksheet Page B-169, B-170, B-171 (b) October 31, 1930 submittal page 4-38 Reviewers Note: Accuracy erroneously specified as 1.85% but demonstrated to 6% (to be correctly stated on future submittal). t 8 y ,,c..- . ~,, y. y ,o ,,m. l 3. Motor Ocerated Valve, limitoraue, 948-000 Function: (a) Decay. Heat System (Room 001, 002, 051, 052) (b) Nuclear service cooling water system (Room 051, 052) (Insulation Class B) Problem: (a) 30 age data Resolution: Licensee will attenot to accuire further vendor data. Test Report: Limitorque 80003

Reference:

(a) Component Evaluation Worksheet cages E-70, 3-71, 3-72, 8-73, S-76, B-77, B-86, 3-37, 3-116, B-117, B-118, S-119 (b) October 31, 1980 submittal page 4-12 Reviewers tiote: (a) Test conditions for temcerature do not enveloce i vapor curve. Recuirements not clear. (b) Age qualification problems are associated with motors not associated limit switches. (c) '.'endor staces valves are qualified for 20 years but justification does not meet 00R guidelines. i l l l*I \\ l

' 4. Motor Ocerated Valve, Limitorcue, SMB-00 Function: Seal injection and makeup system. (Room 043, 052, 051) (insulation Class B) Problem: No age data. Reso?ution: Licensee will attemot to acquire additional vender data. Test Report: Limitorque B-0003

Reference:

(a) Cemconent Evaluation worksheet pages 8-190, B-191, B-192 (b) October 31, 1930 submittal page 4-40 t 6 n<- r.

-36/~7-5. RTD, Rosemount, 177GY Function: Hot and Cold Leg Temperature (Containment) 0 Problem: (a) Evaluation to 1X10 Rad does not include 'possible greater lifetime dose due to location within RCS system. Test Report: Topical Report BAW-10003, Revision 4

Reference:

(a) Comconent Evaluation Worksheet Pages: B-144, B-145, B-146, B-147, B-148, B-109, B-150, B-151, B-161, B-162, B-163, B-164 (b) October 31, 1980 submi ttal page 4-31 Rel ewers Notes: (a) Specified and demonstrated accuracy ti not provided on component worksheets. (b) Ooerating time not specified. (c)Temoeratureandpressureprofilesnot provided (normal service 670 F max, tested to 90 PSI). (d) No chemical spray data provided (sealed unit). L 4 -,w-- .-i,.c . _,,,. ~.... ,___--m,.,,,_-.,..e .c-.,,.,,----y. ,.~.v---. i 6. Flow Transmitter, Bailev, BY3X41X-A Function: Reactor Coolant Flow (Containment) Problem: (a) No age data. Test Re: ort: Topical Reoort BAW-10003, Revision 4

Reference:

(a) Cemconenet Evaluation Worksheet Fages: B-152 (FT 210280) (b) October 31, 1980 submittal page A-33 Reviewers Notes: (a) Comconent evaluation worksheets not provided for: FT21027A FT210278 FT21027C FT210270 FT21028A FT210288 FT21028C (b) Test conditions for temperature and pressure do not enveloce serviceocondition profiles at approximately 5 X 10' seconds. (c) Operating time requirements not specified on component worksheets. (d) No chemical spray data provided (sealed unit). (e) Submergence data not supplied. (f) Radiation qualification on component worksheet less than specified valve. Licensee stated documentation available to shcw qualification. s 6 e

7. Pressure Transmitter, Rosemount,1152GP Function: RCS Pressure (Containment) Problem: (a) No age data. Test Recort: Kinne, Linda, " Qualification Tests for Rosemount Pressure Transmitter Model 1152", Rosemount, Inc., RMT Test Recort No, 117415, Rev. B, September 9, 1975. Reviewers note: ',a) Accuracy is erroneously specified as 1.853 and demonstrated to be 6% on worksheet. (b) Chemical spray data not provided. (c) Temperature / pressure data not provided. (d) Radiation qualification on ccmconent worksheet less than recuired valve. Licensee stated documentation available to show qualification. 4 ,.--,-w.,

..: 9 2.3(c) Eauicment Listed but Exemot from Oualification In the October 31, 1980 submittal, the licensee did not list any equi: ment items in this category. However, some systems were excluded by the licensee (such as auxiliary feedwater) due to location in areas where harsh environments due to steam line ructures would rapidly dissicate to atmosphere. These systems are therefore not included in this review. 4

41~ >i 2.3(d) Ecuioment with Unresolved Qualification Review of the licensee's October 31, 1930 submittal and modifications to that submittal discussed durina the December 1-5, 1980 site visit (Insotection Recort 50-312/30-37), disclosed the following conconents whose qualification to 00R guidelines was incocolete. For these comconents the licensee's schedule for cualification and basis for continued oceration are surmarized. For several of these itens the reviewer has attached notes to sketch information either lacking or erroneously recorted in the October 31, 1980 submi ttal. The licensee stated that data is available in these areas and will be included on a future submittal in orecaration durino the December site visit. (33 items). ~ 4 e y ,y 4--, ,c+

y.. - -.. -..w y

w w rr e-me.- r w c- ..wy-w,- l. Motor Ocerated Valves, Limitorque, SMB-C0 Function: S/G Drains (containment) Insulation Class HR Problem: (a) No radiation documentation Resolution: Written evidence of radiation cualification recuested from limitoraue in October,1930. Basis for Operation: The S/G drains can be ocerated if reactor power is below 15 percent, but are normally closed. HV20611 (outside containment) provides backuo isolation function. (No documentation is availaole for HV20611). Test Report: Limitoruce Recort 600198 FIRL Report F-C2232-01

Reference:

(a) Ccmponent Evaluation Worksheet, pages: 3-1, B-2 (b) October 31, 1980 submittal page 4-4 Reviewers liote: (a) Component worksheet does not specify range of pH for chemical spray test. t i l i e 1 i l 2. Level Tra_,nsmitter, Bailey, BY8841XA Function: S/G Level (Containment) Problem: (a) No age data. (b) located below containment flood level, no submercence data. (c) No chemical spray data Resolution: Obtain missing qualification data. Basis for Operation: Transmitter located within an explosion proof cover. Test Report: Topical Report BAW - 10003, Revision 4.

Reference:

(a) Ccmcenent Evaluation Worksheet pages 8-100, B-101, B-102, B-103, 8-104, B-105 B-106, B-107 (b) October 31, 1980 submittal page 4-20. Reviewers Note: (a) Operating time requirements not specified on ccmponent worksheet. (b) Test conditions for temperature and pressure don't envelope servije conditions at approximately 5 X 10 seconds. (c) Specified and demonstrated accuracy not provided on component worksheets. (d) Licensee erroneously reported qualified on page 4-20 of October 31, 1980 submittal. (e) Radiation qualification listed on component worksheet as less than required value. Licensee stated documentation available to show qualification. i-( o Mpe. A8 ~ 3. Level Transmitter, Bailey, BY3B40X-AX, Function: Pressurizer Level (Containment) Probl em: (a) Nn age data. (b) No chemical soray data. Resolution: Obtain missing qualification data. Basis for Ooeration: Instrument located within an explosien proof

cover, est Report:

Topical Report BAW-10003, Revision 4

Reference:

(a) Ccroonent Evaluation Worksheet page: B-133, B-139, B-140 (b) October 31, 1980 submittal page 4-31 Reviewers Note: (a) Specified and demonstrated accuracy not provided on component worksheets. (b) Test conditions for temperature and pressure do not envelope service condition profiles at approximately 5 X 10' seconds. (c) Licensee erroneously reported as cualified on page 4-31 of October 31, 1980 sucni ttal. (d) Radiation qualification or worksheet is less than required valve. Licensee stated documencation uvailable to show qualification. l l l l 4 l l t ~

4. Pressure Transmitter, Foxboro, EllGH Function: RCS Pressure (Containment) Problem: (a) No age qualification. (b) One transmitter located below flood level and has not been qualified for submergence. (PT 21092) (c) Radiation qualification (by engineering analysis) less that required value. Resolution: (a) Licensee currently plans to move transmitter located below flood level. (b) B&W age analysis performed by June, 1981. Basis for Operation: Function of transmitter located below flood level (PT21092) is accomolished by (PT21099) a Posemount il52GP which is cualified except for aging. PT 21042 and PT 21043 (iocated above flood level) provide same function as PT 21092. Test Report: (a) Topical Reoort, BAW-10003, Revision 4. (b) June 12, 1980 letter to BYW owners group fron F. J. Levandoski. (c) Sears, John A., " Maximum Credible Accident (MCA) Test on Differential and Gauge Pressure Transmitters", The Foxboro Company, Test Report Q9-6005, April,1971. (d) Sears, John A. and Ramsel, Richard, " Radiation Test of E10 Series Differential Pressure Transmitter of the Standard Construction Type...", the Foxboro Company, Test Report No. T2-1075, August,1973.

