ML19318B209

Electrical Equipment Qualification,NUREG-0588 Review.

ML19318B209
Person / Time
Site:	North Anna
Issue date:	06/20/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19318B208	List: ML19318B207 ML19318B209
References
RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8006250129
Download: ML19318B209 (300)

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'V TABLE OF CONE NTS NUREG-0588' REVIEW NORTH ANNA UNIT.'2 Section TiVd i

Discussion . . . . . . . . . . . . . Point By Point Rea;iense tb 1RIREG-0588 Conclusion

• Enviromr.catal . . . . . . . . . . .Environmen%L Areas Environmental s Eeport 4heet::

HVAC & Radiatica -Z6nd E ps' (Figs (1-6)

Qualification..........Qualificatilin% M Evaluat.iun Sneets l

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The review of electrical equipment qualification contained in this report

) Lis supplied in response to the February 19, 1980 NRC lett - to near term fd operating plant licensee's. That letter required th ; the previous submittals of reports for Class IE electrical equipment qualification be compared

, against the latest version of the draft NUREG-0588. The earlier reports on environment qualification of Class IE. electrical equipment were generated

, in response to IE Bulletin 79-01. These reports were forwarded to the NRC by VEPC0 letters dated September 17 and November 2,1979; and February 25, 1980. -

t This review of environmental qualification of Class IE electrical equipment i

and components.for North Anna Unit 2 was based upon the guidelines outlined for Category II plants as defined by NUREG-0588, " Interim Staff Position on

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Environmental Qualification of Safety Related Electrical Equipment".

NUREG-0588 is in draft form at this time; the version used for this review was issued to operating license applicants by NRC letter on February 5, 1980. In addition to the guidelines listed on pages 5 through 17 and Appeadices A through D of the subject docum nt, discussions between VEPC0 and the NRC staff were considered in this review. Differences between the guidelines of NUREG-0588 and the methods specifically employed in the reevaluation are detailed below. The numbers below correspond to the NUREG-0588 section numbers.

• 1.0 Establishment of the Qualification Parameters for Design Basis Events

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[m 1.1 (1) The time dependent temperature and pressure established for V} the design of the containment struecure are described in FSAR section 6.2.1. These parameters have previously been found acceptable by the NRC staff, and are used for equipment qualification.

The methods used to alculate mass and energy release rates following a loss-of-coolant accident (LOCA) and main steam line break (MSLB) have been accepted by the NRC, for the containment functional design, as noted in the North Anna Safety Evaluation Report NUREG-0053, Section 6.2.1 for a LOCA, and Section 6.2.1 of Supplement. 3 for a MSLB. The mass and energy release rates for both the LOCA and MSLB s were calculated with the LOCTIC computer code using data

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J from the Westinghouse REFLOOD code for the reflood phase of the LOCA, and using data from the Westinghouse FROTH code for the post-reflood phase of the LOCA.

3 LOCTIC is also an equivalent industry code to CONTEMPT-LT and, therefore, deemed acceptable for calculating containment transi .cs. The assumption of partial revaporization, which was not used in the North A'nna MSLB analysis, is now allowed.

Lack of use of this assumption increases the conservatism of the present MSLB analysis.

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/ O t 1.1 The time dependent temperature - pressure criteria for a l (2,3,4) -LOCA is established by methods described in 1.1 (1) above; consequently 1.1 (2,3&4) do not apply for this review.

1.2 Environmental profiles for a MSLB were developed for a (1-4) plant specific model in the FSAR and have been reviewed and accepted by the NRC Staff. The model utilized for the MSLB environment is described in 1.1 (1) above.

l '. 2 (5) The suitability of LOCA equipment qualification as a basis for qualification to MSLB is documented in FSAR Section 3C and the response to comment 7.17, and has been reviewed and accepted by the NRC Staff.

For most equipment, heat transfer calculations showed that the peak surface temperature of the component did not exceed the LOCA qualification temperature. For that equipment for which the peak surface temperature was shown to exceed the LOCA qualification temperature, further investigations were performed to show this equipment maintained its functional capability at the higher temperature calculated for the MSLB. This procedure was found acceptable to the NRC staff 3

as stated in Section 3.10.2 of Supplement No. 8 to the Safety Evaluation Report.

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The peak equipment surface temperatures have been calculated for an MSLB using methods which result in higher temperatures than those methods listed in Appendix B of NUREG-0588. Appendix B, Item 2.b states "A convective heat transfer coefficient should be used when the condensing heat flux is calculated to be less than the convective heat flux." The North Anna 2 equipment temperature transients were calculated by adding the heat flux from condensation and convective heat transfer.

This results in a slight overprediction of heat transfer to the equipment; so it is a conservative assumption.

Additionally, in Appendix B, Item 2.b., a correlation is given for the velocity as a function of the blowdown rate and containment volume. A constant velocity of 30 ft/sec

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was used in the North Anna 2 analysis. For the North Anna 2 i

blowdown rates, the correlation gives a velocity greater i

than 30 ft/sec for a few seconds af ter the rupture. However,

! the velocity continually decreases with time as the blowdown rate decreases and is less than 30 ft/sec after the first

few seconds. Using a constant value of 30 ft/sec is conservative with respect to heat transfer to the equipment.

1.3 The effects of caustic spray were addressed in Section 6.2.3 of the FSAR. Single failure was considered, so that the most severe caustic spray environment was addressed and i is reflected on the equipment / component qualification and e',aluation sheets.

j 1.4 The radiation environment for qualification of equipment and v

components is based on the normally expected radiation environment over the life of the plant (40 year), plus that associated with the most severe design basis accident (DBA).

The radiation dose rates are based upon results obtained from the NUREG-0578, Section 2.1.6b design review. Consideration was given to source strength, source volume, structural shielding arrangements and piping locations.

1.4 (1) The analysis to determine the LOCA radiation environment at North Anna is based on the instantaneous release from the fuel to the atmosphere of 100 percent of the noble gas, 50 percent of the iodines, and 1 percent of the remaining

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fission products. The only non-LOCA accident considered for I radiological equipment qualification is an FISLB. The analysis to determine the FISLB radiation environment is based on instantaneous release from the fuel of 5 percent of the noble gases and 5 percent of the iodines in the fuel cladding l

gap. Additionally, the steam generator activity prior to I

,  ?!SLB was assumed to be that due to a 10 gpm primary-to-secondary leak with I percent failed fuel.

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The-radiation qualification for equipment required to operate for F

j a MSLB is in excess of the the calculated radiation environment V

4 using NUREG-0588 source terms. Using'the NUREG-0588 LOCA source term, the containment centerline 120 day integrated dose for LOCA is calculated to be 1.8 x 107 rads. When added to the 40 year normal operating dose of 3 x 107 rads, the total d se is 4.8 x 107 rads which is figure used in our review for components inside the crane wall. Using LOCA doses for radiation qualification i

for MSLB results in conservative doses for MSLB radiation qualification.

1.4 (2) The analysis for the radiation environment assumed a release uniformly distributed in the containment which is consistent f' 'g with NUREG-0588, Appendix D, Page D-5, for a PWR.

b 1.4 (3) See response to 1.4 (2) above.

4 1.4 (4) The analysi. for the LOCA or MSLB radiation environment does

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not take into account the removal of airborne activity in the containment by the ESF systems or leakage. It does account for radioactivity decay. It also assumes that 50 l percent of the iodine released from the fuel plates-out in a very short time in accordance with Regulatory Guide 1.4.

The present analysis results in higher airborne activities than those calculated by the method of NUREG-0588, Appendix D, and is therefore conservative.

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-1.4 (5) The present LOCA ard MSLB radiation environment assumes 50 V-percent instantaneous plate-out of the iodine released from the core ~in accordance with Regulatory Guide 1.4. This is conservative as stated in NUREG-0588, Page D-6.

1.4 (6) The present LOCA and MSLB radiation environment does calculate I

the dose and dose rate at the center point of the containment, and those values are used for unshielded equipment qualification.

The dose rate for unshielded equipment is evaluated with respect to dose contribution of location dependent sources, such as the sump water.

1.4 (7) Integrated dose calculated for equipment qualification is based D on a gamma source only. All cables used in the North Anna Unit 2 containments except the 300V instrument cable supplied under Purchase Order No. NA-265/1265, and the electrical penetrations including splicing material, are qualified to 2 x 108 rads. When the beta dose was added to the presently calculated gamma dose in accordance with NUREG-0588, the total dose did not exceed 2 x 10s rads, which is the qualification to which all the other cables which are required for accident mitigation, has bee, found acceptable.

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i 1.4 (8) Shielded components were qualified, based on a gamma source

[] in accordance-with NUREG-0588.

1.4. (9) The beta dose to unshielded equipment and components has been evaluated for the 300V instrument cable and electrical penetrations. NRC IE Bulletin 79-01B, Section 4.1-2 provides amplifying instructions to NUREG-0588 in regards to the effects of beta radiation dose to electrical equipment. IE Bulletin 79-01B, Section 4.1-2 states that for "the conservative beta surface dose of 1.4 x los rads reported in Appendix D of NUREG-0588 would be reduced by approximately a factor of ten within 30 mils of the surface electrical cable intulation of unit density. An additional 40 mils insulation ' total of g 70 mils) results in another factor of 10 reduction in dose.

Any structures or other equipment in the vicinity of the equipment of interest would act as shielding to further reduce beta doses. By assuming a conservative unshielded j

beta surface dose of 2.0 x 10s rads and considering the shielding ftctors discussed here, the beta dose to radiation sensitive equipment or component internals would be less than or equal to 10% of the total gamma dose to which an item of equipment has been qualified." Then that equipment, or component may be considered qualified for the total radiation environment (gamma plus beta). Since the 300 V o

. instrument cable and electrical penetrations have been p-

, qualified to a gamma dose of I x 10 8Rads, they can be

-( considered qualified for the total radiation environment (gamma plus beta) if 70 mils of insulation and/or jacketing is present. Review of equipment and componeuts at North Anna 2 indicates that this requirement is satisfied.

1.4 (10) The integrated dose calculated for the North Anna 2 e

containment paint coating is based on a gamma source only.

Addition of the beta dose to the presently calculated gamma dose results in a calculated dose in excess of 1 x 10s rads.

North Anna paint coatings that were used on steel are qualified for 1 x 109 Rads. Paint coatings used on concrete U

were tested to 1 x 10s Rads, and other data for tested coatings comparable to coatings used for containment indicate that good results were obtained are for 1 x 109 Rad dose.

1.4 (11) The present analysis to determine the radiation environment for ECCS components is in accordance with NUREG-0588.

1.4 (12) During the evaluation of NRC IE Bulletins 78-08 and 79-01, we used a radiation " threshold" of 2,500 rads and considered all equipment exposed to less radiation to be exempt from <

specific qualification requirements. This threshold value s.J

L was based on an engineering review of material susceptibility

, to radiation damage.as presented in existing literature. We

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believe this threshold of 2,500 rads is reasonable and i acceptable.

1.4 (13) Jee m ..;nses to 1.4.(7-12) 1.4 (14) A conservative analysis has been used as detailed in responses to 1.4 (1-11) above.

4 1.5 (1) The HELB analysis of equipment located outside containment is addressed in the FSAR; Appendix C,.and comment S7.17.

Although specific environmental conditions and durations are not identified in these documents, we have utilized postulated

\v/ worst case conditions, for purposes of equipment qualification review. Required equipment whose qualification has not been demonstrated to these worst case conditions have been identified.

In some cases specific environmental conditions may be 1

developed to demonstrate the acceptability of qualification to less severe environments.

-1.5 We have identified the equipment required for accident (2) mitigation located in general plant areas and also ventilation systems utilized in these areas as well as 40 year and accident radiation levels. This information is provided on s

the enviromental reports as part of this review.

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q -(3) Equipment located in areas where a loss of the environmental t s_

s support system may expose some equipment to environments that exceed their qualified limits are provided with ambient

., temperature monitors'in these areas which will alert the operator that abnormal conditions exist and permit an assessment of these conditions in order to determine corrective action.

Equipment covered by these ambient temperature monitors are i

indicated on the environmental reports as part of this I

review.

2.0 Qualification Methods 2.1 Selection of Methods i

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2.1 (1) The qualification methods used conform to the requirements t

defined in IEEE Std. 323-1971 except for equipment procured prior to acceptance of IEEE-323 by the Atomic Energy Commission, or equipment qualified under the current daughter standards.

A discussion of the qualification methods used is found in FSAR section 3.11 and the response to NRC Questions referenced therein.

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2.1 (2) Testing is the primary method of qualification. Analysis

/) has been used to verify or amplify test results. For equipment inside~the containment exposed to Main Steam Line Break (MSLB) conditions, special analytical methods were used in

conjunction with type testing. Use of the ten (10) degree C rule was the primary means used to determine post-accident

operability.

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A detailed discussion of analytical techniques and conclusions i

is presented in Appendix 3C of the FSAR, the response to I

comment 7.17, and Section 3.10.2 of Supplement 8 of the S.E.R. (NUREG-0053). .

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2.1 (3) The bases for the time interval required for operability of t

h;t,/ .a component is an analysis of the accident and the function of the component. The resulting operability requirements under harsh conditions are identified on the Qualification 3

1 and Evaluation sheet for the component. Operability and J

failure criteris are discussed under Section 2.2. Margins are discussed under Section 3.0.

i (a) Equipment that must function in a harsh environment resulting from an accident _in order to mitigate the accident will be qualified to demonstrate its operability for the time required I

by test or as described in sections 2.2 and 2.4.

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g V (b&c) Analysis of equipment that need not function in order to mitigate an accident for its affects on plant operation will be handled by response to NUREG-0585 "TMI-2 Lessons Learned Task Force Final Report" when it is implemented by the NRC.

2.1 (4) The criteria used for North Anna Unit 2 environmental qualificttion of equipment or components subject to events other than DBA, is that qualification must be demonstrated by actual tests, analysis, or operating history, or a combination thereof.

2.2 Qualification by test

(] 2.2 (1) Operability requirements are defined in the procurement

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documents. Any failures identified during the environmental qualification effort are reviewed and evaluated relative to their affect on the ability of the component to perform its required function.

2.2 (2) The tests results demonstrated that the equipment can perform its required functions. The subject of margins is addressed in Sectie. . O, paragraphs 1 through 4.

O v 2.2 (3) The qualification methods and documentation concerning test procedures, when not specified in accordance with Section 5.2 of IEEE-323-1971, were judged to be acceptable as they specify the accident-based environmental conditions in which the equipment may be expected to function.

2.2 (4) Separate profiles were develope'd for a LOCA and a MSLB as described in the FSAR, section 15.4 and S7.17.

2.2 (5) The flood level has been addressed as referenced on the equipment / component qualification and evaluation sheets.

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) 2.2 (6) The temperature to which equipment is qualified, when exposed to the simulated accident environments, is verified by temperature measurements consistent with the specified requirements. For example, if. ambient temperature is specified, test reports will be reviewed to ensure that ambient temperature readings were taken during testing to verify the adequacy of the test.

2.2 (7). Qualification documentation will be reviewed to ensure that

- the operability of equipment (Ref. Sect. 2.1.3) has been demonstrated. ' Verification of equipment performance characteristics

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throughout its range of required operability will net necessarily require verification periodically during testing nor will i continuous monitoring of the operability status necessarily be required. For example, when testing is being performed to simulate long term effects on operability, testing and/or continuous monitoring during the test is not required.

1 Operability of the equipment will be verified before and

, after such testing.

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When testing is being performed to verify performance characteristics over a range of environmental conditions, verification of 1

operability at the most extreme conditions.will demonstrate 1

operability for the intermediate conditions.

2.2 -(8) The temperature and pressure conditions at which caustic

, spray was applied during testing of components has been

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reviewed.

2.2 (9) See response to 2.7 (7) 4 1 -

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2.2 (10) Application of expected extremes in power supply voltage i

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range and frequency during testing to extreme environmental conditions was not specified in procurement specifications nor required by IEEE-323-1971.

The expected extremes in power supply voltage and frequency were specified as design parameters for all safety-re'ated equipment. The results of an analysis of the 4KV and 480V power system which was performed indicates that proper voltage levels are maintained.

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In order to further ensure that adequate voltages exist on the emergency 4KV and 480V systems a degraded bus voltage protection system has been installed. This system will ,

4 Ns_ / ensure that the emergency power system voltage does not i

remain degraded below 90% (Ref. VEPC0 letter to NRC, dated 10-29-78).

i The Vital bus system which provides power to safety related instrumentation is powered from a regulated power source designed to maintain a voltage of 118V t 2% and frequency of 60HZi2HZ (Ref. FSAR Sect 8.3.1.2).