Reference:

(a) Component Evaluation Worksheet Pages B-165, B-166, B-167 (b) October 31, 1980 submittal page 4-37 Reviewers,;ote: (a) Accuracy is specified as 1.35% and demonstrated to be 6%. (b) Chemical Spray data on component worksheet does not state pH range. (c) Test condition profiles for pressure do not envelope service condition profiles 4 at approximately 5 X 10 seconds. (d) Radiation qualification on worksheet is less than required value. Licensee stated documentation available to show qualification. 6 oi,- --m - +- a.-.. -w ... + p, v ,,.ev--.,. .--<.-~.-- e r-

5. Motor, Allis Chalmers, 531 Function: Pump Room Air Cooler (Room 001, 002, 083, 044, 043) - Problem: The motors are qualified except for two motors located in rooms 043 and 053 which are not analysed for HELB tencerature. Resolution: Analysis to be cerformed to demonstrate cualification to HELB. Basis for Operation: Motors in 053, 044, and 043 provide redundant function. Test Recort: Siemens-Allis Equipment Cualification (Analysis)

Reference:

Comconen evaluation worksheet pages: B-60, B-61, B-172, B-173, B-174 Octocer 31, 1930 submittal page: 4-14, 4-42 Reviewers Note: (a) Operating time reouirements are not defined on component evaluation worksheets. (b) Motor designed to gperate at an ambient temperature of 140 F continuously 6 Motors in rocms 043 and 053 will see 212 F or greater briefly. (c) Profile 11.0 submitted as the HELP environment for Room 053 does not include effects of steam line break within Room 053. (see Westinghous HW5I motors, ITE Imperial Switenes, and GE switches.) 4 ,,r .-,n . - - - ~, e,----,r, -.r. --,c, . -. ~, - -, - - -.

i 6. Terminal Blocks, Kulka, 700 ' Func tion: Connection (Containment) Problem: (a) No age data. (b) No radiation data on worksheet, Licensee stated test data avgilable to 1 X 10' rad. .(recuirement 1 X 10" rao). Resolution: Analysis to higher radiation level will be performed. Basis for Operation: There was,little degredation of the cocoonent at I X 10' rad. Test Report: (a) FIRL Report No. F-Ca927, 2/73 (b) International Nutronics LAB No. 5527 2/16/7B

Reference:

(a) Ccmpenent Evaluation Worksheet Page B-200A (b) October 31, 1980 submittal page 4-47. Reviewers Note: (a) Chemical spray data on component worksheet does not state pH range. (b) Operating time recuirements not defined on ccaponent evaluation worksheet. t 4 r - .v -g-c.. .-<w..-- , ~...

48 7. Terminal Blocks, Souare 0, Type G.X Function: Connection (Containment) Problem: No data orovided, not on master list. Resolution: A test or analysis program will be performed. Basis for Operation: Material similar to Kulka 700. Similar performance expected. Test Report: None P.eference: (a) Component Evaluation Works'neet Page B-2006 -(b) Cctcber 31, 1930 submi ttal page 4-47. i ( l l l 4

-49 8. Motor, Westinchouse, HWSI Function: High Pressure injection pump motors, decay heat pump motors, makeup pump motor. (Room 001, 002, 043, 044, 053) Problem: Motors are qualified except for high pressure injection pumos A&B (Room 043 & 083) which are not cualified to HELB temoeratures. Resolution: Perform analysis of temperature performance or rer0ute steam line. Basis for Operation: Accident mitigation via redundant HPI pump. High pressure injection pumps (Westinghouse HUSI motors) and their associated coolers ( Allis Chalmers 531) are located in rooms which may be subject to more severe conditions than presently postulated (see section 2.2 of this report). The environment profile for Room 053 proviced in the October 31, 1980 resconse does not include the effects of a steam line break witnin the rocm. The environment postulated is that of a main steam line break external to the roca. A main steamline break may inflict temperatures greater than present qualification on these motors. This is furtner complicated by the lack of qualification of the makeup pump transfer switches, if makeup pump is lined up as HPI pump. The licensee stated that the worst case HELB may possibly cause a loss of one high pressure injection pump and the makeup pump. The remaining high pressure injection pump will be qualified to the resulting environment. If one high pressur? injection pump is "out-of-commission" and the makeup pump is lined up as as a nigh pressure injection pump, environmental i qualification presently appears inadecuate to insure the performance of the safety function. i Test Report: Westinghouse Cualification Report WCAP 8745.

Reference:

Comconent Evaluation Worksheet Pages: B-78, B-79, B-185, B-186, B-lS7 October 31, 1980 submittal Page 4-13, 4-41. Reviewers Note: (a) Operating time requirements not defined on component evaluation worksheets. (b) Qualification temperature and pressure not provided. ,l l w w 3 p- ,L i-w ---gw+---- p-t- w --+9e w-w

~. ) ) I 9. Cable Okonite, SMV Function: HPI, nakeue, and decay heat pump motors. (outside containment) i Problem: 'a) No radiation data provided, Resciution: Cualification data to be obtained. Easis for Ooeration: Material does not aopear to be detrimentally affected at i X 10" rad per Table C-1 of COR guidelines. . Test Reoort: IPCEA Publication 5-61 402 l i

Reference:

'a) No Comconenet Evalue: ion worksneet provided. (b) Cctober 31, 1980 submittal page 4-45 Reviewers flote: (al :'iot on master list, no worksheet, i 1 \\ \\ ( i l t i e 4 -. - -a ____._n,,n__,,n,,-~,r-------

l 10. Termination Luas, AMP, Various Function: Termination of Connectors Problem: (a) No Qualification Data Available Resolution: The district will obtain qualification dccumentation by June 30, 1982. Basis for Operstion: The licensee states that the lugs are contained in retallic enclosures which somewhat reduce the effect of the accident environments. These are not however environmental enclosures.~~A program using calibrated tools was used to make connections. Tesc Report: None.

Reference:

(a) No ccmoonent Evaluation Worksheet provided (c) Octocer 31, 1980 submittal page 4-45 Reviewers Note: (a) Not on master list, no worksheet. 1 l l l ~ + ~

+ .. l 11. Insulating Taoe, Scotch, Various Function: Insulate connectors, Scotch 13 (Outside containment) Scotch 23, 33, 35, 70, 88, 110 Scotchfil (Ccntainment) Problem: (a) No cualification documentation available. Resolution: Obtain cualification documentation or replace by June 30, 1982. Basis for Operation: The licensee states that the tape used inside containment is installed in metal enclosures and not exoosed directly to tne chemical spray, (These are not environmental enclos~ures) The taces are desianed to ocerate in a 100 percent humicity environment. Although there is no radiation cualification information on the taces, reviewing the radiation tolerance of materials that are used in insulation tape and the margin in the amount of tace used, the licensee has concluded that the tape will not fail to ground at the voltages applied. The following equipment was reported as having submerged connections using insulating tapes: PLANT 10 FUNCTION SYSTEM FT21027A RCS Loop Flow RPS FT21027B RCS Loop Flow RPS FT21027C RSC Loop Flow RPS FT210270 RCS Loop Flow RPS FT2102SA RCS Loop Flow RPS FT2102SB RCS Loop Flow RPS FT2102SC RCS Loop Flow RPS FT210280 RCS Loop Ficw RPS PT21023 RCS Pressure RPS PT21039 RCS Pressure RPS LT20503A E205 A Water Level MFWS LT205038 E205 A Water Level MFWS LT20503C E205 A Water Level MFWS LT20503D E205 A Water Level MFWS LT20504A E205 B Water Level MFWS LT20504B E025 B Water Level MFWS LT20504C E205 B Water evel MFWS LT20504D E205 B Pa* Level MFWS PT21092 RCS ' essure SFAS The licensee states that the flow transmitters and RCS pressure transmitters in the RPS and the pressure transmitter in the SFAS will perform their function prior to being flooded. _,y,- ---,..,y y y ,,,,y.- ,.m p

• I The licensee adds that because the multiple layers used, the elasticity, adhesion characteristics, and 7 mil thickness of the l

tape, normally provides a moisture tight electrical connection, the circuits should function submerged. ' Test Report: None.

Reference:

(a) No component Evaluation Worksheet was submitted, although listed on master list. (b) October 31, 1980 submittal Page A-46. 4 n --. -n.. r

4 5 12. Flo.s Transmitter, Foxboro. A2020LA-FD Function: Long term boron dilution (Containment) Problem: No qualification data provided. Resolution: Obtain qualification documentation or replace by June 30, 1982. Basis for Goeration: The flow path measured by FT 20001 represents only one of two possible flow paths for boron dilation. The other method than can be used is via HPI to pressurizer. Test Recort: None

Reference:

(a) Component Evaluatien Worksheet Pages: B-62 (b) October 31, 1980 submittal Page 4-16 4 6 13. Flow Transmitter, Bailey, BY8240XA Function: Decay Heat Removal Flow (Room 052). Problem: No qualification data provided. Resolution: Obtain qualification data or replace by June 30, 1982. Basis for Operation: CHS flow can be measured by decay heat removal crosstie flow transmitters which are qualified except for age testing. Test Recort: None

Reference:

(a) Comoonent Evaluation Worksheet Pages: B-63, B-6a (b) October 31, 1980 submittal page 4-15 4 y 1 r 14. Level Transmitter, Bailey BY8231X-A Function: Core Flood Tank Level (Containment) Problem: No qualification data provided. Resolution: Acceptable documentation will be obtained or the units will be replaced by June 30, 1982. Basis for Operation: The level transmitters provide the operator with information as to the relative discharge rates of the two CFT. An uneven discharge rate indicates a break in the CFT discharge line. With this information, the operator can properly align the Decay Heat System (DHS) to provide adecuate core cooling. The level transmitters have no function af ter 7 minutes following a LOCA. Information to operators is also provided by decay heat transmitters located outside containment. Test Report: None.

Reference:

(a) Component evaluation worksheet pages: B-56, B-57, B-58, B-59 (b) October 31, 1980 submittal pages 4-8 4 h . -. - ~

. 15. Pressure Switch, Mercoid, APW-7041-153 Function: Reactor Building Pressure Trip (Room 051, 052) Problem: No qualification data provided for aging and radiation. Resolution: Obtain qualification data or replace by June, 1982. Basis for Operation: Containment building pressure trip function is completed prior to recirculation of fluid. Test Report: None I

Reference:

(a) Component Evaluation Worksheet pages: B-153, B-154, B-155, B-156 i i l t I I l 4 4 f +,. ,v., p a 16. Flow Transmitter Bailey BY3240X-A, BY3241X-A ~ Function: Reactor Coolant Pump Seal Supply, High Pressure Injection Flow (Room 051,052) Problem: No qualification data provided Resolution: Replace or qualify by June,1982. Basis for Operation: The flow transmitters are not required for a HELB outside containment. They will function for a MSLB/LOCA prior to recirculation. Test Report: Topical Retort BAW-10003, Revision 4.

Reference:

(a) Ccmoonent evaluation Worksheet Page: B-175, B-176, B-177, B178, B-179 (b) October 31, 1980 submittal page: 4-42 Reviewers Note: Component evaluation worksheet shows erroneously qualification per topical report BAW-10003, Rev d, however licensee's summary section 4.14.2.3 (page 4-42) states: "flo qualification information... has been received..." Licensee has no qualification da ta. e -... - .. ~,

17. Switch ITE Imoerial Z1193 4 Function: SKV Transfer switch room 052 for HP injection cumo P236. Problem: tio qualification data provided. Resolution: Qualify or evaluate need for transfer switch by June, 1982. Basis for Operation: Pumo is normally used as makeup pump, and redundant HPI pumps are normally available. If makeup pump is lined up as HPI pump the other HPI pumo will not have unqualified transfer switch in circuit. (HPI pump may not be cualified for operation in worst case environment.) (see Westinghouse HWS1 Motors). Test Report: None.

Reference:

(a) Component Evaluation Worksheet pages: 1-180. (b) October 31, 1980 submittal page 4-42. 4 e e-v v e

18. Switch, General Electric Function: Transfer switch (480V) for HP injection value SFV 23508 and fan A5298 for pump P236. Problem: l'odel and qualification unknown. (many components) Resolution: Qualify or evaluate need for transfer switch by June, 1982. Basis for Operation: Pump is normally used as makeup pump, and redundant HPI pumps are normally available. If makeup pump is lined up as HPI pump the other HPI pump will not have unqualified transfer switch in circuit. (HPI pump may not be cualified for operation in worst case envi ronment. ) (See Westinghouse HWSI motors). Test Report: tiene.

Reference:

(a) Component evaluation worksheet pages: 3-181, B-182 (b) October 31, 1980 submittal page 4-43. 4

< 19. Motor Ooerated Valve, Limitoraue, SMB-00 (D.C. ) Function: Seal injection and makeup system (Room 052, 051) (class RH insulation) Problem: Radiation service Conditions exceed radiation qualification test conditions for SFV 23604, SFV 23809, SFV 23811, and SFV 23812 (this is not reflected in all cases on the comDonent worksheets) tested to 1 y 10' rad (worksheet erroniously snows 2 X 10 R) Resolution: Perform test or analysis to show oualification to radiation environment by June,1982. Basis for Operation: Comconents function would be completed prior to component receiving full radiation exposure. Test Report: Limitorque B-0009 (Listed erronously as B-0003 on component worksheet.)

Reference:

(a) Component evaluation.worksheet pages B-189 B-193, B-194, B-195, B-196. (b) October 31, 1980 suomittal page 4-40. Reviewers note: (a) Operating time not specified. s -m>- -,v- ,y

f .L '. 20. Motor Operated Valve. Limitoroue, Unknown Function: Makeup tank isolation and ECCS long term cooldown (Insulation Class RH) (containment) t (room 043) r t Problem: (a) No qualification data. (although section 4.14.2.1 stated no. qualification data for SFV 23508 the worksheeterroneously-(pageB-188)shows qualification per limitorque B-003, I Resolution Awaiting vendor data. Basis for Operation: (a) Makeup tank isolation (B-188) closes on. ESFAS, it'will perform this function prior to receiving' radiation. Specifiedradiation e due to recirculation is y X 10 rad. Valve was purchased for 1 X 10 rad exposure but radiation qualification documentation is missing. Vendor contacted. (b) long term cooldown valves (B-183, B-184) were purchased for in containment use, licensee believes valves are qualified but does not have test data. Vendor. contacted. { Test Report: None. t

Reference:

(a) Component _ evaluation worksheet pages B-183, B-184, B-188 (b) October 31, 1980 submittal page 4-40 l l l*i 1 ~.. _ ~. _ _,_ _.. _._.-._.._._. _.___.._ _.._.-,._ _,....__.~.. _. _.,.. _. _... _ - _ _,... _ _ _.. - _. _ _ _

63-21. Motor Ooerated Value, limitoroue, SMB-00 Function: Letdowr: Cooler Isolation (Containment) Below submergence level, insulation class RH. Problem: Although the licensee status in 4.11.2.1 of the October 31, 1980 submittal that there is no qualification documentation for this valve, the worksheet erroneously shows qualification per limitoroue reports 600198 and 600376A. No qualification data available. Resolution: Awaiting vendor data. Basis for Operation: Redundant valves SFV 22006 and SFV22005 perform safety function. These valves are qualified except for submergence (see worksheet B-141, 8-142) Test Report: None.