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The 125 DC buses are normally fed frcm batteries that are i

maintained by battery chargers. All DC equipment is specified

, to operate over the voltage range encountered dtring normal l

\ and accident conditions.

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\ -2.2- (11) All Class IE electrical equipment is enclosed in NEMA Type 1 J

through 12 enclosures as defined in Publ No. IC4-1958 thereby guarding against the adverse affects of dust.

.(12) Cobalt 60 is considered an acceptable gamma radiation source

, for environmental qualification.

t 2.3 (1) The test sequence selected has been reviewed and when determined to be unjustified has been identified on the qualification sheets, i

(2) Test performed are reviewed to ensure that they simulated

('"'N postulated environments as closely as practicable.

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,. 2.3 (3) The qualification methods and documentation concerning test procedures, when not in accordance with Section 5.2 of IEEE i

323-1971 were considered to be acceptable if it was determined that they specified the required accident environmental

, conditions and equipment operability requirements.

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<~~5g 2.3 (4) Any' deviation from sequential testing will.be addressed and ,

s- evaluated on the applicable' qualification sheets.

. 2 . <4 Any deviation from actual qualification testing .ill be addressed on the applicable qualification sheets.

3.0 Margins (1), (2),_and (3)

For equipment inside the containment, the discussion and conclusion of margins in the qualification program is discussed in Section 3.10.2 of the.S.E.R. Supplement 8.

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s,,jl MSLB conditions are more severe than LOCA for all environmental parameters except for radiation. Radiation qualification is discussed

, in 3;10.3 of Supplement 9 of the S.E.R. This report uses radiation values. computed under the guidelines of NUREG-0578 thus adding to the conservatism of the enveloping parameters.

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All. equipment is qualified'for time periods in excess of that required-to provide equipment's safety function. The guideline that a minimum

-of one hour ~ duration for qualified life be demonstrated was not promulgated at the time this equipment was tested.

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4.0 AGING

'4.0 (1)' Equipment that has known aging mechanisms are addressed on the applicable qualification sheets.

4.0 (2) All Class IE electrical equipment will be aseessed for operability at specified time intervals by systematic application of the plants periodic test program (see VEPCO's Technical Specifications for surveillance requirements of safety equipment). When this program detects any inoperable equipment, the equipment or component will be analyzed. If equipment inope?: ability is determined to be catised by aging, the equipment or component will be reviewed to determine necessary action.

%J Equipment or component operability is defined as that condition which meets the requirements of the manufacturer's technical specification.

The use of the periodic test program, coupled with a detailed 4

analysis of all Class IE inoperable equipment and other sources of information should satisfy the aging requirement j and provide assurance that Class'IE equipment and components will perform when needed.

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~f The other sources of information principally would be derived

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from:

1. Licensee Event Reports filed by other utilities.

2. NRC I&E Circulars and Bulletins.

3. Vendor Specific data reports.

5.0 Qualification Documentation (1) During the review of submitted qualification documentation when it is determined that actual test data was not submitted (i.e. test summaries

-and/or certifcates of conformance only were submitted) actual test i

data will be requested. If such dar: eannot be submitted because it

, is considered proprietary by the manufacturer, an audit of this data will be made. " Testing summaries and/or certificates of conformance will not be considered acceptable on their own merit.

A final determination of the acceptability of qualification documentation

.will consider the requirements of IEEE-323-71.

(2) In-the preparation of the NUREG-0588 response, equipment was classified into three (3) categories:

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1. Actual Test Report, or Audits of test data:

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Reports-supplied detailed information on the test methods.

Direct correlation with the actual plant environment can be made.

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When this form of documentation was used to qualify equipment, a copy of the actual test report, or an audit of records has been arranged to verify the contents.

2. Summary of testing: These documents provide a summary of the actual test data. In many cases, the acceptability of

~ ( the equipment described can be demonstrated.

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4 3. Certificate of Compliance:

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l No-determination of environmental acceptability can be made l on the basis of the certificate. Vendors have been contacted to provide the basis for certifying compliance with the  !

4 technical requirements of the purchaser document. If the basis for compliance is a method as' described in NUREG-0588, we will arrange for an audit of the data used.

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L) CONCLUSION: .

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- As a result of our review for NUREC-0588, we have determined that the components listed on the following qualification sheets

. require further vender. qualifications data:

Sheets- 3, 5, 9, 10, 14, 18, 22, 23, 31, 36, 37, 40, 43, 44, 45, 46, 47, 48, 50, 52, 53, 55, 56, 57, 59, 60, 61.

W-1, W-3, W-5, W-6, W-8, W-11,~W-13, W-14, W-15, W-16, W-17, W-18, W-19, W-20, W-21, W-22, W-23, W-24, W-25, W-28, W-30.

1 As a result of our review for NUREG-0588, we have determined that j the components listed on the following qualification sheets require replacement.or periodic change-out.

Sheets 21, 35, 41, 42, 54.

< W-2, W-7, W-12, W-27.

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ENVIRONMENTAL AREAS DESCRIPTION OF AREA FIGURE

(_./ Auxiliary building elevation 244' 6" Zcne A 1 Auxiliary building elevation 244' 6" Zone B 1 Auxiliary building elevation 244' 6" Zone C. 1 Auxiliary builbing elevation 244' 6" Zone D 1 Auxiliary building elevation 244' 6" Zone E 1 Auxiliary building elevation 259' 6" Zone F 2 Auxiliary building elevation 259' 6" Zone G 2 Auxiliary building elevation 274' 0" Zone H 3 Auxiliary building elevation 274' 0" Zone 1 3 Auxiliary building elevation 274' 0" Zone L 3 Auxiliary building elevation 291' 0" Zone M N/R Auxiliary 'uuilding elevation 274' 0" Zone N 3 Auxiliary Feed Water Pump House N/R Casing Cooling Pump House N/R Intake Structure N/R Main Steam Valve House, below elevation 271' 0" N/R Main Stear Valve House, on or above elevation 271' 0"- N/R Quench Spray Area, below elevation 271' 0" '

N/R A Quench Spray Area, on or above elevation 271' 0" N/R

\") ' Reactor Containment, Inside crane wall N/R Reactor Containment, Outside crane wall N/R Safeguards Area N/R Service building clevation 252' 0" Zone A 6 Service building elevation 252' 0" Zone B 6 Service building elevation 294' 0" Zone C 5 Service building elevation 294' 0" Zone D 5 Service building elevation 294' 0" Zone E 5 Service building elevation 271' 6" Zone F 4 Service building elevation 271' 6" Zone G 4 Service building elevation 271' 6" Zone H 4 Service building elevation 294' 0" Zone J 5 Service building -elevation 252' 0" Zone K 6 Service Water Pump Souse N/R Turbine Building N/R Yard N/R O

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ACCIDENT FUNCTION

1. CONTAINMENT ISOIATION

2. EMERGENCY CORE COOLING / CORE HEAT REMOVAL

3. ENGINEERED SAFETY FEATURE

4. POST ACCIDENT MONITORING

5. DBA (LOCA AND MSLB) MITIGATION 4

6. CONTROL ROOM HABITA1 "'Y

7. HELB MITIGATION 1

8. SUPPLIES POWER TO SAFETY SY5tdMS 4 9. SERVICE BUILDING HVAC SYSTEN i

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EQUIPMENT ENVIRONNENTAL REPORT PIANT: VEPCO, Ntrth Annn 2 NRC REF.: NUREG - 0588 I,0 CATION: INSIDE CONTATNMENT

'l. WING

REFERENCE:

N/R

(./' Normal 40 yr. Dose: 1y 1 n'i o ,a ,-

RADIATION LEVEL:

Accident Dose: 1.8 x 107 pra HVAC CATEGORY: . Seismic Class 1 PLANT ID DESCRIFFION NOTE FUNCTION MOV-2865 B Acc. Tk. 2 Cd. Lg. 2.1 MOV-2865 C Acc. Tk. 3 Cd. Lg. 2,3 SOV- 2460- A Note #1, SOV, Letdown Line Looo 1 1 l

SOV-2460-B Note #1, SOV, Letdown Line Loop 2 1 SOV- SS- 207A RHR Sample Line 1 SOV- SS-207B RHR Sample Line 1 SOV-SS-201B Pressurizer "apor Samole 1 LT-2459 Level Transmitter, Channel 1 2,3,5  !

LT-2460 Level Transmitter, Channel 2 2.3.5 -

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LT-2461 Leuel Transmi tter, Channel 3 2.3,5 I

l PT-2455 Pressure Transmi tter, Channel 1 2.3.5  !

Fr-2456 Pressure Transmitter, Channel 2 2,3,5 PT-2457 Pressure T' ansmi tter, Channel 3 2,3,5 FT-7414 Flow Transmitter, Loop #1 2,5 FT-2415 Flow Transmitter, Loop #1 2,5

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N*rth Anno 2 NRC REF.: NUREG - 0588 LOCATION: INSIDE CONTAINMENT m

N/R

[V ' RING

REFERENCE:

RADIATION LEVEL:

Normal 40 yr. Dose: 1y 10 n / ., a 7

Accident Dose: 1,8 x 10 o ,, u HVAC CATEGORY: . Seismic Class 1 PLANT ID DESCRIPTION NOTE FUNCTION FT-2416 Flow Transmitter. Looo dl ') ;

FT-2424 Flow Transmitter, Loop #2 2,5 FT-2425 Flow Transmitter, Loop #2 2,5 FT-2426 Flow Transmitter, Loop #2 2,5 FT-2434 Flow Transmitter, Loop #3 2,5 FT-2435 Flow Transmitter, Loop #3 2,5 FT-2436 Flow Transmitter, Looo J~, 2,5 S0"- 2200A 507 Letdosen L:ac 1 SCV 22900 SC Lecdo nt L:ne 1 F 3"- 02030 SC7 Let doa1 LI ae i l

I e

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PIANT: VEPCO. N rth Ann, 2 NRC REF.: NUREC - 0538 INSIDE CONTAINMENT OUTSIDE CRANEWALL LOCATION:

g

( l. WING

REFERENCE:

N/R G' Normal 40 yr. Dose:  ?. L x 10'* n, a n 6

Accident Dose: 6.8 x 10 Rads HVAC CATEGORY: -

seismic clan. 1 PLANT ID DESCRIPTION NOTE FUNCTION 2-RS- P- 1 A Recirc. Soray Pumo 3,5 2-RS- P- 1B Recire. Spray Pumo 3,5 SOV- B D- 2001. Steam Cen. Blowdown Trip t'alve 1,7 SOV-BD- 200B Steam Cen. Blowdown 1,7 SOV- BD-200D Steam Cen. Blowdown 1,7 SOV-BD- 200F Steam Cen. Blowdown 1.7 SOV-BD 200G Steam Cen. Blowdown Trio Valve 1,7 SOV- BD- 200H Steam Cen. Blowdown Trio t'alve 1,7 SOV-CC-201 B RCP Thermal Barrier Return Header 1 SOV-CC-205 B Contain. Reefrc. Air 1 SOV-CC-205 C Contain. Recire. Air 1 SOV-CC-205 A Contain. Recire. Ai- 1 SOV-CC-202 F RCP Cooler Return header 1 SOV-CC-202 B RCP Cooler Return Heade- 1 SOV-CC-202 D RCP Cooler Return Header 1

• a Denotes environmental qualification shes.t not required.

For function descriptions see first page of this section.

I NMENTAL REPORT FIANT: VEPCO, North Anna 2 NRC REF.: NUREC - 0588 LOCATION: TNSTDE CONTATNENT OITT9fDF FRANFUATT.

SRAWING REFER N/R 2 ICE:

Normal 40 yr. Dose: 1.L y 10* Rea-RADIATION LEVEL: 6 Accident Dose: 6.8 x 10 Rads HVAC CATEGORY: Sei smic class 1 PLANT ID DESCRIFrION NOTE FUNCTION SOV-DG-200 B PRI DRN Xfer. PP Di schg. 1 SOV-DA-200 B Contain. Sumo PP Di schg. 1 SOV-RM-200 C Rad. Mon. to Reactor Contain. 1 SOV-VG-200 B PRI DRN Xfer. Tk. Vent 1 SOV-SS-204 A Press. Relief Tk. Gas Space 1 S0"-SS-206 A PRI Coolant. Hot Leg Samole 1 SOV-SS-202 A PRI Coolant. Cold Leg Samole 1

_SOV-SS-200 A Pressure. Liould Soace Samole 1 SOV-SS-212 A Steam Gen. Samole 1 1

SOV-SS-2OI A Pressure. Vnoor Soece Carole 1 MOV-HV-200 A Containment Supoly I SOV-CV- 200 Containment vacuum Eject Tnlet 1 SOV-TA-201 A Containment Instrument Ai r 1 HOV-2380 RCP SWHX Dis. 1 I ISOV-2842 Accumulator Test Line Inboard 1

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO. North Anna 2 NRC REF.: NUREG - 0588 l TION: TN9TDE CGJTAINMENT OUTSTDE CRANEWALL l

RAWING

REFERENCE:

N/R Normal 40 yr. Dose: 1_/ v in" o.a.

Accident Dose: 6.8 x 10 Pads HVAC CATEGORY: s.<=mfc cl am e 1 FIANT ID DESCRIFFION NCTTE FUNCTION l

FT-2474 Flew Transmitter. Generator IA Channel III 2.3,5 FT-2475 Flow Transmitter. Generator 1A, Channel IV 2.3.5 FT-2484 Flow T'ansmitter. Generator IB. Channel III 2.3.5 l FT- 248 5 Flow Transmitter. Generator 1B Channel IV  ?.3.5 FT-2494 Flow Transmitter. Generator IC, Channel ITI 2.3.5 FT-2495 Flow T ansmitter. Generator 1C channel IV 2.3.5 LT-RS251A Level Transmitter. Containment Wtr. 4 LT-RS251B Level Transmitter. Containment Wtr. 4 Tyne IA Instrumentation Penetration Assemblies 8 Tyne IB i Control Penetration Asser.blien R Type IC Low Vol t age Pwr , Penetration Assemblies R Tyne IIA low Voltace Pur Panervation Assemblies A Type TIB Low rottace Pur Panervation Aseembi f es A Tyoe IIC

__1pv "otence pur o ne.e-me<nn A c c omh1 4 . - o

{ Tyne IID Low Voltane Pwr . Penetrat 8on Agnemb1'en Q

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT FIANT: VEPCO. North Anna 2 NRC REF.: NUREC - 0588 TION: TNSTDP t'ONTATN"ENT Ofi9TDE CRAMEJATT.

RAWING

REFERENCE:

N/R Normal 40 yr. Dose: 1/ y i n'+ t a -

Accident Dose: 6.8 x 10 Rnd s HVAC CATECORY: Seismic Ctees 1 FIANT ID DESCRIFFION NOTE FUNCTION Ty,e TTE Low Voltage Pur Penetration Assemblies a Tyne ITI Ta ' axial Penetration Assemblies 8 Tyne 17 Thermocounl es Penet ation Assemb1'es A 1.2.3.

N /A Terminat'on Taoe 4.5 N /A Splices - as part of penetrat'on assem51.1es 8 l l

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

V RONMENTAL REPORT PLANT: VEPCO North Anna 2 NRC REF.: NUREC - 0588 mLOCATION: IN3 IDS CONTAI!!! GIT

)

v sRAWING

REFERENCE:

N/R Normal 40 yr. Dose: ~

,. 1nt o-a RADIATION LEVEL: 7 Accident Dose: 1.8 x 10 Rads HVAC CATECORY: Seismic Class 1 PLANT ID DESCRIFIION NOIE FUNCTION HCV-2200-A Regen Ht. Outlet S0V, Loop h1 1 HCV-2200-B 'egen. Ht. Outlet SOV, Loop #2 1 HCV-2200-C Regen. Ht. Outlet SOV, Loop #3 1 FS-BD-203 A Steam Gen. Blowdown

• 7 FS-ED-203 B Steam Gen. Blowdown

• 7 FS-BD-203 C Stean Gen. Blowdown

• 7 LGV-2460 A Loop 1 Letdown Line Cont. VV 1 LCV-2460 B Loop 2 Letdown Line Cont. VV 1 MOV-2865 a Ace Tk. 1 Cd. Lg. 2,3 l I

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0588 TION: _INSIDE CONTAINMENT IN PIPING l

RAWING

REFERENCE:

Normal 40 yr. Dose: N/A RADIATION LEVEL:

Accident Dose: ___N /A HVAC CATECORY: N/A PLANT ID DESCRIFFION NOTE FUNCTION TE-2410 Temperature Wide Range RTD 4 TE-2420 Temperature Wide Range RTD 4 TE-2430 Temperature Wide Range RTD 4 TE-2413 Temperature Wide Range RTD 4 IE-2423 Temperature Wide Range ETD 4 TE-2433 Temperature Wide Range RTD 4 TE-2412B Temperature Narrow Rance RTD 1.3.5

_TE-2412D Ten oerature Narrow Rance RTD 1.1.9 TE-2422B Termerature Narrow Rance RTD 1.1.9 TE-2422D Temerature Narro.rEnrce R M 1 1 9 TE-2432B Temperature Narrow Range RTD 1,3,5 TE-2432D Temperature Narrow Range RTD l

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l EQUIPMENT ENVIRONMENTAL REPORT FIANT: VEPCO, North Anna 2 NRC REF.: NURZG - 0588 AUXILIARY BUILDING ZONE C

\

f. LOCATION:

d RAWING

REFERENCE:

Figure #1 Normal 40 yr. Dose: 3,5 in4 ,. a.