Reference:

(a) Component evaluation worksheet pages B-143 (b) October 31, 1980 submittal page 4-30. t a e m + -+ w e w

' 22. Motor Ocerated Valve, Limitoroue, SMB-00 Func ti on * ' etdown cooler isolation (containment) insulation class RH SFV 22005 and SFV 22006 Proolem: No submergence data Resoluticn: Licensee does not intend to demonstrate qualification for submergence base on answer to question 20 of IEB 79018 supplement 2, Basis for Operation: Valves are qualified to DOR guidelines except for sucmergence, licensee states valves will function prior to submergence, and submergence will not affect function or mislead operator to perform incorrect action. Test Report: Limitorque Report 60010 (FIRL FC2232-01) Limitorque Report 600376A.

Reference:

(a) Component Evaluation Worksheet pages B-141, B-142 (b) October 31, 1980 submittal page 4-30 P l 1 i j l l l 4 ._,m

~-' 23. Motor Coerated Valve, limitoruae, SMB-000 Function: Pressurizer Vent, (Containment) insulation Class RH Problem: (a) No radiation data provided Resolution: Awaiting vendor data Basis for Operation: Valves are normally closed and remain closed throughout postulated accidents Test Report: Limitorque Report 600198 (FIRL F-C 2232-01)

Reference:

(a) Ccmoonent evaluation worksheet pages B-136, B-137 (b) October 31, 1980 submittal page 4-30 Reviewers Note: (a) Chemical spray pH data not provided. (b) Operating time requirements not provided. t e a r.,,. ,.n.,. ~, 24. Motor Operated Valve, Limitoraue, SMB-00 Function: Pressurizer Relief stop valve HV 21505 (Containment) Insulation class RH Problem: (a) No radiation qualification data. Resolution: Vendor contacted to confirm radiation data. Basis for Operation: Valve should be qualified to radiation due to class RH insulation. Test Report: Limitorque Report 600198 (FIRL F-C-2232-01)

Reference:

October 31, 1980 submittal page 4-30 Reviewers Note: (a) Although this valve is discussed in section 4.11.2.1 of the October 31, 1980 submittal it does not accear on the master list and no worksneet was proviced, i i 25. Motor Ooerated Valve. Limitoraue, SMB-00 Function: Containment Isolation (Room 002) Decay Heat System (Room 052,046) insulation class B Problem: (a) No radiation data (b) No aging data Resolution: Awaiting vendor data. Basis for Operation: (a) Containment isolation valve closes prior to receiving full radiation dose. (b) Decay heat system valves will function prior.to full radiation exposures. Test Report: FIRL Report No. F-C3771

Reference:

(a) Component Evaluation Worksheet Pages B-20, B-82, B-83, B-84, B-85 (b) October 31, 1980 submittal page 4-4 0 26. Motor Ooerated Valve, Limitoroue, HMB-UT/150 Function: Containment Isolation (Containment) Insulation class RH. Problem: No qualification data provided Resolution: Awaiting vendor data. Basis for Operation: (a) Valve outside containment (SFV 53503) will provide same function. (b) Valve is normally closed and locked closed. Test Report: None

Reference:

(a) Component Evaluation Worksheet Page B-14 (b) October 31, 1980 submittal page 4-4 27. Motor Goerated Valve, Limituroue, SMB-00 Function: Containment Isolation (Containment) 0 Insulation Class (ll5 C) Problem: (a) No age data (b) No chemical spray data (c) No qualification to containment environment. (Tested to outside containment profile.) Resolution: Licensee is attempting to obtain additional qualification data. Basis for Operation: (a) Valve outside containment (SFV 2209) provides redundant function. Test Recort: Limitorque qualification type test report No. 80003 (Outside containment qualification, valve located inside containment).

Reference:

Component evaluation worksheet B-5, October 31, 1980 submittal page 4-4 l l 28. Motor Ooerated Valve, Limitoroue, Unknown Function: (a) Steam Generator Drain (Room 052) Model unknown (b) Long Term Boron Dilution (Containment) SMB-00 insulation class B Problem: Model identification and/or qualification unknown no qualification data. Resolution: Awaiting vendor data Basis for Operation: (a) S/G drain functions prior to receiving full radiation dose. Closed at greater than 15% power. (b) Long term boron dilution provided by redundant valves believed qualified. (See B-183, B-184) Test Report: None.

Reference:

Component Evaluation Worksheet Pages B-3, B-69 October 31, 1980 submittal page 4-4 4 ~ + .- c 29. Motor Ooerated Valve, Limitorque, SMB-0, SMB-00 4 Function: Containment Isolation (Containment, Room 002) Insu11ation Class H or RH Problem: (a) No radiation test data (b) No brake cualification data on SFV 66308. (located in Room 002) Resolution: Awaiting vendor data. Basis for Operation: (a) Redundant valves outside containment provide safety function. (b) In some cases valves are locked closed. (c) SFV 66308 will function prior to radiation exposure. Test Report: Limitorque Report 600198

Reference:

(a) Ccmoonent Evaluation Worksheet Pages B-9, B-12, B-15, B-16, B-18, B-22, B-27 (b) October 31, 1980 submittal Page 4-4 Reviewers Note: Chemical spray pH not specified. 4

_72 30. Motor Operated Valve, Limitoraue, SMB-00 Function: Containment Isolation (Containment) Insulation Class H and RH Problem: (a) No data Resolution: Awaiting vendor data. ?I Basis for Operation: (a) Redundant valves outside containment provide safety function. Test Report: None.

Reference:

(a) Comoonent Evaluation Worksheet Pages B-24, B-26 (b) October 31, 1980 submittal page 4-4 Reviewers Note: Ccmconent Worksheet B-26 erroniously shows valve cualification documented, by limitorque 600198, submittal correctly page 4-4 states no aualification data available. 1 31. Motor Operated Valve, limitoraue, SMB-00 Function: Reactor Building Spray (Room 052, 051) Insulation Class B Problem: (a) No radiation qualification or aging. Resolution: Awaiting vender data. Basis for Operation: (a) valves function prior to receiving full radiation dose postulated. Test Report: Limitorque B-0003

Reference:

(a) Component Evaluation Worksheet pages B-132, B-133 (b) October 31, 1980 submittal pages 4-27 Reviewers Note: (a) The licensee states in section 4.10.2.1 (submittal page 4-27) that no radiation qualification is available, however, the component worksheets erroneously show sequential testing to 2 X 10' rad. e een,... ~ - n-

-7a-32. Motor Ocerated Valve, Limitoroue, SMB-00 Function: Nuclear Service Cooling Water (Room 051,052) Insulation Class HR Problem: (a) No radiation qualification Resolution: Awaiting vendor data. Basis for Operation: Safety position is open, presently operating with valves open. If closed, valves will open prior to full radiation exposure. Test Report: Limitorque Report 600198 (Report 600456 erroneously reported on worksheet)

Reference:

(a) Comoonent Evaluation Worksheet Pages 8-120, B-121, B-122, S-123, B-124, B-125, S-126, B-127 (b) October 31, 1980 submittal pages 4-24 Reviewers note: (a) Operating time not defined (b) The licensee states in Section 4.9.2.1 (submittal page 4-24) that no radiation qualification has been performed on these valves, however, the component wogksheets show sequential testing to 2 X 10 rad, t 1 l l 1 l

. 33. Motor Operated Valve, Limitoroue, SMB-00 Function: Reactor Building Spray System (Room 001,002) Insulation Class B Problem: (a) No age testing (b) Radiation qualification less than service condition requirements Resolution: Awaiting vendor data. 7 Basis for Operation: 5.5 X 10 rad is 200 day dose. Comoonent functions within 1 day. Test Report: Limitorque B0003

Reference:

(a) Ccraconent Evaluation Worksheet Pages B-130, B-131 (b) October 31, 1980 submittal page 4-27 8

• 2.3(e)

Eauionent tiot Oualified The following equipment was found to be not oualified for it's required harsh environment service af ter review of the component evaluation worksheets submitted with the licensee's October 31, 1980 response and discussion with the licensee during the December 1-5, 1980 site visit (Inspection Report 50-312/30-17). Equipment listed has been demonstrated to be unqualified or a determination has been made that reasonable assurance does not exist to ensure that the Class IE electrical equipment can perform their safety-related function. Inadequate or no data were factors in this determination. The licensee's schedule for replacement and basis for continued operation submitted with the October 31, 1980 response or licensee event reports, are summarize for each component. (5 items) l 1 t 1 1 )

_77-1. Solenoid Valves, Asco, (Various) Function: Containment isolation (Room 051 or 052) Models LB834aA1, 8344B27, HT80173, FT80033, FT-8211-01, 8302C29RG, FT-8211-833, HT-8316-B17, 8302C25RG. Problem: (a) Not qualified to radiation environment. (b) Not qualified to HELB environment. Resolution: Replace with qualified comoonent by June 30, 1982. Basis for Operation: Valves will perform their function prior to radiation excesure due to recirculating fluids. Redundant MOV's will also close to isolate containment Test Report: None.

Reference:

(a) Component Evaluation Worksheets Pages: B-30, B-31, B-32, B-33, B-34, B-35, B-36, B-37, B-38, B-39, B-40, B-41, B-42, B-43. B-44, B-45, B-46, B-47, B-48 B-49, B-50, B-51, B-52, B-53, B-54 and B-55 (b) LER: 80-43 (Attachment 4) (c) October 31, 1980 submittal page 4-5 t t 8 e -w ,,,e-, .-,,-----,-m -i. v

78 = 2. Limit Switches NAMC0 (Various) Function: Containment isolation valve position indication. Models M8-300, D1200C Series, (Room 051 or 052). Problem: Not qualified to the recirculating fluid radiation levels. Resolution: Replace with qualified component by June 30, 1982. Basis for Operation: The limit switches provide operator indication of containment isolation valve position. They will function properly prior to recirculation. Test Report: None.

Reference:

-(a) Comoonent evaluation worksheet pages: B-4, B-7, B-8, B-10, B-ll, B-13, B-17, B-19, B-21, B-23, B-25, B-28, B-29. (b) LER: 80-45 and 80-20, SMUD letter of April 23,1980 (Attachment 4). (c) October 31, 1980 submittal page 4-6 l l

e . J3. Limit Switch, NAMCO, EA180 Func tion: DHS pump trip (Containment) Problem: (a) Limit switches require a sealed connector Eto assure qualification which is not installed. (b) Age qualification incomplete. Resolution: A qualified connector will be installed by June 30, 1982. Basis for Operation: The limit switch is used to trip the DHS pumps. The trip signal is automatically terminated in 3 minutes allowing the pump to operate. Also, safety features actuation overrides the trip signal. Test Report: NAMCO EA180 test report 3/3/78.

Reference:

(a) Comconent Evaluation Worksheet Pages B-67A, B-68 (b) October 31, 1980 submittal page 4-15. 4 a ~

. 4. Pressure Switch, Meltron Coro, 312-49A 4 Function: The pressure switches initiate isolation of the steam generator from the main feeccater following a low pressure indication. (Containment) Problem: No qualification documentation. Resolution: The licensee is designing a new main steam line break detection system to meet the requirements in NUREG 0667. This design will use qualified pressure switches. The main steam system pressure switches will be replaced with qualified units by June 30, 1982. Basis for Ooeration: Design Review concluded that the two credible failure moces (short or ground) would not prevent the circuit from performing it's intenced function. Test Report: None.

Reference:

(a) Ccmponent Evaluation Worksheet Pages: 8-108, 8-109, B-110, B-111, B-ll2, B-113, B-114, 8-115 (b) October 31, 1980 submittal page 4-22 (c) LER 80-44. (d) SMUD letter to Mr. Denton, Director Office Nuclear Reactor Regulation dated October 5,1979. .1

• l

5.- Pressure Transmitter, Westinghouse, 59PH Function; Reactor Coolant Pressure Trips (Containment) ' Problem: (a) No qualification data provided. (b) Two transmitters located below flood level and are not oualified for submergence. Resolution: Replace by June 30, 1982. New Westinghouse transmitters are available, seismic qualification of power supplies is in progress. Basis for Operation: Valves will operated prior to submergence. Test Report: None

Reference:

(a) Component Evaluation Worksheet Page: B-157, B-158, B-159, B-160 (b) October 31, 1980 submittal page 4-34 (c) Response to IEB-7901 June 9, 1979. 4 -~

3.0 - Summary - Due to the technical. evaluation reporting requirements. imposed by the. Commission Order of May 27, 1980, this evaluation has - been based on the. licensee's submittal dated October 31,.1980. made in response to IEB-7901B and the order for modification of license of August 29, 1980, and on interviews with licensee personnel. involved with the environmental. qualification effort during.the week of December 1-5,1980-(Inspection Report 50-312/80-37). Although the licensee's October 31, 1980 response appeared 'to address all items required by IEB-79018.and supplements 2:and 3 of this bulletin. dated September 29, 1980 and October 31, 1980 respectively, numerous errors in this response' were identified during the December 1-5, 1980 site visit. Three items were identified by the licensee as . missing from the master list as submitted. Numerous errors and inconsistencies were identified on the component evaluation worksheets, and component evaluation worksheets were missing for some' componer ts. The licensee had also stated that several components were qualified although a review of the - component worksheet with the licensee disclosed that insufficient data was available to support that Conclusion. Moreover, the licensee's outstanding item list, included as Appendix D in the October 31, 1980 response, did not truely reflect the status of unresolved qualification. issues. During the week'of December 1-5, 1980 the reviewer met with licensee personnel involved with.the environmental qualification effort and reviewed the licensee's position with respect to environmental' qualification for each component listed on the master; list. Particular emphase was placed on the following issues: (a)' A clear. statement of qualification status and unresolved isses. (b)- Licensee's plans for resolution of unresolved issues. (c) Licensee's basis for continued operation with unresolved issues. This report details.the equipment status.as identified in that j meeting. The reviewer did not review any supporting qualification I reports or data. l The licensee was aware of the numerous errors in the October 31, 1980 submittal and planed to make an edited submittal in the December 1980/ January 1981 time frame. related equipment required to mitigate an accident (LOCA, HELBsubmit The licensee's October 31, 1980 and bring the plant to a cold safe shutdown condition. r ~ *.,, gn n,e .,,,.e ,,,n., .,,,..,,..,,,w,~~~,v,,....n,,...ne ,,.,,-,..s v.-+ .,,,..-..v,..w,,,wa, w,,,,,n,vnn,, v.,a n e ,,v. The licensee's October 31, 1980 submittal did not include equipment installed per the TMI action plan. The qualification information for this equipment will be provided by the licensee by February 1,1981 in accordance with IEB-7901B, Supplement 3, of October 4, 1980. No components have been identified by the licensee as having a qualified life of less than 40 years (age qualification is incomplete on many items). A program of periodic replacement of this type of component will be addressed if further review identifies such equipment. The licensee stated that documentation was available at the SMUD Headquarters in Sacramento, California, to support the equipment qualification status of this report. The reviewer noted that if one HPI pump is replaced by the makeup pump, as is presently permitted in the technical specifications, environmental qualification appeared inadequate to insure the performance of the safety function in some accident conditions. This is discussed in unresolved equicment item Nunber 8 (Westinghouse HWSI Motor). The licensee stated that a clear statement of the issue would be made in the December / January submittal. l l l 4 -,-w- +.. -