RADIATION LEVEL:

Accident Dose: 5x 106 rsds HVAC CATECORY: nnne,.a,,namne venefinef on PIANT ID DESCRIFFION NorrE FUNCTION SOV-SI 201A Safety Injection Accumulators to Waste Gas Filters

• 1 SOV-SS 203B Sol. VV Res. Ht. Rem. Inlet

• 1 SOV-SS 200B Pressure Liquid Space

• 1 SOV-SI 201B Safety Injection Accumulators to Waste Gas Filters

• 1 l

l l

l I I

• Denotes environmental qualification shaet not required. .

For function descriptions see first pag -)f this section. l l

@ T ENVIFONMENTAL REPORT PLANT: VEPCO, Nnrth Anno 2 NRC REF.: NUREG - 0538 LOCATION: Auxiliary Building Zons C WING

REFERENCE:

Firure #1 L Normal 40 yr. Dose: _L 5 x 10 bh DIATION LEVEL: "

Accident Dose: 5 x 10 P. ads HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION MOV-2289A Ch. PP Disch. to Safety Inj.

• 2,3 MOV-22893 Ch. PP Disch. to Safety Inj. 2,3 SOV-SS 200B Pressure Liquid Space

• 1 l

l 1

-- Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l V RONMENTAL REPORT PIANT: VEPCO North Anna 2 NRC REF.: NUREC - 0588 LOCATION: Af?vTT.T Apv Ri?TT.DTNC 70ME C

)

vdRAWING

REFERENCE:

rienre 41 Normal 40 yr. Dose: 1.5 x 104 rads RADIATION LEVEL:

l Accident Dose: ,e 106 rnS HVAC CATEGORY: . r n ,. ,, ,s . ., a , - , y,,n e < 13 e i n, FIANT ID DESCRIFIION NOIE FUNCTION 30V-BD-200A Steam Cen. Blowdown 1 SOV-CC-200B Cont. Recire. Air Coolers 1 SOV-CC-200C Cont. Recire. Air Coolers 1 SOV-CC-202A R.C.P. Return Header 1 S07-CC-202C R.C.P. Return Header 1 S OV-RM-200A Limit Sw. on TV-RM-200A 1

)

l l

9

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PIANT: VEPCO, Nsrth Annn 2 NRC REF.: NUREG - 0588 LOCATION: Auxiliary Building Zone C RAWING

REFERENCE:

Finire #1 4

[ ] Normal 40 yr. Dose: . 5 x 10 Rads ClDIATION LEVEL: O Accident Dose: 3 x 10 P. ads HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION MCV-2867B Chrg. PP Disch.

• 2,3 MOV-2869A Chrg. FP Disch. to Loops

• 2,3 MOV-2869B Chrg. PP Disch to Loops

• 2,3 SOV-CV-250A Cont. Vac. PP Suction

• 1 S0V-CV-2503 Cont. Vac. PP Suction

• 1 l

l L

- Denotes environmental qualification sheet not required.

For function descriptions se first page of this section.

T ENVIRONMENTAL REPORT FLANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0558 m LOCATION: Auxiliary Buildine Zone C RAWING

REFERENCE:

Figure #1 4 Normal 40 yr. Dose: J.D X 8v N3 RADIATION LEVEL: o Accident Dose: 5 x 10 Pads  !

HVAC CATEGORY: Nonredundant Ventilation FLANT ID DESCRIFIION NOTE FUNCTION MOV-2836 HH Cold Leg PA Cire. Icol

• 2,3 FT-2940 Hot Leg SI Dp. Xmtr

• 2,3 FT-2943 Boron Inj. Tk. Flow Xmtr

• 2,3 l

l I

l l i

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l l

7-

Q T ENVIRONMENTAL REPORT PIANT: VEPCO, N rth Anno 2 NRC REF.: NUREG - 0588 LOCATION: Auxiliary Building Zone C WING

REFERENCE:

Figure #1 L Normal 40 yr. Dose: 3.5 x 10 Rads DIATION LEVEL: 6 Accident Dose: 5 x 10 hds HVAC CATEGORY: Nonredundant Ventilation PLANT ID DESCRIFFION NOTE FUNCTION SCV-DG 200A Pri. Drn. Transf. PP Disch.

• 1 1

SOV FR2 GOB u

l l

f l 1

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVTRONMENTAL REPORT PLANT

• VEPCO, Nerth Annq 2 C REF.* NUREG - 0588 I,0 CATION: Auxiliary Building Zone C

, " WING

REFERENCE:

Figure #1 ,

( ) Normal 40 yr. Dose, o c; _ y in :na ,.

's ;DIATION LEVEL:

6 Accident Dose: 5 x 10 Pads HVAC CATEGORY: Nonredundant Ventilation ,

PLANT ID DESCRIPTION NOTE FUNCTION From Ref. Water Stg. Tank

• 2,3 MOV-2115B MOV-2115D From Ref. Water Stg. Tank

• 2,3 MOV-2863A To Charg PP Suet.

• 2,3 MOV-2863B To Charg. PP Suct.

• 2,3 MOV-2381 Seal. Water Hx Inlet

• 2,3 MOV-2867A Charg. PP Disch.

• 2,3 MOV-2867C MOV-1867D Boron Inj. Tk. 0

• 2,3 MOV-2867D Boron Inj. Tk. Outlet

• 2,3 l

l i

Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT PLANT: VEPCO, Ntrth Ann 9 2 NRC REF.: NUREC - 0588 LOCATION: Auxiliary Buildine Zone C

/'^l' RING

REFERENCE:

Firure 41 /.

( ) Normal 40 yr. Dose: 3.5 x 10 Rads

\JDIATION LEVEL: o Accident Dose: 5 x 10 Pads HVAC CATEGORY: Nonredundant Ventilation PLANT ID DESCRIFFION NOTE FUNCTION SC'/-DA 200A RC Sump PP Disch.

• 1 SOV-SS 202B Prin. Coolant Cold Leg

• 1 SOV-SS 212B St. Gen. Surface Sample

• 1 SOV-VG 200A iri. Drn. Transfer Tk. Vent

• 1 l

l l

L

- Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

TAL REPORT PLANT: VEPCO. Nrrth Anna 2 NRC REF.: NUREG - 0588 LOCATION: Auxiliart Building C Fi w e #1 ,

Normal 40 yr. Dose:

(/'1*NING

)

REFERENCE:

%;DIATION LEVEL:

34y in '

6 n+

Accident Dose: 5 x 10 Rads HVAC CATEGORY:  !!onredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION SOV-CC 200A Cont. Recire. Air Coolers 1 SOV-CC 201A R.C.P. Them. Barrier 1 SOV-SI 200A Nitrogen Supply Lina SOV VV 1 SOV-SI 200B  !!itrogen Supply Line SOV VV 1 l

l L

-' Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

TAL REPORT PLANT: VEPCO, Nerth Anno 2 NRC REF.: NUREC - 0588 LOCATION: Auxiliary Buildinrr Zone C WING

REFERENCE:

Ficure #1 4 Normal 40 vr. Dose: 3.5 x 10 Itads DIATION LEVEL: o Accident Dose: 5 x 10 Rads HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION SOV-CV 250C Cont. Vac. PP Suction 1 SOV-SS 204B Press. Relief Tank Gas Sp. 1 SOV-SS 206B Prim. Coolant Hot Leg

• 1 SOV-FJ4 200A Rad. Mon. to Reactor Cont. Sol V

• 1 c.

N l

l L

l l

l '* Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PIANT; VEPCO, Nrrth Anni 2 NRC REF.: NUREG - 0580 LOCATION: Auxiliary Building Zono C WING

REFERENCE:

Firmre #1 4 Normal 40 yr. Dose: 3.5 x 10 nads DIATION LEVEL: o Accident Dose: 5 x 10 Rads HVAC CATECORY: I nredundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION SOV-CV 250B Cont. Vac. PP Suct.

• 1 l

SOV-CV 25CD Cont. Vac. PP Suct

• 1 SOV-LM 201A Cont. Closed Press. Tap

• 1 SOV-LM 201B Cont. Closed Press. Tap

• 1 SOV-LM 201C Cont. Clos?d Press. Tap

• 1 SOV-LM 201D Cont. Closed Press. Tap

• 1 l

I l

l L

Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT l PLANT: VEPCO, NTrth Annn 2_ NRC REF.: NUREG - 0588 I l

LOCATION: Auxiliary Building Zone C tiING

REFERENCE:

Figure e1 g Normal 40 yr. Dose: L 5 x 10 han DIATION LEVEL: o Accident Dose: 5 x 10 Rads HVAC CATEGORY: Nenredundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION f

• i SOV-CC 202A R.C.P Return Header 1 1

SOV-CC 202C R.C.P. Return Header 1 SOV -2884A Boron Ins. Tk. to Batch Tk. 2,3 SCV-2804B Boron Ins. Tk. to Batch Tk. 2,3 l l

SOV -2884C Boron Inc. Tk. to Batch Tk. 2,3 l

l l _

'w Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT FIANT: VEPCO, Nerth Ann 1 2 NRC REF.; NUREG - 0588 LOCATION: Auxiliary Building Zone C Figure #1 4

([')' RING

REFERENCE:

40 yr. Dose:

Normal 3 5 x 10 ftads

\ JDIATION LEVEL: o Accident Dose: 5 x 10 Rads HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION SOV-CC 203A Res. Ht. Renoval Ht. Ex.

• 1 SOV-CC 203B Pec. Ht. Removal Ht. Ex.

• 1 l

l I

I L

i

-- Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT PIANT: VEPCO, N rth Annq 2 NRC REF.: NUREG - 0538 LOCATION: Auxiliary Building Zone C WING

REFERENCE:

Figure s1 j Normal 40 yr. Dose: ,6y in om DIATION LEVEL: o Accident Dose: 5 x 10 Rads HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION SOV-BD 2000 Steam Gen. Blowdown

• 1 SOV-D'.

. 200E Steam Gen. Blowdown

• 1 SOV-CC 204A-1 Lim Sw. on TV - CC 204A Train A

• 1 Lim. Sv. on TV - CC 204A S0V-CC 204A-2 Train B

• 1 SO'4-CC 204B-1 Lim. Sw. on TV - CC 204B

• 1 Train A SOV-CC 2049-2 Lim. Sw. on TV - CC204B

• 1 Train B SOV-CC 204C-1 Lim Sw. on TV - CC 204C

• 1 Train A S0%CC 204C-2 Lim Sw. on TV - CC 204C

• 1 Train B l

l L

-- Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, Nerth Anno 2 NRC REF.: NUREG - 0583 "D"

LOCATION: Auxiliarr Buildinrr Zone aren surrounMrc nrea

[n '1 MING

REFERENCE:

Ficure #1 )

L/ Normal 40 yr. Dose: 1. 6 x 10 Rads RADIATION LEVEL: 6 '

Accident Dose: 1 x 10 Rads HVAC CATEGORY: Redundant Ventilation (Suprily)

PLANT ID DESCRIPTION NOTE FUNCTION MOV-SV 213A Fuel Pit Coolers 2,3

• 9 ,

vnv_cv 91on v.. a 94+ c e ,,, , ,. e S/nV _ c'U 'no* FF W 4n U4

• 7,3 Mov_sv 9non rc uv 4 - m.

• 7,7 MOV-SW 113A Fuel Pit Coolers 2,3 MOV SV 1119 %1 P4+ conlo-e

• 2,3 I

I e

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

f EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N*rth Ann, 1 NRC REF.: NUREG - 0588 LOCATION: Auxiliary Buildine Zone E

,, l l

( ); WING

REFERENCE:

Figuro J1 Normal 40 yr. Dose: 3.5 x 10' Rnds j RADIATION LEVEL: 6 Accident Dose: 5 x 10 Rads HVAC CATEGOPT: Redundant Ventilation (Exhaust)

PLANT ID DESCRIPTION NJIE FUNCTION

• 2,3 MOV 91"O Tn 9 c. ,1 U+ _ . Te4_ 741+c*e unv_,17, en pp +n %, v+,._ py_

• 7.9 _

l I

9

• Denotes environmeatal cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PIANT; VEPCO, N?rth Anna 2 NRC REF.: NUREG - 0588 LOCATION: r - --4 7 4 -. n,-4, a in- m _c r i l

l WING

REFERENCE:

Fir ' Ire e 2 Normal 40 yr. Dose: c.25 - in3 rea - j DIATION LEVEL: ,

Accident Dose: 1 -- i n b Ng-HVAC CATEGORY:  !:9 1on' Te . 'b 4'orsd (7e' et. 7 m/oi PLANT ID DESCRIPTION NOTE FUNCTION 2- F 'l-20 210.-2S Cable Mr.nl - South n g i

l l

L

'* Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO Nirth Anno 2 NRC REF.: NUREG - 0583 LOCATION: !r.edlicre 3u'Idir~ "or.o P WING

REFERENCE:

Firure #2 Normal 40 yr. Dose: 4. o c -, , n; m, a -

DIATION LEVEL:

Accident Dose: 1 -- w6 a HVAC CATEGORY: /_9dert To ,. 'ori'ored (%t r+ . 10/ Ori PIANT ID DESCRIPTION NOTE FUNCTION 2-IF-: E-19 2Ill-2:' Cable Tiumel - I~ orth e e SG7-U3200A CC:7 Cpen Precs. Tcp

• y 3C7-El 200D CC:7 Cpen Prec::, Tcp

• 1 i

C77-E:2000 CO:7 Oper. Prec::. Tcp n 1 i

l l

l l

L 7 Denotes environmental qualification sheet not required.

For function descriptions see first page of this section, l

' TAL REPORT PIANT: VEPCO N*rth Anno 2 NRC REF.: NUREC - 0583 LOCATION:  ?>rdli-- }tOd5n- Tone F WING

REFERENCE:

Figure /?2 Normal 40 yr. Dose: 5.05 - W Tric DIATION LEVEL:

Accident Dose: 1 x M *e4 HVAC CATEGORY: !zhient Tcnn. :~on!.tored (Set T'. 10/.0H PLANT ID DESCRIPTION NOTE FUNCTION 577-E! 200D C0"T Cpen Trecc. Tap <

1 CUI-E: 200:: 00:C Open Frecc. Tap n 1 CUI-L': 200T CCII Open ?recc. Tap n 1 SCl-L': 2003 00:"2 Open ?recc. Ta7

• 1

'.77-E. 200'I C0!"? Cpen 7:ccc. Tep

• 1 PT-L': 200A Eeactor Cont. Precc. U 4

FT-E! 2003 Ecactor Cont. Frecc.

• 4 PT-E' 200C Ecactor Cont. Frecc. e 4 FT-E: 2003 Reactor Cont. Pres:;. U 4

l l

L l

f 's Denotes environmental qualification sheet not required.

l For function descriptions see first page of this section.

1

TAL REPORT PLANT VEPCO, N?rth Annq 2 NRC REF.: NUREG - 0588 LOCATION: t-dlia rr ~Mi1M r~ Pore F

/fEING

REFERENCE:

Figure F2 Normal 40 yr. Dose: p .; -- W re d-( ~!DIATION

}

LEVEL:

Accident Dose: 1 c 10'- 7.nce HVAC CATEGORY: '91ont '"em.  :'oritored ("et Ft. '.0/.UM PLANT ID DESCRIPTION NOTE FUNCTION 2-CP-: I'-22 2J1-23 Cable Tur.r.el - South E l

l L l l

-- Denotes environmental qualification sheet not required. 1

, For function descriptions see first page of this section.

l

EQUIPMENT ENVIRONMENTAL REPORT PIANT: VEPCO, Nwrth Ann, 2 NRC REF.: NUREG - 0553 LOCATION: .b>Mlia.r* .lht4 1dir ~oro F WING

REFERENCE:

Figure #2 Normal 40 yr' Dose: C.v - 10s *:r d ,

DIATION L" VEL:

,3 Accident Dose: _1 10 *

~5 HVAC CATEGORY: '+ 1ent Te . "onitoral

. (ne t Pt. 10/ UM ._

PLANT ID DESCRIPTION NOTE FUNCTION LIT-F3 2511. 00:"2 Unit for LT-P3 251A 4 LIT I'S 251E CO::T Unit for LT-TS 2513

• 4 2 "'i-: .U-21 2J1-2'I Cc.ble Tur.nel " orth 0 E 1

l l

l 1

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l l

EQUIPMENT ENVIRONMENTAL REPORT PIANT; VEPCO, Nerth Ann, 2 NRC REF.: NUREC - 0538 LOCATION: * * : -4 ' ' e -- ' 4 7 A 4- lone F DRAWING

REFERENCE:

Figure #2

[' Normal 40 yr. Dose: 4.25 -- 10> rn&

\- )JJIATION LEVEL:

Accident Dose: 1 - in 6 h_ A -

HVAC CATEGORY: l ent Tw r,.

"onitored (Sat 7t.10/ 07)

PIANT ID DESCRIPTION NOTE FUNCTION T;ge II.

Instrrr.cntaticn Paletration !.ccerbliec

• C Ripe IB Control Penetration !.sconbliec

• C

?;no Id Iou Yolttce Pouer Penetration 1.cceiliec

• S 2/po _.u...s Iou Voltngo Tovar Fenetration 1.ccei liec

• 8 R ce II3 Ecu Voltage Forer Penetration !; cc:ibliec

• 5

?/po IIC Lou Voltage Tovar ?cnetration 1.caciliec

• C

{ bpeIID

.~w Volta:ic Power Penetration 1.c::cSlica

• C R7e IE Iou Volte c Pouer Penotration .bcci lies

• C r,. m. e T T Triaxic1 Penetration Itacedlies

• C

'CTe H Lermcouplec Penetration 1.c::c%11oc

• i C

l'/1. Splicec-as part of penetration acce.ilies -

C l

l L l

_ Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l l

l l

l

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, Nirth Anne 2 NRC REF.: NUREG - 0588 LOCATION: Auxiliary Building Zone G WING

REFERENCE:

Figure #2 _

Normal 40 yr. Dose: 5.25 x 10' %

DIATION LEVEL: o Accident Dose: 1 x 10 Rads HVAC CATEGORY: Ambient Temp. Monitors (Set Pt. 104 F)

PLANT ID DESCRIPTION NOTE FUNCTION SOV-IA-202A SOV for 2-I A-CO-l 1 SOV-I A-202B SOV for 2-IA-C-01 1 SOV-I A-201 A SOV for 2-I A-C-01 1 S0V-I A-201 B SOV for 2-I A-C-01 1 i

l l

1

'u Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

1 EQUIPMENT ENVIRONMENTAL REPORT PLANT; VEPCO, Nerth Ann,2 NRC REF.: NUREG - 0588 LOCATION: AUXILTARY BUTLDTNG ZONE H O" e 4 -, , .m ., e

(,)VING

REFERENCE:

Normal 40'yr. Dose: 5.25 x 103 rads RADIATION LEVEL:

Accident Dose: 1 x 10 6 rads HVAC CATEGORY: - Nonredundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION H2A-HC-200 '

Hydrogen Analyzer 4

\ l l

l i Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

Q T ENVIRONMENTAL REPORT PLANT: VEPCO, Nnrth Anno 2 NRC REF.: NUREC - 0588 LOCATION: a,v414n f an41aieg 7ene T WING

REFERENCE:

Figure #3 E

Normal 40 yr. Dose: 3.5 x 10 war Accident Dose: 1 x 10 Rade HVAC CATEGORY: Nenredundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION MOV-2350 From Boric Acid Filter 2,3 l

l L

'* Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l

T ENVIRONMENTAL REPORT PLANT: VEPCO, N3rth Anno 2 NRC REF.: NUREG - 0588 LOCATION: a,,w 14., j n33 4, a4 n g 2nne ' T.

WING

REFERENCE:

Figure #3 Normal 40 yr. Dose: 3.5 x 10 Rads DIATION LEVEL:

6 Accident Dose: 1 x 10 Rads HVAC CATEGORY: Rean~1nnt Ventilation (Exhaust)

PL\NT ID DESCRIPTION NOTE FUNCTION

• 2,3 MOV-21150 Vol. Contr1. Tk, Outlet MOV-2115E Vol. Contr1. Tk. Outlet 2,3 l

l 1

-

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l l

l

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N rth Anno 2 NRC REF.: NUREC - 0588 LOCATION: a.,y4 ,4 ,,-,, 3 ,4 ,a:. 7 7- u v RAWING

REFERENCE:

li/R j Normal 40 yr. Dose: p oc y in' m ar j RADIATION LEVEL:

Accident Dose: 4 -, sn 6 og_  !

HVAC CATEGORY: ~~ Redundant Ventilation (Exhaust & Fresh Air Louvers)

/ l PLANT ID DESCRIFIION NCTTE FUNCTION

• 10 2-HV-F-40A(NOTE 11 Safeguards Area Exh. Fan A 2-HV-F-40B (NOTE 1) Safeguards Area Exh. Fan B 10 i

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l NOTE 1 - Ambient Temp. Monitors

V TAL REPORT PLANT: VEPCO, Nxrth Anne 2 NRC REF.: NUREC - 0588 LOCATION: Auriliary Buildinc Zone N

/' (IEUTO#3 -

f )iWING

REFERENCE:

Normal 40 yr. Dose: c . ? c; y 10> Reds Accident Dose: 1 y 10 6Rads HVAC CATEGORY: ,g g . . ,,, v,,; , n, n (Set Pt. = 104 F)

PLANT ID DESCRIPTION NOTE FUNCTION

• 8

? FF-SR-01 480V Emer. SWGR 2H-1

• 8

? F7 99-01 480V Emer. SVGR 2J-1 _

• 8 9 FE nT n1 280V Ener. XFMR 2H-1

• 8

?-EE-ST-02 480V, Emer. IFMR 2J-1 l

l 1

- Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

l l

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO. N tth Anno 2 NRC REF.: NUREG - 0588 LOCATION: AUXTLTARY FEEDWATFR PUMP HOURE

' MING

REFERENCE:

N/R q ,/ Normal 40 yr. Dose: 260

• ads RADIATION LEVEL:

Accideint Dose: > l rad HVAC CATEGORY: Redundant Ventilation and Ambient Temo. Monitors (Set Pr. = 1040F PLANT ID DESCRIPTION NOTE FUNCTION Aux. Steam Gen. Fd.

• 7 MOV- W- 200 A PP Di sch . VV Aux. Steam Cen. Fd.

• MOV-W-200B PP Di sch. VV 7 Aux. Steam Gen. Fd.

• 7 MOV-W-200C PP Di sch. VV

• 7 2-W- P- 2 Pumo Motor Stm. Gen. Aux. Dp.

Mot. A

• 7 2- W- P- 03 A Stm. Gen. Aux. Dp.

• 7 2- W- P- 03B Mot. B Feedwater Control from Aux. Feed Heater B to Stm.

III., W- 200A Gen. lA 7 Feedwater Control from Aux. Feed Heater B to Stm.

Gen. 1B

• 7 HY-W-2003 Feedvater Control from Aux. Feed Heater B to Stm.

• 7 HY- W-200C Gen. ic Feedwater Control from Aux. Feed Heater B to Stm.

Gen. 1D

• 7 HY rW-200D I

l d

• Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

i EQUIPMENT ENVIRONMENTAL REPORT FIANT: VEPCO, Ntrth Anno 2 NRC REF.: NUREG - 0588 LOCATION: CASEING COOLING PUMP HOUSE N/R WWING

REFERENCE:

Normal 40 yr. Dose: 260 rads RADIATION LEtTL:

Accident Dose: _44 rads HVAC CATEGORY: Redundant Ventilation (Exhaust)

PLANT ID DESCRIPTION NOTE FUNCTION 2-R S- P- 3 A Casine Clg. RecIre. Sorav Pumn

• 3,5 2-RS-P-1B Casing Cig. Rectre. Soray Pumo

• 3,5 i

l l

l l

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT FIANT: VEPCO, Nsrth Anno 2 NRC REF.- NUREG - 0588 LOCATION: FUEL OIL PUMP HOUSE

'*VING

REFERENCE:

N/R

\v' Normal 40 yr. Dose: 260 rada RADIATION LEVEL:

Accident Dose: >1 red HVAC CATEGORY: - Temperature Element PLANT ID DESCRIMION NOTE FUNCTION 2-EG- P- 2HA Emergency Gen. - 2H Fuel Oil Pumo

• 8 2- EG- P- 2MB Emergency Gen. - 2H Fuel Oil Pump

• 8 2- EG- P- 2JB Emergency Gen. - 2J Fuel Oil Pumo

• 8 2- EU- P-JA Emergency Gen. - 2J Fuel Oil Pump

• 8 l

l 4

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

Q T ENVIRONMENTAL REPORT PIANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0588 OCATION: H9 Recombiner RAWING

REFERENCE:

N/R Normal 40 yr. Dose: 1 x 10 Rad Accident Dose: 1 x 10 Rad HVAC CATEGORY: Redundant Ventilation (Future)

PLANT ID DESCRIFIION NOTE FUNCTION 2-HC-HC-1 Hydrogen Recombiner

• 3,5 2-HC-HC-1 Hydrogen Recombiner

• 3,5_ j I

.~

l A

l I

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

I . . _ _. _. . - .-. __

EQt/IPMENT ENVIRONMENTAL REPORT PIANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0588 TION: Intche Stricture i

RAWING

REFERENCE:

II/E I Normal 40 yr. Dose: 260 i ncis  !

RADIATION LEVEL:

Accident Dose: T e c t'.ar 1 trd HVAC CATEGORY: Y a4 - A --+ Va-t' k+ inr "- '-a ct T '. . Imarers PIANT ID DESCRIFIION NOTE FUNCTION 2 -T-T-7-04 Aux. Sc:7. I ater Frp " 2,3,5 1 - 317 1 !. Traveling ~.Itr Screens-Service l'ater

• 2,3,5 1-3'.? C-1B Traveling ~ltr Screens-Cervice 1:ater

• 2,3,5 2-C.:-3-1A Traveling 'ltr Screens-Ge:vice 1 ater

• 2,3,5 2-SWS-1B Travoli .c '.!tr Screens 3crvice 1:ater-

• 2,3,5 s

l I

• Denotes environmental qualification sneet not required.

For function descriptions see first psge of this section.

l L

V NMENTAL REPORT FLANT: VEPCO, North Anna 2 NRC REF.: NUREC - 05T28 LOCATION: Mein ern,- vn1rn h41ain, h un el _ 971' C JRAWING

REFERENCE:

N/,

Normal 40 yr. Dose: 1.4 x 10#

RADIATION LEVEL: 4 Accident Dose: 1.5 x 10 Rads HVAC CATECORY: Non-redundant PLANT ID DESCRIPTION NOTE FUNCTION SOV-MS211A Aux. FD PP Turb. Drive

• 2,5,7 EOV-MS211B Aux. FD PP Turb. Drive

• 2,5,7 SOV-MS213A-1 SOL VV for TV-M5113A

• 1 SOV-MS213A-2 SOL W for TV-MS113A

• 1 SOV-MS213B-1 SOL VV for TV-MS113B

• 1 SOV-MS213B-2 FOL VV for TV-Ms113B + 1 S0V-MS213C-1 SOL W for TV-MS113C *

• SOV-MS213C-2 SOL W for TV-MS113C

• 1 S0V-SV202-1 Air Removal SYS SOL W

• 1 SOV-SV203 Air Renoval SYS e0L VV ^ $

l I

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

VIRNTAL REPORT PIANT: VEPCO, North Anna 2 NRC REF.: NUREC - 0588 r LOCATION: SERVICE BUILDING ZONE A b)RAWING

REFERENCE:

Figure #6 Normal 40 yr. Dose: 200 nads RADIATION LEVEL:

Accident Dose: 160 Rads HVAC CATEGORY: Redundant AC, F.edundant Energency Ventilation Equipnent Located in Service building vill not cee Ghanging Environnent Due to accident PLANT ID DESCRIPTION NOTE FUNCTION 2,3,5 2-EP-CB-28A Aux. Relay Cabinet A

• 7,8 2,3,5 2-EP-CB28B Aux. Relay Cabinet B

• 7,8 2-EP-CE-12A D.C. Cabinet 2-1

• 8 2-EP-CB-12B D.C. Cabinet 2-2

• 8 2-EP-CB-12C D.C. Cabinet 2-3

• 8 2-EP-CB-12D D.C. Cabinet 2-4

• 8 1

2-VB-I-01 Vital Bus Inverter 2-1

• 8 2-VB-I-02 Vitai Bus Inverter 2-2 * '8 2-VB-I-03 Vital Bus Inverter 2-3

• 8 2-VB-I-04 Vital Bus Inverter 2-4

• 8 2-EP-MC-10 MCC 2H1-1

• 8 2-EP-MC-41 MCC 2H1-4

• 8 2-EP-MC-11 MCC 2J1-1

• 8 l l

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPVINT ENVIRONMENTAL REPORT PLANT: VEPCO, Nrrth Anno 2 NRC REF.: NUREC - 0588 LOCATION: SERVICE BUILDING ZONE A l

/ ~ 'iWING

REFERENCE:

Figure #6

( ,) Normal 40 yr. Dose: 260 rnan i RADIATION LEVEL:

Accident Dose: 160 rnan HVAC CATEGORY: Redundant VAC. Redundant Emercency Ventilation PLANT ID DESCRIPTION NOTE FUNCTION i

l FS-HV2213A Switch for Heaters

• 9 1 i

FS-HV2213B Switch for Heaters

• 9 l 4

l FS-HV2213C Switch for Heaters

• 9 J

2-HV- AC-06 Emergency Swgr. Rm. l./C

• 9 2-H V- AC- 07 Emergency Swgr. Rm. A/C

• 9 2-HV-F-42 Emergency Swgr. Ventilation

• 9 SOV-HV2200A Valve for 2-HV-P-22A

• 9 SOV-HV2200B Valve for 2-HV-P-22B

• 9 SOV-HV2200C Valve for 2-HV-P-22C

• 9 2- DB- P- 10A Chiller Room Sump Pump

• 9 2-DB- P- 103 Chiller Room Sump Pump

• 9 FS-HV2213A Wtr. Chiller Flow Switch

• 9 FS-HV2213B Utr. Chiller Flow Switch

• 9 FS-HV2213C Wtr. Chiller Flow Switch

• 9 S-HV-2214A Wtr. Chiller Flow Switch

• 9 u Denotes enviror. mental qualification sheet not recuired.