84-4.0 References. License Submittals: TITLE DATE IES 7901

Response

July 9, 1979 IES 7901B 45 day response March 3, 1980 IEB 79018' 90 Day interim resoonse May 15,1980 IEB 7901B Final response (per the order for modification of license of August 27,1980) October 31, 1980 NRC Inscection Reports: Inspection Report (50-312/80-12) April 7, 8 and 10,1980 Inspection Report (50-312/80-28) September 2-5, 1980 Inscection Report (50-312/80-37) December 1-5, 1980 4 ATTACHMENT 1 TECHilICAL EVALUATION REPORT ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMEtiT TO HARSH ENVIRONMEllTS IEB-7901B RANCHO SEC0 QUALIFICATION TEST REPORTS i I 6

This table details the qualification test reports referenced in Sacramento Municipal Utility District's October 31, 1980 submittal in response to IEB-79018. These reports were extracted from the ccmponent evaluation worksheets included with that submittal. 1 .~,

- ' ' 8 Ref. No. Test Reoort or Document Equipment item 11.. Limitorque-Report 600198 Limitorque Motor Operated Valves 2. Limitorque Report B0003 .Limitorque Motor Operated Valves 3. l Limitorque Report 600376A Limitorquel Motor Operated Valves 4. FIRL Report No. F-C2232-01 Limitorque Motor Operated Valves 5. FIRL Report No. F-C3271 Limitorque Motor-Operated Valves 6. Siemens-Allis -Equipment Qualification Allis~ Chalmers Motor 7. Topical Report BAW-10003, Revision 4 Bailey Meter 4 Transmi tters i 8. .NAMCO EA-180 Test Report Limit Switches 3/3/78 9. Westinghouse' Qualification Report WCAP 745 Westinghouse Motor 10. Joy Manufacturer Company, Summary and Joy Motor and Discussion of Design Considerations and Simulated Environmental Testing. 11. Limitorque Report 600456 Limitorque Motor Operated Valves t 12. Westinghouse Environmental Qualification Westinghouse Motor of Class IE Motors for Nuclear Out-of-Containment use. June 1976 13. June 12, 1980 Letter to B&W Owners Temperature Group' frem F. J. Levanduski Elements 11 4. Conax IPS-491/17/72 Penetrations 15. Conax IPS-27 1/4/71 Penetrations 16. FIPL Report F-C 2857 9/70 Cable j 17. FIRL Report F-C2750 3/70 Cable 11 8. .FIRL Report F-C293510/70 Cable 19. FIRL Reoort F-C4927 2/78 Terminal Blocks j 20. International Nutronics Lab. No. 5527 2/16/78 Terminal Blocks i i --,~,...,G.---m.. .1-.,--. .-.,,...-,-...-_.,.~a.--.,-,,..~,_.,.,-.,,,. .,r.., 1 .-;--c-

. Ref. No. Test Reoort or Document Equioment Item 21. Sears, John A., " Maximum Credible Accident (MCA) Foxboro Pressure Test on Differential and Gauge Pressure Transmittal Transmitters", The Foxboro Company, Test Report Q9-6005, April, 1971. 22. Sears, John A. and Ramsell, Richard, " Radiation Foxboro Pressure Test of E10 Series Differential Pressure Transmitter Transmitter of the Standard Construction Type ..., the Foxboro Company, Test Report No. T2-1075, August, 1973. 23. Kinne, Linda, " Qualification Tests for Rosemount Rosemount Pressure Pressure Transmitter Model 1152", Rosemount, Transmitter Inc., RMT Test Report No. 117415, Rev. 8, Septemcer 9, 1975. 24. Limitorque Report B0009 Motor operated valves 25. IPCEA Publication 5-61-402 Cable 26. BAW Topical Report 10007 Control Rod Drives l t l l l

. ATTACHMENT 2 TECHflICAL EVALUATION REPORT ENVIRONMEilTAL QUALIFICATION OF SAFETYY RELATED ELECTRICAL EQUIPMENT TO HARSH ENVIRONMENTS IES '79018 RANCHO SECO ( COMPONE?lT TYPE /MODEL LISTIflG L i i l l f l ( l 1

a 90 This table details the component types or models requiring harsh environment qualification per Sacramento Municipal Utility District's October 31, 1980 submittal. to IEB-79018. These component types /models were extracted from the component evaluation worksheets included with that submittal. 9 4 4 r,

- Ref. No. Comoonent Manufacturer Tyoe/Model 1. Motor Operated Valve Limitorque SMB-0 2. Motor Operated Valve Limitorque SMB-00 3. Motor Operated Valve Limi torque SMB-000 4. Motor Operated Valve Limitorque SMB-2 5. Motor Operated Valve Limitorque SMB-3 6. Motor Operated Valve Limitorque HMB-UT/150 7. Motor Westinghouse ABW1 8. Motor Westinghouse HWSI 9. Motor Allis Chalmers 531 10. Motor Joy Manufacturing 45.25-26.5-80 45-26-1170 11. Penetration Conax 12. Cable Cerro Firewall III Pyrotrol III 13. Cable Continental Silicone Rubber 14. Terminal Blocks Kulka 700 15. Terminal Blocks Square D Type G, K 16. Switch ITE Imperial Zl193 17. Switch GE Unknown 18. Limit Switch NAMC0 EA180 19. Limit Switch NAMC0 M8-300 20. Limit Switch NAMCO D1200G Series 21. Solenoid Yalve ASCO LB8344A1 22. Solenoid Valve ASCO 8344827 23. Solenoid Valve ASCO HT80173 24. Solenoid Valve ASCO FT80033 25. Solenoid Valve ASCO FT-8211-B33 e Ref. No. Comoonent Manufacturer Tyoe/Model 26. Solenoid Valve ASCO FT-8211-01 27. Solenoid Valve ASCO 8302C25RG 28. Solenoid Valve ASCO 8302C29RG 29. Solenoid Valve ASCO HT8316-B17 30. RTD Rosemount 177GY 31. Pressure Switch Mercoid Corporation APW-7041-153 32. Pressure Switch Meltron Corporation 312-49A 33. Pressure Transmitter Foxboro EllGM 34. Pressure Transmitter Foxboro EllGH 35. Pressure Transmitter Rosemount ll52GP 36. Pressure Trasmitter Westinghouse 59PR 37. Flow Transmitter Bailey BY3X41X-A 38. Flow Transmitter Bailey BY3241X-A 39. Flow Transmitter Bailey BY3240X-A 40. Flow Transmitter Bailey BY8240XA 41. Flow Transmitter Bailey BY8X30XA 42. Flow Transmitter Foxboro A2020LA-FD 43. Level Transmitter Bailey BY3840X-AX 44 Level Transmitter Bailey BY8231X-A 45. Level Transmitter Bailey BY8841XA 46. Control Rod Drive Babcock & Wilcox-47. Cable Okonite Unknown (SKV) 48. Termination Lugs AMP Various 49. Insulating Tape Schotch Various l .\\ e -, - ~ l

4 I i I ATTACHMENT 3 TECHilICAL EVALUATION REPORT E:lV!RONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TO HARSH ENVIRONMEtlTS IEB-7901B RANCHO SECO HARSH ENVIRO llMENT AREAS t .. -..,., -,, ~,... - +

_94 These drawings detail areas considered subject to harsh environment conditions as reported in Sacremento Municipal Utility District's October 31, 1980 submittal in response to IEB-79018. 9 4 -w -a +,- ..n. ..,..,..~. -.-.,,-~.--