For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT PIANT: VEPCO, Nnrth Anno 2 NRC REF.; NUREC - 0588 LOCATION: SERVICE BUTIDING 70NE A WING

REFERENCE:

Figure #6 Normal 40 yr. Dose: _

260 raam DIATION LEVEL:

Accident Dose: 160 rada HVAC CATECORY: Redundant AC. Redundant Emercenev Ventilation Eouinment Located in Service Building will not See Changing Environment Due to Accident PLANT ID DESCRIFFION NOTE FUNCTION 2-EE-SW-01 4K Swgr. Bus 2H

• A 2-EI-CB-06A Aux. Shutdown Panel

• 2.3.4,5 l

2-EI-CB-06B Aux. Shutdown Panel

• 2.1.4.s 2-EI-CB-23A Process Rack

• 1,3,4,5 2-EI-CB-23B Process Rack

• 1,3,4,5 2-EI-CB-23C Process Rack

• 1,3,4,5 2-EI-CB-23D Process Rack

• 1,3,4,5 2-BY-C-02 Battery Charger

• a l

2-BY-C-03 Battery Charger

• g l 2-BY-C-04 Battery Charger

• A

• 8 2-BY-C-05 Battery Charger

• 8 2-BY-C-06 Battery Charger

• 8 2-BY-C-07 Battery Charger I

[ 'N

\ /

'T Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N*rth Anne 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDING ZONE A g" FRING

REFERENCE:

Figure #6

( ) Normal 40 yr. Dose: 260 rads N.JDIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Redundant AC, Redundant Emergency Ventilation Ecuipment Located in Service building witt not see unanging t.nvironment vue to accioenc PLANT ID DESCRIPTION NOTE FUNCTION SOV-HV2300A Bottled Air System

• 6 SOV-HV2300B Bottled Air System

• 6 SOV-H V23000 Bottled Air System

• 6 SOV-HV2300D Bottled Air System

• 6 SOV-HV2306A Pottled Air System

• 6 SOV-HV- 2 306B Bottled Air System

• 6

, 2-E T-CB ,4 7A Solid State Protection Cabinet

• 1,3,5 2-EI-CB-47B Solid State Protection Cabinet

• 1,3,5 2-EI-CB-47C Solid State Protection Cabinet

• 1,3,5 2-EI-CB-47D Solid State Protection Cabinet

• 1,3,5 2-EI-CB-47E Solid State Protection Cabinet

• 1,3,5 2- EI-CB-47F Solid State Protection Cabinet

• 1,3,5 2- EI-CB- 51 Process Rack 1 (Prot. Set 1)

• 1,3,5 2- EI-CB- 52 Process Rack 2 (Prot. Set 2)

• 1,3,5 L

EI-CB-53 Process Rack 3 (Prot. Set 3)

• 1,3,5

- Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N'rth Anno 2 NRC REF.; NUREC - 0588 LOCATION: __ SERVICE BUILDING ZONE A WING

REFERENCE:

Firure it6 Normal 40 yr. Dose: 260 rads DIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Redundant AC, Redundant Emergency Ventilation PLANT ID DESCRIPTION NOTE FUNCTION I

SOV-HV215A-1 Flush Vv Service Bldg. Strainer

• I SOV Hv?15A_p Flush Vv Service Bldg. Strainer

• 1 30V-HV215B-1 Flush Vv Service 31dg. Strainer

• 1 30V-HV215B-2 Flush Vv Service Ridg. Strainer

• 1 FS-HV-2214B Wtr. Chiller Flow Switch

• 9 FS-HV-2214C Wtr. Chiller Flow Switch

• 9 2- EE- SS-01 480V SS Bus 2H

• 8 2- EE- S S- 02 480V SS Bus 2J

• 8 2-EI-CB-54 Process Rack 4 (Prot. Set 4)

• 1.3,5 l

l l

1

- Denotes environmental qualification sheet not required, i

l For function descriptions see first page of this section.

t l

l

EQUIPMENT ENVIRONNENTAL REPORT PLANT: VE PCL , N?rth Anne 2 NRC REF.: NUREC - 0588 LOCATION: AUXILTARY BUILDING ZONE B p ; WING

REFERENCE:

Figure #1 i

\- / Normal 40 yr. Dose: 3.5 x 10" rads RADIATION LEVEL:

Accident Dose: 5 x 106 rads HVAC CATECORY: . Redundant Ventilation (Exhaust)

PLANT ID DESCRIPTION NOTE FUNCTION i

l MOV- 2267A Charg. PP 1A Suct. 2.3 MOV-2267B Ch a rg. PP. IA Suct. 2.3 _

MOV-2269A Charg. PP IB Suet. 2,3 Mov-2269 B Charg. PP IB Suct. 2.3 MOV-2270A Charg. PP IC Suct. 2.3 MOV-2270B Charg. PP IC Suct. 2.3 CH PP Dis. to Seal.

MOV-227 5A Wtr. Tank 2.3 CH PP Di s . to Seal.

MOV-2275B Wt r. Tank 2,3 CH PP Di s. to Seal.

MOV- 22 7 ;C Utr. Tank 2.3 MOV- 2286A Charg. PP Disch. 2.3.

MOV-2286B Charg. PP Di sch. 2.3 MOV-2286C Charg. PP Disch. 2.0 CH PP Di sch .

MOV-2287A to Loop Fill 2.3 CH PP Disch.

MOV-2287B to Looo Fill 2.3 CH PP Disch.

4NOV-2287C to Loon Fill

• Denotes environmental qualification sheet not required.

2,3 For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, Ntrth Anna 2 NRC REF.: NUREG - 0588 LOCATION: q?RvTrF Rt'TinTNc 7057E R

' RING

REFERENCE:

Figure #6 u) Normal 40 yr. Dose: 760 rads RADIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Seismic Cateeory I Ventilation (non redundant) Supplied with Ambient Temperature Monitors PLANT ID DESCRIPTION NOTE FUNCTION

• 8 2-BY-B-04A Station Battery 2-4

• 8 2-BY-B-04B Station Battery 2-4 Battery Rm. 2-4 Exh. Fan

• 9 2-H V-F- 5 7 D Battery Rm 2-4 ventilation Flow Sw.

• 9 FS-HV-2207D

• 8 2-BY-B-02A Station Battery 2-2

• 8 2-BY-B-02B Station Battery 2-2 Battery Rm. 2-2 Exhaust Fan

• 9 2-HV-F- 57 B i

l Battery Rm. 2-2 Ventilation Flow Sw.

• 9 FS-HV2207B e l

I 1

l 6 w Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

NMENTAL REPORT PIANT: VEPCO, Nerth Annq 2 NRC REF.: NUREC - 0588 LOCATION: AUYTLTARY BUTLDING ZONE B

/m

[V; WING

REFERENCE:

Fim2re Normal #1 Dose:

40 yr. 3.s x 104 rads RADIATION LEVEL:

Accident Dose: 5 x 106 rads HVAC CATEGORY: - Redundant Ventilation Exhaust PLANT ID DESCRIPTION NOTE FUNCTION 2-CH- P-01 A Charg. Pump A 2,5 2-CH- P01B Charg. Pump B 2,5 2-CH-P01C Charg. Pump C 2,5 l

l l4

• Denotes environmental qualification sheet not recuired.

For function descriptions see first page of this section.

l

EQUIPMENT ENVIRONMENTAL REPORT PIANT: VEPCO, Nerth Annn 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDINC 20hT D rx

( 7 RING

REFERENCE:

Fimn e #5

() Normal 40 yr. Dose:

RADIATION LEVEL:

Accident Dose:

HVAC CATEGORY:

PIANT ID DESCRIFFION NOTE FUNCTION No Required Fouff mane l

l 4 0 Denotes environmental cualification sheet not required.

l For function descriptions see first page of this section.

i

NMENTAL REPORT PLANT: VEPCO, N9rth Ann,2 NRC REF.: NUREC - 0588 LOCATION: M yrcE ntf77nTMc ?nNR v

[m'% WING

REFERENCE:

Ficure h5 C/ Normal 40 yr. Dose: 260 rads RADIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Seismic Catalog I Ventilation (non redundant) Ambient Temperature Monitors PLANT ID DESCRIPTION NOTE FUNCTION 2- BY -B-01 A Station Enerprv 2-1

• R 2- BY -B- 01 B Station Betterv 2-1

• 8 F9-HV2207A Rareprv Rm. 2-1 Van t f i nr i nn F1nu Ru.

• 9 2-HV-F- 57A Batterv Rm. 2-1 Exhaust Fan

• L l 2-By-B-03A Station Batterv 2-3

• 8 l i

2-By-B-03B Station Battery 2-3

• 8 FS-HV2207C Battery Rm. 2-3 Ventilation Flow Sw.

• 9 2-HV-F-57B Battery Rm. 2-3 Exhaust Flow Sv.

• 9 l

l l I

L* Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

VIRONMENTAL REPORT PIANT: VEPCO, N rth Annq 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDING ZONU F WING

REFERENCE:

Figure #/.

Normal 40 yr. Dose: _ 260 rads RADIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Class IE Redundant AC/ Redundant Emergency Ventilation PLANT ID DESCRIPTION NOTE FUNCTION 2-EP-CB- 12 D1 DC Disl. Pane' 2-4A

• 8 l MOV-HV-204-1 Control Rm. Emer. Air Supply

• 7 MOV-HV- 204- 2 Control Rm. Emer. Air Supply

• 7 2-EP-CB-28RS2A Aux. Relay Cab. Casing Cooling

• 2 2-EP-CB-28RS2 B Aux. Relay Cab. Casing Cooling

• 2 2- EP-CB-34 Control Panel for Control Rm. A/C

• 6 2-E P-CB-3 5 Control Panel for Control Rm. A/C

• 6 2- EP-CB-19 A Vital SOV Panel

• 8 2- EP-CB- 19 B Vital SOV Panel

• 8 2- E P-CB- 23 A DC Dist. Panel 2A

• 8 2-EP-CB-23B DC Dist. Panel 2B

• 8 2-EP-CB-04A vital Bus Cab. 2-1

• 8 2- EP-CB- 04B Vital Bus Cab. 2-2

• 8 2- EP-CB- 04C Vital Bus Cab. 2-3

• 8 Vital Bus Cab. 2-4

• 8 2-EP-CB-04D

• Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

W T ENVIRONMENTAL REPORT PLANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDING ZONE F A

' RING

REFERENCE:

Firruro #4 s_/ Normal 40 yr. Dose: 260 rads RADIATION LEVEL:

Accident Dose: __

160 rads HVAC CATEGORY: Class IE Redundant AC/ Redundant Emergency Ventilation PLANT ID DESCRIPTION NOTE FUNCTION 2- EI-CB- 01 Main Control Board

• 2,3,4,5 2-EI-CB-02 Main Control Board

• 2,3,4,5 2-EI-CB-03 Main Control Board

• 2,3,4,5 2-EI-CB-04 Main Control Board

• 2,3,4,5 2-EI-CB-05 Main Control Board

• 2,3,4,5 2-EI-CB-07 Ventilation Control Board

• 6,9 2- EI-CB-08 A Emer Gen. 2H Control Panel

• 8 2-EI-CB-08B Emer. Gen. 2J Control Panel

• 8 2-EI-CB- 156 A Control Cab. for Air System

• 6 2-EI-CB-156B Control Cab. for Air System

• 6 i

2-EP-CB-80A Inst. Disl. Panel 1

• 8 2- EP-CB-80B Inst. Disl. Panel 2

• 8 l

l 2-EP-CB-80C Inst. Dist. Panel 3

• 8 2- EP-CB-80D Inst. Disl. Panel 4

• 8 l

l 62-EP-CB-12B1 DC Disl. Panel 2-2A

• Denotes environmental cualification sheet not required.

• 8 1

I For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT PLANT: VEPCO, Nerth Anno 2 NRC REF.: NUREC - 0588 LOCATION: cru vice nittiminc vrwr v

/%

l lRING

REFERENCE:

Figure #4 V Normal 40 yr. Dose: 260 rads RADIATION LEtTL:

Accident Dose: 160 rads HVAC CATEGORY: Class IE Redundant AC/ Redundant Emerstency Ventilation PLANT ID DESCRIFFION NOTE FUNCTION

• 6 2 -H V- AC-03 Control Rm. A/C

• 6 2-H V- AC-09 Control Rm. A/C

• 6 2-HV-F-41 Control Rm. Emer. Vent. Fan l

I e u Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N*trth Andn 2 NRC REF.: 'NUREC - 0588 LOCATION: SERVICE BUILDING ZONE G WING

REFERENCE:

Firure #4 Normal 40 yr. Dose: zou rads DIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Ventilation Supplied from Safety Power (non redundant)

PLANT ID DESCRIPTION NOTE FUNCTION 2 - EC-C- 2.f A Pmar. Cen. Air comnrasnor 1

• 8 2-EG-C-2JB Emer. Gen. Air Compressor 2

• 8 2 PP-MC-l's MCC 271-1A

• 8 2- E E- EG-04 A Emer. Gen. Unit 2J

• 8 2-EE-EG-04B Emer. Gen. 2J Eng. Control Box

• 8 2-EE-EG-04C Emer. Gen. 2J Control Cab.

• 8 2-EG-B-04D Emer. Gen. 2J Battery

• 8 1-HV-F-22D Exhaust Fan Emer. Gen. Rm. 2J

• 9 TS-HVL96D Emer. Gen. Rm. 2J Temp. Sv.

• 9 PS-EG2JA Emer. Gen. 2J Compressor Pressure Sw.

• 8 PS-EG2JB Emer. Gen. 2J Compressor Pressure Sw.

• 8 2-EG-AC-2HA Af ter Cooler Emer. Rm. 2H

• 8 2-EG-AC-2HB Af ter Cooler Emer. Rm. 2H

• 8 1

l Denotes environmental qualification sheet not required.

l For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL REPORT PLANT VEPCO. N rth Ann 9 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDING ZONE J

(-

Figure #5

(~[J. WING

REFERENCE:

Normal 40 yr. Dose: _ 260 rads RADIATION LEVEL:

Accident Dose: 160 rads HVAC CATEGORY: Redundant HVAC PIANT ID DESCRIPTION NOTE FUNCTION c ,

i S OV-HV- 160-1 Control and Rel. Rm. Supply Air Damner

• 6 I

I' i

!

• I SOV-HV-160-2 Control and Rel. Rm. Supply Air Damper 6 i

l S OV-HV _161- 1 Control and Rel. Rm. Exhaust Air Damper 6 i

i S OV-HV- 161- 2 Control and Rel.Rm. Exhaust Air Damper

• 6 i

I. . l i

l

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EQUIPMENT ENVIRONMENTAL REPORT gm vgPcq, Ntrth Ann" 2 NRC REF.; NUREc - 0588 LOCATION: SERVICE BUILDING ZONE K

[h

.lWING

REFERENCE:

. Figure #6-Normal 40 yr. Dose: 260 rada RADIATION LEVEL:

Accident Dose: _160 rada HVAC CATEGORY: Class IE power single train ventilation PIJLNT ID DESCRIPTION NOTE FUNCTION

-  ?

chf11er um. Rn-n op 6 2-DB-P-LQA l

f 2-HV-F- 24 Equipment Rm. Supply Fan l 6 l

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I 6 T

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6 2-HV-E-4B Control and Relay Rm. A/C Chiller }6 l

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EQUIPMENT ENVIRONMENTAL REPORT PIANT: VEPCO, N rth Ann 9 2 NRC REF.: NUREG - 0588 LOCATION: SERVICE BUILDING ZO?E H WING

REFERENCE:

Fir ure #4 Normal 40 yr. Dose: 260 rads DIATION LEVEL:

Accident Dose: 160 rads HVAC CATECORY: Ventilation Supplied from Safety Power (non redundant)

PLANT ID DESCRIPTION NOTE FUNCTION 2-FC-C-2HA Emer. Gen. Air Comoressor 1

• 8 2-EG-C-2HB Emer. Gen. Air Compressor 1

• 8 2 -E P-MC- 12 MCC 2H1-IA

• 8 2-EE-EG-02A Emer. Gen. Unit 2H

• 8 2-EE-EC-02B Emer. Gen. 2H Eng. Control Box

• 8 2-EE-EG-02C Emer. Gen. 2H Control Cab.

• 8 2-EG-B-02B Emer. Gen. 2H Battery

• 8

_ l-HV-F-22B Exhaust Fan Emer. Gen. Rm. 2H

• 9 TS-HVl96B Emer. Gen. Rm 2H. Temp. Sw.

• 9 RPS-EG2HA Emer. Gen. 2H Compressor Pressure Sw.

• 8 RPS-EG2HB Emer. Cen. 2H Compressor Pressure Sw.

• 8  !

2-EG-AC-2JA Af ter Cooler Emer. Rm. 2J

• 8 2-EC-AC-2JB After Cooler Emer. Rm. 2J

• 8 l

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Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPHENT ENVIRONMEMTAL REPORT PIANT; VEPCO, N+rth Annn 2 NRC REF.: NUREG - 0588 Quench Spray Pump Hose below 271 I LOCATION:

/ lWING

REFERENCE:

N/R (j Normal 40 yr. Dose: Neelicible RADIATION LEVEL: 6 Accident Dose: 5.4 x 10 ,

HVAC CATEGORY: Nonredundant Ventilation PIANT ID DESCRIPTION NOTE FUNCTION MOV-SW201A Recircular Spray Heat Exch. Heater Inlet

• 3,5 MOV-SW201B Recircular Spray Heat Exch. Heater Inlet

• 3,5 _

MOV-SW201C Recircular Soray Heat Exch. Feater Tnlet

• 3.5 MOV-SW201D Recircular Snrav Heat Exch. Unntor Tel n e

• 1 E MOV-SW203A Service Water en Poc4reninen Rarw rdolore

• 7,M

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• 7,5 MOV-SW205A Recirculatinn hrw Unn e Pv. Un,ene enelne

• 5 MOV-SW205B Recirculation Spray Heat Ex. Heater Outine

• 9,9 MOV-SW205C Recirculation Spray Heat Ex. Heater Outlet

• 1.5 MOV-SW205D Recirculation Spray Heat Ex. Heater Outlet

• 1, 9 l

l l

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EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO, N:eth Anna 2 NRC REF.: NUREC - 0508 LOCATION: ntfENCH SPDAY MNp Mnffsr

/x N/R (b' 3fING

REFERENCE:

Normal 40 yr. Dose: u,.g 147 4h1.

RADIATION LEVEL:

Accident Dose: 4.8 x 10 2 HVAC CATEGORY: . Nonredundant PIANT ID DESCRIPTION NOTE FUNCTION Ouench Spray Pump 1A

• 3,5 2-OS-P-1A 2-QS-P-1B Ouench Spray Pump 1B 8 3,5 l

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• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

EQUIPMENT ENVIRONMENTAL kEPORT PLANT: VE PCO , Nerth Anno 2 NRC REF.: NUREG - 0588 LOCATION: qArtctfAnns ArrA WING

REFERENCE:

N/R Normal 40 yr. Dose: _ Netligible RADIATION LEVEL:

Accident Dose: _. 5x106 rads HVAC CATECORY: Redundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION 2-HV F- 71 A Ventilation Safeeuard Area 10 2-H V-F-71 B Ventilation Safecuard Area 10 --

M0"- OS- 201 A nuench spray PP Discharce 3,5 MOV- OS- 201B Ouench Soray PP Discharge 3,5 Mov-OS-295A Recirculation Soray Suction 3,5 MOV-QS- 2 5 5B Recirculation Soray Suction 3,5 MOV-RS-2 56 A Recirculation Soray Discharge 3,5 l

_ MOV-R S- 2 56B Reefreulation Spray Dfscharge 3,5 l

l 2-RS- P- 2 A Recirculation Soray Pumo 3 2-RS- P- 2 B Reci rculetion Soray Pump 3 l

l l

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v Denotes environmental cualification sheet not required.

For function descriptions see first page of this section.

T ENVIRONMENTAL REPORT FIANT: VEPCO, North Anna 2 NRC REF.: NUREC - 0588 TION: Safeguards Area RAWING

REFERENCE:

N/R Normal 40 yr. Dose: lierlicible RADIATION LEVEL: 6 Accident Dose: 5 x 10 Rnic HVAC CATEGORY: Pedundant Ventilation PLANT ID DESCRIFFION NorE FUNCTION 2-RS-P-2B Recirculation Spray Pump 3 l I

• Denotes environmental qualification sheet not required.

For function descriptions see first page of this section.

- - - - , co.- _ , -,

TAL REPORT FLANT: VEPCO, North Anna 2 NRC REF.: NUREG - 0588 TION: Safenuards :m -

RAWING

REFERENCE:

I:/d Norlaal 40 yr. Dose: lier'lihie RADIATION LEVEL: o Accident Dose: 5 x 10 ib d a HVAC CATEGORY: Redtriar.t Ventilation PIANT ID DESCRIFIION NOTE FUNCTION MOV-2860A LHSI Pump Suction Valve

• 2,3 MOV-2860B LHSI Pump Suction Valve

• 2,3 MOV-2885A LHSI Pump Recirculation Velve

• 2,3 MOV-2885B LHSI Pump Recirculation Valve

• 2,3 FDV-2890A LilSI Line Stor. Valve

• 2,3 i

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I

EQUIPMENT ENVIRONMENTAL REPORT PLANT: VEPCO. N rth Ann 1 2 NRC REF.: NUREG - 0588 LOCATION: TURBINE BUIIDING WING

REFERENCE:

N/R Normal 40 yr. Dose: 260 rads RADIATION LEVEL:

Accident Dose: 160 rad HVAC CATECORY: - Noncedundant Ventilation PLANT ID DESCRIPTION NOTE FUNCTION MOV-SW-220A Service Water Discharge to Cire. Tunnel

• 1 MOV-SW-220 Service Water Discharge to Cire. Tunnel

• 1 4

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TAI REPORT FIANT: VEPCO, North Anna 2 NRC REF.: NUREG . 0588 c LOCATION: Tard I

v ,!: AWING

REFERENCE:

N/R Normal 40 yr. Dose: re-lihih)e RADIATION LEVEL:

Accident Dose: MeM i ni M c HVAC CATEGORY: N/R PLANT ID DESCRIPTION NOTE FUNCTION LC 70-200A E.F. '.Itr. Storace Tank

• 3,5 LT CC-2003 E.7. Utr. Storage Tanh " 3,5 LT-Q-2000 T.cfuelin;; Uator Storace Tarl:

• 3,5 LT :D-200D refueling '.:ator Storago Tanh '

3,5 M77-20-202A Refueling Unter,Chor.1. Edition Tenk 3,5  ;

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1 Qualification and Evaluation FytllPNEN T !)ESCRll'IlON DESCRIPTION OF ENVIRONMENT OPFRARILITY REQtilREMENTS A/C Chillers Main Steam Line Break (MSLB) In Turbine Break NSLB NANiit ACTlikt RS 1. liigli ambient temperature 211 F 30 minutes - 211 F & 1001 Ril for duration of steam elistharge Westanr, house Electric Cosposation in vicinity of chiller room air CITRARILITY DEt9)NSTRATED Ho.lel iPOa88W antakes - 30 minutes.

HS!$

SIIPPLIER ENVIRohMENT TO WillCll EjU!!'flENT IS gllAliFIED None Snne .es hove MSLB ACCURA _CY REQL}lRENENTS P.O.

~~

Nonu Not. Requireal NA - 1247 (l(NCTI(JN Cont rol kooin liabitability lgCATION Servic e Buil. ling, Chiller roons Zone K ,

$lAl@_NO .

2-IIV-E-4A , Cont s ol an.1 Re lay Roma A/C Chiller 2-IIV-E-4h, Control anil Relay Rone A/C Chiller 2-ifV-E-eC, Cont. ,. .n.1 kelay Room A/C CI: eller

r\ ry [5

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la Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES yt!ALIFICATION DOCUMENT AND REC 0t1MENDFD SOLUTIONS HANNER OF Qt!A MFICATION HSLB HSLB HSLB None None A. Deficiencies:

Equipment not qualified for exposure to:

1) High ambient temperature 211 F

2) Saturate

• atmosphere, 100% R.H.

B. Solutions:

In the event of a Main Steam Line Break (MSLB) in either turbine building and the corresponding failure of a main steam stop valve to shut, temperature in the control goom A/C chiller room will approach 180 F at 100% relative humidity due to steam blowdown entering the thiller room. A/C chiller systems are not qualified to withstand these environmental conditions. In order to maintain habitable temperat ures in both tinits' s ontrol rooms under the above conditions it is necessary to operate two A/C chillers in the unaffecte.1 unit.

Continued operation of Unit 2 can be justified on the basis of always having two Unit 1 A/C Chillers, one Unit I caergency diesel generator and the two Unit I caergency buses available. Since the analysis assumes a main steam trip valve fails to shut, no other single tailure need be postulate.1 per Regulatory Guide 1.81. Therefore, only one Unit I diesel generator nerd be availaale to operate two A/C chillers (this arquires tying emergency buses lit and IJ).

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Q. J '%sl 2

Qualification and Evaluation EWII_phNT_D,ESCRIPTION DESCRIPTION OF FNVIRONMENT OPERABILITT RF3}tllkEME_NTS Air Con.litsoning Self-Cleaning Strainers Main Steam Line Break (MSLB) in Turbine Ruilding MSLB in Turbine building HANUFACTURFikS 1. Itigh ambient temperature 211 F for 30 minutes - 2tl F and 1001 Ell for duration of steam discharge in Elliot Company vicinity of chiller room air intakes, OPERABILITY DENONSTRATED Model #ECA

2. High ambient moisture content MSLR in Turbine Building SUPPLp;R saturated steam, 1001 Ril for duration of steam discharge None Same as aleuve ENVIRONMENT TO Mif CH EQUltitENT IS QUALIFIED ACCURACY RFQUIREMENT NSI.R in Turbine Building Not Required NA-1299 None

[1JNCTIO_N Cont rol Huom liabitability LOCATION ACCURACT DEMONSTRATED Seavire Building, Chiller room N/A Zone K ,

[lAkl _N,{h 2-ilV-S-IA, Self-cleaning Strainers 2-IIV-S-lH, Self-cleaning Strainers

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,._ / v  %./

2a Qualification and Evaluation (Cont'd)

Q"ALIFICATION DEFICIENCIES ttANNER OF fp]Al.IFICATION ff AI.lFICATION DocttfENT A% RECOMMEhDED SOLUTIONS MSLR in Turbiric building MSI.B in Turbine Duilding MSLB in Turbine BuildinE None None A. Defiriencies:

I. liigh ambient temperature 211"F

2. Saturated atmosphere B. Solutions:

In the event or main steam line break (MSLB) in either turbine building and the corresponding failure of a main steam stop valve to shut, temperature in the control rone A/C chiller room will approach 180 F at ID01 selative humidity due to steam blowdown enter-ing the challer room. A/C chiller systems are not qualified to withstand these environmental conelitions.

In order to maintain habitable tempera-tures in both Unit s' c ont rol rooms under the above renditions it is nec-essary to operate two A/C < ht llers in the unaffected unit.

Continued operation of linit 2 can be justified on the basis of always having two finit i A/C Chillers, one linat I emergency diesel generator and the two Unit I emergency buses availabic.

Since the analysis assumes a main steam t rip valve f ails to shut, no other single failure need be postu-lated per Regulatory Guide 1.88.

Therefore, only nne lin i t I diesel generator need be available to operate two A/C chillers (this requires tying emergency buses IH and IJ).

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3 Qualification and Evaluation

[QUltitENT DESCRIPTION 1)ESCRIPTION OF ENVIRONMENT OPERABFt.lTY REQtilRFPfENTS Propeller F.in Plain Steam Line Break (NSLR) In Turbine hreak HSIB in Turbine lluilling flANtf[ACTUkERS 1. Iligh ambient temperature 211 F 10 minutes - 211 F & 1001 kH for eluration of steam discharge Acaovent Fan Coms.any, Inc. in virinity of chiller room air OPERARILITY DEff0NSTRATED Hodel #1-216; ins. Class F intakes.

2. High ami.icnt mo.isture content HSI.R in Turi >ine Ituil. ling SUPPL. lek

" -~

saturated ste.im, 1001 Ril for durat ion of steam disc harge. 30 minutes - 211 F & 1001 kil Same as al>ove ENVikONPfENT TO WillCH EqtilP".ENT IS Qi!Al.IFIED ACCtfRACY REQIllREMENTS PA HSLB in Tuabine Building NA - 1241 1. High amhient temperature 211 F at saturated atmosphere. ACCT' RACY _l_$_ftlNSTRA_TED

[UNftl0N

2. See Qualification Deficiencies N/A Cont rol koom II.shitabilit y llEATION Servite Ituilding, Chiller room Zone K ,

HARK NO.

2-liv-F-24, Equipment Ro m Supply Fan

3a Qualification and Evaluation (Cont'.1)

Qt!AI.lFICATION DEFICIENCIES itANNF.R OF_QtJAI.lFICATlyN Qt:AI.IFICAT!nN IMYthr:NT Aht) REOMtENDED SOLUTIONS Test TI.X-3-29 W. B. Schumaclaer PtSLB to J. E. Erethling A. Defiriencies:

Qua l i f ira t ion dat usent is a TL7 susunarszang test results.

9 Solution:

Istter has been sent to supplier requesting copy of test report or arrangreent made for audat to records at vendor's plant.

v v  %/

4 Qualitiration and Evaluation EQUlittENT DESChil"flON DESCRIPTION OF ENVIRONMENT OPERABILITY kEQtilREMENTS In-line Pumps Main Steam Line Break (MSLB) in Turbine Building HSLB tlANilFACTI:HER 1. IIngh ambient temperature 211 F 30 minutes - 218 F and 100% Ril for duration of steam discharge Itingham - Winiamette Company in vicinaty of chiller room OPE _RAltlLITY DEf10NSTRATED Ho.tel 20's #7 7111581G47 Type "B" insulat ion air intakes 30 minutes.

Model 22's #7731tS81G31 Type "it" insulation HS_LR

2. Itagh ambient moisture content

• >ljt PLla saturated steam 1001 Rif for None eluration of steam disch.arge Same .as above 30 minutes. ACCliRACY IEQUI.REMENTS P.O. ENVIRONNENT TO Mi!C11 Ef)UIPMENT ISJUALIFIED Not Reeguired NA-1276 MSLil

>tlNCTioN None Cont rol Room llahitabii a ty I.tW XIinN Service !!nsiding, Chiller Room Zone K MAKK_Ny.

2-ilV-P-20A, in-line pump - Air Conelitioning 2 -IIV - P- 20 lt , in-line pump - Air Conditioning 2 -IIV- P- 20C , I..-line pump - Air Conditioning 2 - IlV- P-2 2 A , in-line pump - Air Conditioning 2 - IIV- P- 2 2 f t , in-line pump - Air Conditioning 2-IIV-P-22C, In-line pump - Air Con.fitioning

N ']'

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4a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES HANNER OF QUAL.lFICAff0N QUAI.lFICATION DOct4fENT AND RECOMMENDED Sol.trTIONS USI B USLp US_l.Q None None A. Deficiencies:

Equipment not qualified for exposure to:

1) liigh ambient temperature 211 F

2) Saturated atmosphere, 100% R.H.

B. Solutions:

In the event of a flSLIl in either turbine building and the vorsespond-ing failure of a main ste.im stop valve to shut, temperature in t he c ont rol room A/C rhiller room will approath 180"F at 100% relative humidity due to steam blowdown entering t he chiller room. A/C < hiller systems are not qualified to withstan.1 these environ-mental conditions.

In criler to maintain habitahic temperature in both units' rentrol room under t he above rondit ions it is necessary to operate two A/C thillers in the unaffected anit.

Continued operation of Unit 2 aan 1.c justified on the basis of always having two Unit i A/C < billers, one Unit I emergency diesel generator and the two Unit I caergenry l>uses avail-abic. Since the analysis .sssumes a main steam trip valve fails to shut, no oth-r single failure need he postulated per Regulatory Guide 1.88.

Therefore, only one Unit t .liesel generator need be availabic to operate two A/C thillers (this requires tying caergency buses 111 an.1 1.1) .

/] N N 5

Qualification and Evaluation DESCRIPTION OF ENVIRONMENT OPERABil.lTY REQlMRENF;NTS EQtlilt1ENT I)ESCRIPTION Sump Pumps  ?!ain Steam Line Break (NSI.R) in Turbine Building HSI.ll in Turbine Building HANtlFACTtil<ER I. liigh ambient temperature 211 F for 30 minutes - 211 F & 100% k!!

duration of steam discharge in vicenity Juhuston Pump Company of chiller room air intakes 30 minutes, OPERAltli.lTY REqutREMENTS tio<tel # Type RGZV

2. liigh ambient mositure content - MSI.P in Turbine lluilding SUPPI.lER saturated steam, 100% Rif for duration of steam discharge None Same as above 30 minutes.

ACCURA.CY RFQlllREMENTS P.O. ENVIRONMENT TO WillCil EQUIPHfjNT IS QtIAI.lTIED NA-1421 1. liigh ambient temperature 211 F at saturated atmosphere llW_CT!DN Con t a ul koom liabi t al i l i t y

,1.OCAT I ON Servite Hailding, Chiller Room Zone K HAl<K NO.

2-Dil-P-10A, Chiller Room Sump Pumps

(

\% ~  %

5a Qu.slification and Evaluation (Cont'd)

QtlALIFfCATION DEFICIENCIES

[1ANNtH_,OF yllALIFICKilON AND RECOMMENt)ED SOLIJTIONS 9tlAl.lFICATION IkCllHENT (10!!). s_rt Tus hine linilding MSLH in Turbine Huilding MSLR in Turbine Bullling Test TLX 3-28 John Anderson A. Deficiencies:

to J.E. Krechting

1. Ifigli assinient t esipt rast us e 2il"F Vendor seply to TLX innluiry 2. Saturated atmosphere

3. TLX simunary of test report H. Solutions:

1. Contacted Vendor for copy of test report. and/or audit of Vendor's records

2. Il no qualitiration lata available use equigeent in unaffected unit t o :n.s int.a in control room environment.

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6 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONPIENT OPERABILITY REQUIREMENTS 600 V Cu Power Cable Loss of Coolant Accident (LOCA) LOCA MANUFACTUREN~ 280 F 0 to 30 min 120 days @ 150 F Reduce from 280 F Okonite to p 3 F 30 to 60 min Main Steam Line Break (MSLBJ Jacket: Neoprene 150 F >60 min Insulation: Ethylene Propylene Rubber 45 psig 0 to 30 min Reduce from 45 30 to 60 min 120 days @ 150 F to O psig SUPPLIER 0 psig >60 min OPERABILITY DEMONSTRATED 4.8 x 107 rads Same as above Spray: 0-4 hr solution of boric acid P.O. (2,000 - 2,100 ppe boron) buffered to a pH of 8.5 to 11 with NaOH)4 hr.

NA-1128 Similar solution with a pH of 7 to 9.