95-PLANT ARRANGEMENT ORAWINGS LIST OF DRAWINGS TITLE Basement Level Plan Elevation (-) 20' Grade Level Plan-Elevation O' 'e::anine Level Plan - Elevation 20' Turbine Deck Level Plan - Elevation 40' l

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y -101-ATTACHMENT 4 TECHNICAL EVALUATION REPORT ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT TO HARSH ENVIRONMENTS IES-7901 RANCHO SECO LICENSEE EVENT REPORT N0. 80-20 LICENSEE EVENT REPORT N0. 80-43 LICENSEE EVENT REPORT NO. 80-44 LICENSEE EVENT REPORT NO. 80-45 LICENSEE LETTER OF APRIL 23, 1980 DELETING LER 80-20 1 4

-102- ?i S M U D 'M SACRAMENTO L'UNICIPAL UTILITY O! STRICT C C:01 S Street, 8:x 15220, Sacramento, California 95a13; (916) 452 3211 '?: April 17, 1980 RJR 80-189 l Mr. R. H. Engelken, Director Region V Office of Inspection & Enfercerant U. S. Nuclear Regulatory Cc= mission 1006 harth California Boulevard Walnut Creek Plaza, Suite 202 Walnut Creek, Califormia 94596 Re: Operating License DPR-54 Docket No. 50-312 'acorti:le Occurrence 80-20

Dear Mr. Engelken:

In accordance witn the requirements of I&E Bulletin 79-013, the Sacra: ento Municipal Utility District is hereoy reporting the follow-ing as Reportaole Occurrence o0-20. 'i r. J. Elin. of your office, visited Rancho Seco on April 7 through 10, 1950. The purpose of the visit was to deter =ine and discuss 73 the status of the District's answer to II Sulletin 79-OlB. During that T/ visit, Mr. Elin was inforced tnat several safety related valves in the -20 of the Auxilia ry Luiicing we re idcntified as having NAMCO switches, which are not e:...:.at.e...aily qualified f o r ope ra tion in high radia tion cu' j ect to adverse effects of.a line break. areas or areaa t..a t cau. ce o E'll:w-up report -;1 be subsitted to your office within 2 fourteen dayc. CerpectfuIy)sbcitted, j g y ' G "* Ro'riguez, l R. J. d Manage r, ';ucicar Operations RJ R:i!!!: b ka l cs: Director, MPC (2) l l l l l l &cnt/venfied. l 1 I 4-t7-EO 0950i / ( c.J. O .( hh b1 ' \\', [G( L-T) ~ . C.~ a.'. 3 '7 ' AN ELECTRIC SYSTCM '; t R y l N G M0RC THAN 600,000 IN THE HCART Of CAL Q

a -103-5$Nb SACRAMENTO '.tu?UC: PAL UTitlTY CISTRICT O Cl 3 Street. Box 15320. Sacrarrento, California 95813; (916) 452 3211 .3 x April 23, 1980 1 k5-6 iw,,.' Mr. R. H. Engelken, Dir2:ter IY , '. - S 4 f r Region V Of fice of Intrettien S Enfer:e ent C U. S. Nuclear Regulaterv CC 9ission t'e '-7 '.,,, d ,e /- t-i- ~.9 3/ 1990 Nor tn Cal i for,i3 9 u!evard V,. Walnut Creek Plaza. Suite 202 \\.4;- AJ Walnut Creek, California ?L:04 X[;pg'(9' -Os Re: Operating License DPR-54 Docket No. 50-312 Recortable Occurrence 80-20

Dear Mr. Enceiken:

Su!!etin 79-013 issued January l*, 1950, item 6, required the Distri:t to ma <e an immeciate recort i r nonenvi romnenta l ly cual i fiec comconents are utili:ec as sarety equipment anc requirec to function curing postulated ac ! dents. Ac:Or: aas sucmitted to your office on Apri1 17, 1980 stating tha t NAMCO 3ai tenes, Mo:ci Nos. M-2-3CC and Ol200G, were icen ti fied on sa fe ty rela tec vai,e3. Tne s u s equ-:n t investigation determined that these switenes ~. 43 are sole 1 / u : i i :.a: rar iignt indication. 3~.it naa mc ca t :. ntrol ac tua t icn, position nor any other interlock ~ functicn. T.ar. ;re,.,i ; ; c:: rren e is not reportable and Reportable Cccurrence 80-20 aiii :2.u ;.: c u ? rem the uE.', fiIe. Respectfully submitted, _-l9d/>Li~C,.A -). ."J. Mattimoc As s is tan t General Manager and Chief Engineer JJM : W.': : j r es: Directar, niPC (.' ) h I .~ afar.: *:. g CALt@t */ N ')( AN ELCtfRlt t Y ". T E M S E RVI N C MORE THAN 600.000 IN THE HEART Of j '-

• i is

-104-e -=G-t. $g; SACRAMENTO MUNIO! PAL UTILIT/ DISTRICT C 5 SMUD 15320. Sacrarnento. California 95313: (916).t523211 RJR 80-560

ovember 3, 1980 f

[/\\ s u , n = .4 A 9". f.l #. s, Aq y Mr. R. H. Encelken, Director ,e l. W'r, 3,m -c c - / Region V Office of Inspectien & Enforcerent \\.s M. o / \\jGF [ U. S. Nuclear Reculatory Cor:.im ien 1990 :: orth California Boulevard 'hj% 1 Walnut Creek Plaza, Suite 202 Walnut Creek, CA 94936 Re: Oceratinz License DPR-34 _ u.e t ::o. 50-312 _'.c.c r able Occur rence 50-4 3

Dear Mr. Engelken:

n accercance witn Iecnnical Speci:ications Section 6.9.4.1 (1), the Sacramento Municipal L'tility District is nereby submitting the following written confir=ation of a 24-heur Licensee Event Report initially reported to 'dr. O. : wet::ig of your of fice on Octooer 31, 1930. / p~~.9 .u a rauuit u: Iu ;;. Julietin 79-013 review, it was determined that certain centa anent ise.atica valves,specifically the air-operated valves, ut;.;ce s dena., pl.o calves walen do not meet the current environment ~ p..;.;ctica eri.eri. .;c u.enca valves la questica are manufactured by s J.Z ) and ara act; qua.1fied to reciraulating fluid Autc=stic a it;. w. radiatice : /. c l.3 folicwing LC"J.. u.a Di.:trict'a intent to replace the solenoid valves en5 envircum :n ta. '. .n.111f :.:.! unit o in accordance with the ti:nc frame sps. .cd in the bulle n. In t%' in t e r ie., j ustification f or continued operation .s -redicat d n the "alves bein;; outaide con tainment isolation valves. <:ocatien nac a redun.lant inside containment isolatica valve Ea ch va '. >.' "u ! i t led "~tnr Operated Valve. chich ..a /s

lled r. port will be nubmitted to your office within 14 days.

Rincerely, )s g sG' '\\ s R .I. Rodrigot ?. ".in.t;;e r, Nucita r Ope rat ions RJ R :1!!! : r= / 7au w.2 //+ A)$ D 17 0 OGJ es: Directcr, I M. 'la n h i n g t on, D.C. .v A-Dir e c t o r. "Ii'C, '<.'an h in g t on, D. C. \\

1. ~'

~f ( o,m.a m, n. ..a m.