FUNCTION Main Steam Line Break (MSLB)

Supplies Power to Safety Systems 430 F 0 to 2 min 280 F 2 to 60 min PostLOCAthermalagfngisgreater 150 F >60 min than 2.9 years @ 150 F IDCATION 45 pr.ig 0 to 30 min Reduce from 45 MSLB Inside and Outside Containment to O psig 30 to 60 min O psig >60 min See above MARK NO. 3 x 10' rads ACCURACY REQUIREMENTS NCA-20, 1/c 250 MCM ENVIRONMENT TO W1f!CH EQUIPtfENT IS QUALIFIED NGA-21, 1/c 2/0 AWG LOCA & MSLB NGB-15, Triplex #4 AWG LOCA*

NGB-16, Triplex #6 AWG Not Required NGB-17, 1/c #8 AWG Aged 168 hr @ 121 C NGB-18, 3/c #10 AWG Irradiated to 2 x lo s rads NGB-19, 3/c #12 AWG Spray: 10,000 ppm boric acid buttered with NaOH to a pH of 10.5 throughout the PWR exposure period.

• The same cables that had been exposed to the PWR accident conditions were then exposed to a BWR simulated accident condition.

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(%_a) 6a Qualification and Evaluation (Cont'd)

ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED IpCA 304 F - 3 hr 20 min

, 346 F - 4 hr 27 min 256 F - 1 day 212 F - 100 days 259 F - 10 hr 324 F - 4 hr 252 F - 7 days My Same as above QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS U)CA LOCA LOCA Test - Sequential Okonite's Engineering Report A. Deficiencies:

No. 141 dated 2/29/72 MSLH None Additional Supporting Documents Test - Analysis MJLB - Comment Outline of Franklin Institute Research Laboratory Report -C3694 Qualification based on independent test and analysis.

IEEE Transaction paper T 74 044 4 Each of the qualification parameters (obtained from independent test and analysis) exceeds the corresponding Stone & Webster Calc. #ES-215-0, MSLB requirements.

Cable Temperature Transcient, dated 8/10/79. Amend FSAR as stated in " Qualification Document".

Maximum calculated surface temperature during limiting MSLB in 355 F which does not exceed qualification temperature of 345 F given in BWR exposure portion of LOCA qualification, per Cale. #ES-215-0.

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( b) 7 Qualification and Evaluation EgullM[j{MRIPTjQN DESCRI.pTION OF.ENVIRONtfENT OPERABILITY _ REQUIREMENTS liigh Temperature Cable Loss of Coolant Accident (I.0CA) IDCA HANUFACTURER 280 F 0 to 30 min 120 days @ 150"F

' ~ ~ ' ' ' " ~ ~ ~

Reduce from 280 F Cerru Wire anil C.shle Cnspany to ,1,50"F 30 to 60 min MSLR Jacket: Ashestos Braid 150 F >60 min i nsul.s t a un : Silirone Rul.ber 45 psig 0 to 30 min 120 d.nys @l50 F Redute from 45 SilP_Pl. l ER to O psig 30 to 60 min OPERAllILITY DEMONSTRATED 0 psig >60 min Same as .above 4.8 x 10 7 rads LOCA Spray: 0-4 hr solution of horir acid 276 F for 12 hr P.O.~

(2,000-2,100 ppm boron) buffered to a 160 F for 7 days NA-1359 pH of 8.5 to II with Naoll >4 hr Similar solution with a pil of 7 to 9 PostLOCAthermagagingisequivalent to 65 days @ 150 F.

[tJNCION Main Steam Line lireak (HSLR)

8. Enginecir.1 S.sfety Feature HSLR

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2. DilA (IfiCA and MSLR) Mitigation 430"F 0 to 2 min 280"F 2 to 60 min See above 150"F >60 min I.OCATION 45 psig to ACCURACY REQllikEMENTS 0 pt ig 30 to 60 min -

luside Cont.sinment 0 psig >60 min Not Required 3 x 107 rads NANK_NO.

ENVIRONMENT TO WillCH EQtJIPMENT IS quai.lFIED NGA-l's Triplex 250 HCH Note: NGA-15 is required for the inside lACA recirculation spray pumps.

Irra.liated to 2 x lo s rads, 50 psig, and 2/6"F for 12 hr Spray: Last 2 hr of 12 hr period with a solution of borated water containing approximately 1,720 ppm of baron as boric arid.

Reduced to 5 psig and 164 F over an unspecified time with spray continuing.

IM"F at 5 psig for the remainder of the 7 day period without spray.

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7a Qualification and Evaluation (Cont'd)

ENVIRONMENT TO WHICil FgullitENT IS_QtIALIFIED (Cont'd)

MANNER.tg_ QUAI.lFICATION F-C2750 isulicates that in an earlier QUALIFICATION DEFICIENCIES test, the spray was buffered with NaOH AND RECOMMENDEO SOLUTIONS l.OCA to pl! of 9.

IDCA Test - Sequential (ISI.Il A. Deficiencies:

[ Fill! Same as "Descriptson of Environment" Qualification documents do not Temperature - Analysis QUALIFICATION DOCitfENT address:

Pressuse and Radiation - Test LOCA l. 276 F, O to 30 min vs Franklin Institute Research 280 F Refer to IDCA Qualification I.aboratory (FIRL), Report F-C2857 2. 1,750 ppe boson vs 2,000 ppm Cerro's Supplement to FIRL, 3. Long-term post-accident Report F-C2857 B. Solutions:

FIRL, Report F-C2750

1. The above 276 F through Cerro's Supplement to FIRL, first 30 min is within Report F-C2750 tolerance of the 1.oCA tem-perature transient prolite -

MSLil FSAR Fig. 6.2-82 (Amendment No. 65).

FSAR Section 3C and response to - 2. The cable jacket is of an Cousnent 7.11. abestos braid whit:h has been shown to be resistant to all Rockhestos' letter dated 4/25/77 diluted alkaline solutions.

IDCA qualification documents. Therefore, we helieve th.st since the IDCA spray is in F-C2750 indicates that in an earlier the range of a diluted alkaline test, the spray was buffered with Narli solution, it should have no to pH of 9. significant ef fect on the cable.

3. The cable (NGA-15) insulation Each of t he qualification parameters is rat ed for 125"C con.im tor (obtained from independent test and temperature at rate.1 amparity, analysis) exceeds the corresponding it can he shown by stand.srd MSLil requirements. industry practices that the cable is capable of operating in a 150 F ambient continuously.

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Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS 600 V hatrol Cable Loss of Coolant Accident (LOCA) IDCA & Main Steam Line Break (MSLB)

MANUFACTURER 280 F 0 to 30 min 120 days @ 150 F Reduce from 280 F 30 to 60 min Cerro Wire and Cable tog 50*F OPERABILITY DEMONSTRATED Jacket: Neoprene 150 F >60 mit Insulation: Cross-Limited Polyethylene 45 psig 0 to 3i sin LOCA Reduce from 45 SUPPLIER to O psig 30 to 60 win 270 F for 12 hr 0 psig >60 min 160 F for 6 days Same as above 4.8 x 107 rads Spray: PostLOCAthermagagingisequivalent PA . 0-4 hr Solution of boric acid to 71 days @ 150 F (2,000-2,100 ppe boron) buffered NA-1312 to a pH of 8.5 to 11 with NaOH FUNCTION >4 hr similar solution with a pH ACCURACY REQUIREMENTS of 7 to 9.

Supplies Power to Safety Systems Main Steam Line Break (MSLB)

LOCATION ) 60 min O psig 40 yr dose Inside and Outside Containment 3 xo to rads h3c F 0 ta 2 min 280 F 2 to 60 min MARK NO.

1500F > 60 min GA-19, 2/c #2 AWG NGA-45, 2/c #12 AWG -

NGA-34, 1/c #14 AWG NGA-47, 4/c #12 AWG ENVI!Y)NMENT TO WHICII EQUIPMENT IS QUALIFIED NGA-35, 2/c #14 AVG NGA-49, 7/c #12 AWG NGA-36, 3/' M 4 AWG NGA-57, 4/c #10 AWG m NGA-37, 51 414 AWG NCA-77, 4/c #10 AWG NGA-38, 7/c ei4 AWG NCA-43, 2/c #8 AWG Irradiate to 2 x 100 rads NGA-39, 9/c #14 AWG NGA-44, 2/c #6 AWG 50 psig and 2760F for 12 hr NGA-40, 12/c #14 AWb NGA-45, 4/c #6 AWG Spray: Last 2 hr of 12 hr period NGA-44, 1/c #12 AWG with a solution of borated water containing approximately 1.,720 ppm of baron as boric acid.

Reduce to 5 psig and 1640F nyer an unsgecifiedtimewithspraycontinued.

160 F at 5 psig for the remainder of the 7 day period with no spray.

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k 8a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION ENVIRONMENT TO WillCll EQUIPMENT IS QUALIFIED (Cont'd) AND RECOMMENDED SOttrTIONS

.LOCA USLE See frt,B Qualification Sequential Test Thermally aged for 1,300 hr @ 150 C at a rate 0.30 x 10s rads per hr for MSLs total dose of 2.01 x 108 rad.

Sequential Test Spray: Solution of 6,'ei ppm Baron and hydrazine solution ma st..ained at a pH value of between 8.6 and 10.0 for 399 br 376*F @58 psig 0 to 13 min 376 F 062 psig 13 to 15 min 366 F @62 psig 15 to 20 ein 337 F 060 pgig 20 to 25 min Reduce from 337 F 25 to 3.6 hr

@60 psig to 242 F MANNER OF QUALIFICATION QUALIFICATION DOCUMENT, LOCA LOCA Sequential Test Franklin Institute Research Laboratory Report F-C2857 Cerro's Supplement to F.I.R.L.

Report F-C2857 Rockbestos Company Report 13-10407-E) S8-13-2 Test was performed on cable of a similar construction as that supplied in P.O. NA-312/1312 FSAR Section 3C and response to Comment 7.17 A. Deficiencies:

Qualification temperature is below proposed accident temperature 430 F for 2 min vs 376 F for 13 min Solutions:

Surface temperature will reach a maximum of 355 F after 2 min 0430 F for therefore we meet the temperature requirements.

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QUALIFICATION DEFICIENCIF.S AND RECOMMENDED SOLUTIONS

[lANNEN OF MIALEICATIOri QUALIFICATION DOCUMENT IDCA IDCA LOCA Sequential Test B.f.W. Letters dated A. Deficienrics:

1-17-72 12-14-11 1. 8-8.5 pil vs 8.5-11 pit See Note 1 2. Tir.e, temperature envelope not sufficient.

MSI.B M_S_Lil

3. Insuf f icient post-operability demonstrated.

Temperature - Analysis of me,.mium calculated FSAR Section 3 C =ad response surface temperature during limiting MSI.B to coeuwent 7.17 is 343"F whic h does not exceed qualification B/ Solutions:

temperature of 460 F given in R.I.W. letter R.I.W. letter dated 10-12-76 date d 10- 12-76. Pressure and Railiation - LOCA Qualification documents 1. The cable jatket is of Test ref er to IDCA qualification. a neoprene material which was showa to be resistant to all dilute.l alkaline solutions. Therefore, we believe that since the LOCA spray is in the range of a diluted alkaline solution it should have no signilirant effect on th= cable.

2. This instrument rable has the same jacket and insula-tion as the (200v Cunt rol Cable. P.O. NA 312/1312 page 8 which surpassed operability requirements.

3. llave contacted manuf acturer to obtain f urther data.

Noy: I.etter has b- sent to supplier requesting ropy of test report, or arrange-ment made for audit et records at vendor's plant.

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Qualification and Evaluation l

EQlllitlENT DESCRIPTION I)ESCRIPTION OF F.NVIRONMENT OPERABil.lTY kEglIREMEKTS 5 KV Alum Power C.ible Loss of Coolant Accident (LOCAJ IOCA MANUFACTIJ.HER I x 10" rads (leased on 120 day thCA). 1.04 x 106 rads in addition the 40 year radiation Crueral Cable dose of 4 w 104 rads must be considere.t OPERABII.lTY DEMONSTRATED J.as ket : Neoprene for a total possible radiation dose lusul .s t i on : Etbylene Propy. Rubber of 1.04 x 10" rad. LOCA SUPI'i. l ER ENVIRONMENT To WillCH EQlllitlENT IS _ QUAI.lFIED 2 x 10" rads S.sme as above LOCA_ ACCURACY REQUIREMENTS P . O ., Not Required NA-1255 2x 10" rads FilNCTION Supplies Power to Safet y Systems MQTit,LN Outside Containment MARK NO.

NGA 'l, Triplex 1000 MCH NGA-4, .1/C 500 HCH Aluminum Anm.>r NGA-6, 3/C 1250 HCH Aluminum Armor NCA-5, 3/C 1250 HCH Steel Armor NGA-10, 1/C 2000 NCH NGA-12, 3/C 1000 HCH Aluminum Armor NCA-13, 3/C 4/0 AWG. Aluminum Armor NCA-9, I/C 1500 HCH l

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QUAI.lFICATION DEFICIENCIES MANNEW Of gilALIFICATION QUALIFICATION DOCUMENT ANI) RECOMMENDED SOU TIONS thCA IDCA LOCA i

Test Cencral Cable Letter < lated 12-22-71 A. Deficiencies:

Qualification Document is in letter form.

The le t t e r i s a s unsaa r y o f t he nuclear environment tests per-formed on cables of a similar construction, which Cencrat Cable has stated are applicable.

B. Solution:

Letter has been sent to supplier requesting a copy cf test reports or arrangescut s made for an audit of qualifira-tion data, i

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Il Qu.slification and Evaluation Etfull MENT !)ESCRil' TION DESCRIPTION OF ENV!MONMENT OPERABil.lTY REQUIREMENTS 5 kw Alum, Power Ca!>le f.nsu of Coolant Accident (IJH:A) Loss of Coolant Accident (l.oCA) tt{NilFACTURg 5x 10 8 rads 5 x los rads Okonite Main Stram I.ine Break (HSI._B) OPERARILITY DEMONSTRATED

.J.schet : Neoprene Insulation: Cross-linked Polyethylene Will not see a changing envirorunent due to Loss of Coolant Accidentj LOCA)

MSLil SijPPI.I Fk 2 x 10" rads ENVIRONMENT TO.Wil!CH EQUIPMENT IS QUAL.lFIED Same as above ACCtfRAC_Y_REQUIRFMENTS Loss of Cool.snt Accident (LOCA)

P.0: Not Required 2x 10s rads

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NA-l'115 Fl}N(.T ION Supplies Power to Safety Systems I.nCATION Outside Containment I.IAUb UU:

NGA-4,'l/c 500 tICH NCA-14, Triplex 4/0 AWG NGA .1, Triplex 1000 tlCM N GA - l 'l , 3/c #4/0 AWG

Ila qualification and Evaluation (Cont'il)

QUALIFICATION DEFICIENCIES QUAI.!FICATION DOCIIMENT AND RECOMMENilED S01.UTIONS MANNER OF QUALIFICATION IDCA l.OCA I.OCA Test Okonite's Engineering Report A. Delicienrics:

0'I'I_i t {gn_a l_, yulipo_[tj ngp2,r jacn_is None Outline of Franklin Institute kescarch Laboratory Report F-C1694 IEEE Transaction Paper T74 044 4

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12 Qualification and Evaluation FAUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS 600 V Alum. Power Cable Loss of Coolant Accident (IACA) thCA MANUFACTURER 280 F 0 to 30 min 120 days @ 150 F Reduce from 280 F Okonite tog 50*F 30 to 60 min OPERABILITY DEMONSTRATED Jacket: Neoprene 150 F >60 min Insulation: Ethylene Propylene Rubber 45 psig 0 to 30 min Reduce from 45 to SgPLIER 0 psig 30 to 60 min 0 psig >60 min Same as above 4.8 x 107 rads M: Spray: 0-4 hrs Solution of boric acid (2,000 - 2,100 ppa boron)

NA-1384 buffered to a pH of 8.5 to 11 with NaOH. >4 hr similar solution with a pH of 7 to 9. PostLOCAthermalaggngisgreater than 2.9 years 0 150 F Main Steam Line Break (MSLB)

FUNCTION Will not see a changing environment due to MSLB.

ENVIRONMENT TO WHICII EQUIPMENT IS QUALIFIED ACCURACY REQUIREMENTS Supplies Power to Safety Systems IACA* Not Required ,

304 F - 3 hr 20 min Inside and Outside Containment 346 F - 4 hr 27 min 256 F - 1 day MARK No. 212 F - 100 day 259 F - 10 hrs NGB-5, Triplex 500 MCM 324 F - 4 hrs NGB-7, Triplex 250 MCM 252 F - 7 4:ys NGB-11, Triplex #2/0 AkG NGB-12, Triplex #1 AWG Aged 168 br at 121 C Irradiated to 2 x los rads PWR Exposure:

324 F at 80 psig 0 to 4 hr 252 F at 16 psig for 7 days Spray: 0-4 hr Solution of boric acid with NaOH to a pH of 10.5 throughout the PWR exposure period.