-105-N' SACRAMENTO MUNIC: PAL UTlLITY DISTRICT [] 6:01 S Street. Box 15320. Sacrament:. California 95313; (916) 452 3211 d RJR 80-561 November 3, 1980 G ; dlj/> s - r- ~. Q, D~... '69^ %,p ~ l-m

• y

~,, Mr. R. H. Enge l '.en, Director p' T,3.W* ,,q. C'. ,c,-, '&p Q, Reg ion 'l O f f i :2 of Ins:ection L Enforce ent

),

U. S. Nuc l ea r Regu l a to ry Cc~,i s s ion yb '. @)./ 1990 North California hulevard Walnut Creek Plaza, Suite 202 Walnut Creek, California 96936 Re: Opera ting License DPR-54 ^ ::Nat 'l o. ~0-312 ?.erer:acl e Oc:urrence c0-44

Dear Mr'. Engelken:

In 2:corcance wi tn Tecnnical Speci fications Section 6.9.4. l(i), the Sacramento Municipai Ctility District is nereoy suomi tt ing the following wr i tten con fi rma tion of a 28-ncur Licensee Even t Report initially reported to Mr. G. Zwetzig of your of f ice on uc tocer 31, 1930, 2.] As a res it of i;E Bulletin 79-013 review, i t was determined tha t at present no q ua. i f i ca t ; cn cocu.aen ta tion is available for the pressure switches utili:cd in tne aia stec. 3 y ;> c em. ii.e se pressure swi tches are manu f actured by c.. cre utilice: to ini tia te isolation of the s team generator Meletron Corp;rati n f rem :ne main N.:..a ;;.r ; c i i c.ii ng a icu pressure indication. Cu2 : :,. ; m.: uire...un t s u r. G EG 0660, the District is presently design-u arca cf " sin S team Line Failure Lcgic. The new system ing a new s y a ::.:. wilI be designeJ

P :. nce an ta mau :I n;; a l I the requi red quali fica tions.

Instal-latien of the .i si::: uill a l lev i a te tne necessi ty of requi ring quali fication i documentation of ~5e l'e !c t ron pres sure swi tches. Either the new system will be installed and crer,tiunr.1 er.hc cxis ting t' ele trcn swi tches will be replaced within the ti e f r ne s.:ecified in the bulletin. f l~ .ua ca r t -eill be suLaitted within 14 days. n " i n ce tie t yb b 1. DI R. J.. Rod r i gu,t z Hanageh, Nucle,rOperations RJR:HH:je ?]sbe+.a& //~3 *ih , 9 M O.? *f 3 i

fi

'g l'! J %' $ y'"}o ll4 Wjnp f. ? N A T. ILCC*Ett "Yt!!" t ! * '! ! :; C " Oft f if : '. t t t.0 0 0 ! *; IHt HtART OF C A, l F O R f; f A,

-107-c $*) SACRAMENTO MUN:0! PAL UTILITY CISTR S M L' J C CD1 S Street, Box !!a20, Sacramento, California 95313, (916) 452 3211 RJR 80-568 November 5, 1980 m M Mr. R. H. Encelken, Direct:- / 'O, 4 d\\ ca g d,n%w"d, Region V Of fice of las:ecticn r, Enforce ent p Y, %p/.'a$ $ M U. S. Nuclear Pegulatcry Cc missicr. 1990 North California Soulevard P h,.., g$ <O] Walnut Creek Pla:a, Suite 202 Walnut Creek. Ca l i fo rn ia 95936 Q. M Nfg3, Re: Operating License DPR-54 Docket No. 50-312

ecortable Occurrence 80-kh Cear Mr. Engelken:

In a::Orcance witn Tecnnical Soeci fica tions Section 6.9.4. l (i), the Sacramento Municipal Utility District su:mi t tec wri t ten con fi rma t ion of a 24-hour Licensee Event Report on hovemoer 3, 19c0. At the recuest of Mr. R. Faulkenberry and G. Zwetzig of your staff, tne folicwing additional information is being submi t ted. The ' cvericer 3, i300 le tter accressed the inabili ty to octain quali-(,' fi ca t ion docu.nentaciun for heietron pressure s.witenes in accordance witn ISE Bulletin 3-013. naciticnaliy, tne ie t ter addressed the Dis trict's plans to meet tne env;ru.c.enta, wei;;.ca ticn requi remen ts wi thin the speci fied time f rare.. 7 m rev ;.e,, 2 : rctica for in terim opera ti on, District engineers have re v i c..eu,,.: .ea i.;n o f tne ci re.ui t associa tec wi th the Hele tron swi tches. The design revin ::nc!J:: that the two credible failure modes for the switch, either a R cr: r 3 gr:ana,. u?J nct prevent the circuit from performing its intenced fun: tion. A third f ailure mode, speci fically an open ci rcui t, is not censidered 1 credible failure modo from an environmental qualification ctanau, int. Ci": 2 no cr:dible railure mcde, induced by a harsh environment, will p reven t t,c circuit frcm performing its in tended func tion, continued i n ter I; c,s e rn ; i c n is jostifiabic. . t v.i in-the Nov eler 3, 1930 Ic t ter, a fol lowup repor t wi ll be A-submit'.JJ ii Liii n !?6 dny9. ^* Cercl" [ \\ \\ J m Nk \\ ' V R. J...odrigue Mnnager, Nuclem. Operations RJR:HH:jr cs: Director, MIPC (3) Director, IEE (40) M b @n 'f, \\\\N nD\\ m ,(90RE ) 1 c

m. :

A Etferoic t Y t f E 'A $fovtN, T H A ft 600.000 IN THE HEART OF CAtlFORNIA ~ ' ~

a -103 SACRAMENTO.'.tUNICIP AL '.' T "_ ITY CIST"!CT _',' 5:01 $ S treet. Oox 15330. Sacramento California 95313, (916) 452 3211 D.JR o0-562

ovember 3, 1950 w,.1 g-J C<,/,

/~W~'. N', ? .-9 3 G, ' -> w s /8

e. f.

a / ls C.3 5 /r -\\ c_:. $ 5. C2,. l .'.O' Mr. R. H. En ?lhen, Director O! gs '?. G '.5. Region V Offi:2 of :.srection & ' a - Y)., ;3.(.- 'S$ d ' U. S. ':uclear "equintory Co-ission \\Q' d, W, j) 1990 :: orth Califer-i Feulevard Walnut Creek Plaza. Suite 07 Walnu: Creek, CA 9'936 Re: Operating License DPR-54 Decket No. 50-312 Reportable Occurrence 80-45

Dear ':

r. Encelken.

r ;;;;r:cnce wl:n icchnical Specifica icns Section 6. 9. '. 1 ( 1), the fr.cramento nunic;. pal.'L i;ity District is hereby submit ;n; tne : allowing wri: ten con:1rna:1cn of a 24-hour Licensee Even: ?.cpor; initial;y reportea to etr. G.

Zwe :1;; of your of fice on Oc cber ~)i, i)cO. r;;a u c. .. ;.ul.,e:in /y-via,., review it was determined . v i that the limi; esi:enes uci.. ed an air-uperated containment isolation valves t.o uc ;. ..u-c..e carrent environmental qualification criteria.

;. c.. c o a que=c ca ara.anuf actured by lW

C0 2 4

- :.: ;ra n-- -.... ; : rac.c..; qua.; fica to recircula:ing fluid radiation icvai-L c.. s.n.; m. s ; -...o .n qu.:a r.;ca a re.;ca:cd outside the conra:r.:nt. _.s. ...r" S u il;in ;;.

.e function of the switches is to :)rc.

'erater indication at valve position.

The switch will funct.cn ; ri:r to

in; c::pered to the : distien levels associated f l u i d., Calicwin:; a : 0CA.

As a result, the switches with remr t'.- will p r-

Su necesacrv indication ta the operator for some time f a ll,, t n.

.'m accident. Failure of the switch at a later time will r.. ' w, of pas : .,n indicatien only, and actual valve position itL. r i: on,: f ue tud. L.,

.'i n t r i ;:: ' a intent to replace the limit switches n accor ws ci th rhe tine fenme specified in the bulletin.

A detailed

part

'e

uhnitted to your office within 14 days.

S,j er / J ' ~\\ a w 6 l -vow ,V R. J Rodrigic.

tanager, Nuci ar Operations 7tu.:.,.nt, it 3. if.

l.. s l en# A M g.) f Qlli U ~19n {f

Y '. ? ! '.!

OERV'N; 't 'O R i T H A.'i C 0 0.

fN THC s:49T OF tALITORNiA

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