• The same cables that had been exposed to the PWR accident conditions were then exposed to the BWR simulated accident conditions.

12a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLLTIONS

@ LOCA IDCA Test - Sequential Okonite's Engineering Report A. Deficiencies No. 141 dated February 29, 1972 None Additional supporting Documents Outline of Franklin Institute Research Laboratory Report F-C3694 IEEE Transaction Paper T 74 044 4 t

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I 13 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS 300 V Instrument Cable Loss of Coolant Accident (LOCA) y MANUFACTURER 280 F 0 to 30 min 150 F for 120 days Reduce from 280 F 30 to 60 min Cerro Wire and Cable to 150 F MSLB Jacket: Neoprene 150 F >60 min insulation: Cross-Linked Polyethylene 45 psig 0 to 30 min 140 F for 120 days Reduce from 45 to 30 to 60 min SUPPLIER: O psig OPERABILITY DEMONSTRATED (2}

O psig >60 min Same as above 4.8 x 107 rads (1) IM P&, Spray: 0-4 hr solution of boric acid 30 days at or above 212 C (2,000 - 2,100 ppm baron) buffered to Post IOCA Thermal Aging is equivalent NA-1392 pli of 8.5 to 11 with NaOlt >4 hr similar to 320 days e 150 F.

solution with a pH of 7 to 9 FUNCTION Main Steam Line Break (MSLB) MSLB

1. Containment Isolation See above

2. Emergency Core Cooling / Core Ifeat Removal

3. Engineered Safety Feature 430 F 0 to 20 min ACCURACY REQUIREMENTS

4. Post Accident Monitoring 280 F 2 to 60 min

5. DBA (LOCA or MSLB) Mitigation 150 F >60 min MSLB

6. Service Building liabitability 45 psig 0 to 30 min Reduce from 45 to 30 to 60 min Not Required LOCATION O psig 360 min 3 x 10 rads (1) 7 Inside and Outside Cont.sinment LNVIRONMENT TO WilICll EQUIPMENT IS QUALIFIED MARK NO.

LOCA NGA-67, 19/c No. 16 AWG NGA-68, 12/c No. 16 AWG NGA-70, 18/c No. 16 AWG Aged 1,300 hr @ 150 C NGB-35, 2/c No. 16 AWG Irradiated to 2 x los rads NGB-39, 3/c No. 16 AWG 280 F @ 70 gsig 0 to 10 sec Rise to 346 F @ 10 sec to 5 min 113 psig Reduce to 140 F 5 min to 3 hr 280 F (* 70 gsig 5 hr to 5 hr & 10 see Rise to 346 F 5 br & 10 see to 5 hr & 5 min 346 F @ 113 psig 5 hr & 5 min to 8 hr 335 F @ 93 psig 8 hr to 11 hr 315 F @ 69 psig 11 hr to 15 hr 256 F @ 28 psig 15 hr to 4 days 212 F @ 0 psig 4 days to 30 days

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I .la Qualification and Evaluation (Cont'd)

DESCRIPTION OF ENVIRONMENT (Cont'd)

Spray:

Ist 24 hr of 30 day perioil - solution af the following composition:

0.28 molar 11 3B03 0.0t,4 mola r Na 2S0 2 3 NaOH to make pH between 9-11 Following above 30 day LOCA period, an additional period of 100 days at 200 F.

MSLH Same as above QUALIFICATION DEFICIENCIES AND RECOMMENDED Sol.trflONS t}Af'n.R_RQUAl.l f it.AT !ON QUALIFICATION DOCt! MENT IUCA LOCA INCA Test - Sequential Rockbestos (formerly Cerro) A. Deficiencies letter dated 2-21-79 and its attached report Nog MSI.H MS[8 MS(B - Comunent Temperature Analysis FSAR Section 3C anil response to Comment 7.17 Qualification base on independent Rockbestos letter dated 4-25-77 test and analysis.

LOCA qualification dornment ca h of the qualification parameters (obtained from independent test and analysis exceeds the corresponding MSLB requirements.

Maximum calculated surface t emperature during limiting MSLB in 341 which does not exceed qualification ter.perat,'re of 460" given in Rockbcstos (f. w ely Cerro) letter dated 4-25-77. Pressure and Radiation - Test Refer to I.OCA Qualitira-tion

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Redure from 280 F to 150"F 30 to 60 min General Cable 150 F >60 min OPERAlliLITY LENONSTRATED

. Jar ket : Neoprene 45 psig 0 to 30 min Insulation: Ethylene Propylene Rubber Reduce from 45 LOCA to o psig 30 to 60 min SitPPLIER 0 psig >60 min 163 hr 6 260 F 4.8 107 rads (l)

Same as above Srpay: 0-4 hrs. Solution of boric Post LOCA thermal aging is equivalent aci.1 (2,000-2,100 ppe boron) buffered to 490 days el50*F IM). to a pH of 8.5 to il with NaOH. >4 hrs similar solution with a pit of 7 to 9. ACCIIRACY REQLIIREMf;N_TS NA-1256 Nain Steam Line Hreak (MSLB) LOCA FilNglON Will not see a (hanging environment due Not Required Supplacs Power to Safety Systems to HSLB.

ENVIRONMENT TO WillCil EQLIIPMENT IS QUALIFIED IpCATIO_N iga Inside and outside Containment Irradiated to 5.5 x 107 rads ilAkW No. 100 psig 0340"F for 4 hrs 62 psig PJ10"F f or 1 hr NGil-5, Tripicx 500 HCH 20 psig 0260"F for 43 hrs NGil-1. Triplex 250 NCH 2.5 psig 0260 F for 5 days NGil- 1 I , l*riplex 2/4 AWG NGis-12 Triplex #1 AWG Spray: Throughout test cycle solution consisting of a 2,000 ppm solution of boron as horir acid buf f ered with NaOli to a pil of 9.0 8

Irradiated an ad.litional 1.45 x 10 rads bringing the total exluisure to 2 x 10" rads.

ym I i I G J 14a Qualification and Evaluation (Cont'd)

QllALIFICATION DEFICIENCIES HANNERsp], QUALIFICATION gllAl.lFICArlON DOCllMENT AND REOW1 ENDED SOLtrrlONS I.DCA I.OCA IACi.

Test - Sequential General Cable I.etter dated 12-22-71 A. Deficiencies:

Qaalification Document is in letter form.

The letter is a sessunary of the nuclear environment tests per-foraud on cables of a similar const ruction, which General Cable has stated are applicable.

B. Solution:

1.ctter has been sent to supplier requesting a copy of test report s or arrangement s made for an audit of qualification data.

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(.j; 15 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Operated Valves Loss of Coolant Accident (LOCA) LOCA NANUFACTURER s 5 x lo rads (based on 120 day LOCA). SOV will perform its function of In addition, the 40 yr radiation dose closing isolation valve within Automatic Switch Company of 4 x 10' rads must be considered for 60 see of receiving signal.

Model #HB-830281U a total possible radiation dose of 5.04 x 10' rads. OPERABILITY DEMONSTRATED SUPPLIER ENVIRONMENT TO WICH EQUIPMENT IS QUALIFIED J LOC Same as above LOCA SOV perfcrmed required safety function P.O. after receiving radiation dose.

8 Valves not specifically tested to 5.6 x 10 rad integrated dose. When exposed to 5 x 107 ACCURACY REQUIREMENTS

. d, leakage developed which exhausted the FUNCTION prem ure vessel. Solenoid valves will have Not Required achievo* safety-related function within 60 Containment Isolation see of an initiation signal. T e long term failure mode will not reintroduce air to a LOCATION control valve, therefore, the valve will main-tain its fail safe position.

Auxiliary Building Zone C MARK NO.

SOV-DG-200A Primary Drain Transfer Pump Discharge

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, 15e Qualification and Evaluation (Cont'dl QUALIFICATION DEFICIENCIES

. p R OF QUALIFICATION QUALIFICATION DOCUMENT AND REC 0t9 TENDED SOLUTIONS-LOCA^ TACA IDCA

. Test Franklin Institute Research" A. Deficiencies:

Laboratories (FIRL) Test

- Report F-C4539, Failure during radiation exposure.

Catalog #30, Westinghouse letter B. Solution:

MS-557706 When exposed to a radiation dose of 5 x 107 rads, some plastic inards of the SOV did desintegrate causing the valve to leak. However, the i

valve was able to exhaust its accu-mulated pressure and perform its j safety function. (W letter i NS-5577060).

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16 Qualification and Evaluation EQUIPitENT DESCkiPTION DESCRIPTION OF ENVIRONMENT OPFRADILITY REQUIREMENTS 600 V Cu Power Cable - He.st Tracing Loss of Coolant Arci. lent (LOCA) IDCA HANUPACTUkEN 280 F 0 to 30 min 120 days it 150 F H i e from 280 F Okonite to 150 F 30 to 60 min OPERABILITY DEMONSTRATED

" ~ ~ ~ - ~ ~

Jacket: llypalon 150"F >60 man l usu l .s t i on : Cross-linke.1 Polyethylene 45 psig 0 to 30 min l_DCA_

Reduce from 45 SUPPL.!ER to O psig 30 to 60 min 27 days 612I2"F 0 psig >60 min Sane .ss above 4.8 s 107 rads Post 1.OCA thermal aging is equivalent Spray: 0-4 hr Solution of horic to 291 days 64 150 F P.O. ari.I (2,000-2,100 ppe loron) huffered t o a pit of 8.5 to it with NaOH. >4 hr NA-1404 similar solution with a pH of 7 to 9.

FilNCTION Hain Steam Line Hrcak (MSLB)

Supplies Power to Safety System Will not see a changing environment a changing environment due to NSLit.

I.OCATION ENVIRONMENT TO WillCll EQUIPM_ENT IS QUAL.lFIED fuside .sud out s i le Cont a inment IDCA HARK No. Aged 14'd.sys at 250 F frradiated tn .5 x los rads an.1 aged NGH-ol, 2/r #10 AWG at 240 F lur 7 days For 31 days perimi 280"F/ 70 ps,i,g 0 to 10 ser kisc to 346 F/

113 psig to see to 5 min 346 F/113 psig 5 min to 3 hr Reduce to 140 F 3 hr to 5 hr 280"F/70 psig 5 hr to 5' hr and to see Rise to 346"F/ 5 hr and 10 see to 113 psig 5 hr and 5 min 346"F/Il3 psig 5 hr and 5 min to 8 hr 335"F/95 psig 8 hr to 11 hr 315"F/69 psig 11 hr to 15 hr 265"F/28 psig 15 hr to 4 day 212"F/0 psig 4 day to 31 day

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164 Qualification and Evaluation (Cont'd)

DESCRIPTION OF ENVIRONMENT (Cont'd)

Spray: Continuously for 31 day period solut ion of 2,000 ppe boron as l'oric rid huf f ered with NaOh to a pil to 9-11. Irr.s.fiated to 1,5 x 10 rads during the 31 day period. Total 2 x los r.sda .

QUALIFICATION DEFICIENCIES HANNEk 0F yl!AI,lFjCATION gllALIFICATION DOCUMENT AND RF.C0ttMENi>ED SOI.trl'80NS LOCA IJDCA LOCA Sequential Franklin Insit ut e Reasearch Lal> oratory A. Dejiriencies,:

Report F-C3694 None Aitditionsl SugygLt,ing_ iia [a IEEE Trans.iction Paper T 74 044 04

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17 Qualifiratinn anit Evalu.ition Equit'flENT Dr.Sritil'floN DFSCRIPTION OF ENVIRONMENT Ol'ERAHil.lTY REgt JtREMENTS Hotor operateil valve H. sin Steam Line Break (MSLB) in Terbine Buililing MSI.B in Tushine_Hu giliepg HANilFAC'! UREN 1. High ambient temperature 211 F inr 30 min - 211 F and 1001 Ril duration of steam elischarge in Filiot G.mpany vicinity of chiller room air OPF_RAHill]Y DEMONSTRAT.ED Hod. l #f TAR 2's inntakes - 30 min.

MSLB in Tierbine Huilding Sul Pl.ll.R 2. Ifigh ambient moisture content satur.sted steam, 1001 Rif for None S.une as above duration of st.eam discharge 30 min.

P . O ., ENVIRONMENT TO WillClf EQUll' MENT ISXAI.lFIED ACCl!NACY_REQUlHENENTS NA-1299 HSI.H in Turbine Buililing Not Required ItyCTION None Cont rol Room liabitabilit y IDCATION Service lluilding, Zune J MARK _NO.

NOV-liv- I I's- 1, Flinii Valve f.elt for Strainer HOV-IIV-Il5-2, Flush Valve Right for Strainer NOV-IIV- I l 6- l , Flush V.elve f. cit for Strainer HOV-IIV-Il6-2, Flush Valve lii gh t for Steainer w - -- -_ m-. m_ _

U(b f) t v Ela Qualification and Evaluation (Cont'd)

QilALIFICATION DEFICIF.NCIES MAN _NFit isF_yllALIFICATION QUALIFICATIONIUCllMF.NT AND REC &1 MENDED SOLIITIONS NSI.it in Tushine Itu i l.li ng MSI.B in Turbine Building MSt.B in Turbine fluilding None None A. Deficiencies:

1) High ambient temperature 28t"F

2) Saturated atmosphere B. Solutioni in the event of a MSt.B in either turbine building and the correspond-ing teilure of a main steam stop valve to shut, temperature in the control room A/C chiller room will approach 180"F at 1007, relative humidity due to steam blowdown entering the chiller room. A/C chiller systems are not qualified to withstand these environ-mental conditions.

In order to maintain habitable temperature in both units' control room under the above conditions it is necessary to operate two A/C chillers in the unaffected unit.

Continued operation of linit 2 can be justified on the basis of alw.sys having two Unit I A/C chillers, one Unit I emergency diesel gener,atur .end the two Unit I emergency tenses . avail-able. Since the analysis assumes a main steam trip valve fails to shut no other single failure need be postulated per Regulatory Guide 1.81.

Theref ore, only one !! nit I diesel generator need be .svailable to operate two A/C chillers (this resguires tying escrgency lusses Ill and IJ).

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18 Qualifaration and Evaluation IllHI!'H! NT ljhSC$lglpN Df1CFJ g,[j[N OF ENVIRONMENT of'ERAnil.lTY RFylllREMENT_S Centrilugal Fans Loss of Coolant Accident (l.OCA ) IJ)CA NANUFACTlHF.R I. Radiation zone IV 40 yr dose + 1.04 x 103 rads 1/>CA dose = 880 + 160 = 1,040 rads tiollato Fu r r.c Corpany No.le l e,80b lo lG51 ENVil;ONNENT TO k'lllCII F.QUIPHENT IS QUAI._lFIED OPER_A!!!I.lTY_DEMONSTRATElj SUPPI.lER I.OCA I.OCA Saa.c as al.uve Radiat ic.n dose of 7 x 104 rads 7x 104 rads P 0- A CCURACY RF. QUIRT.NENTS NA- 12% Not Required tll_!Ng ION Safeguarils Area Ventilation IDCATION Anxiliary linilding Zune il UARE_NO-2-HV-F-40A, S.steguar.1 Area Ventil.stion 2-IIV- F-40 H , S.ileguard Area Ventilation l

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18a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES ttANNF.H OF QUALIFICATION Q(IAI.lFICATION Ix)Ct' TENT S AND RECOMMENDED SOLilT10NS lhCA thCA IACA W-n.her's seply to TLX inquiry TLX-3-29-79 W.11. Shumacher None J. E. Krethting COtetENT Letter has been sent to supplier requesting copy of test report or arrangement made for analit of recos-ds at vendor's plaut.

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19 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Polysulfone Terminal Blocks Supplied kith Loss of Coolant Accident (LOCA) _LOCA Reactor Containment Electrical Renetration -

CONAX 280 F 0 to 30 min 120 days 150 F Reduce from 280 F PLtNUFACTURER toj50F 30 to 60 min MSLB 150 F >60 min Connection Inc. 45 psig 0 to 30 min 120 days @ 150 F Model NSS3 polysulfone Reduce from 45 t6 0psig 30 to 60 min OPERABILITY DEMONSTRATED SUPPLIER 6.8 x 10 rads LOCA & MSLB Conar Spray = 0 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> solution of boric acid (2,000-2,100 ppe boron) buffered Low Voltage Power / Control / Instrumentation PA . to a pH of 8.5 to 11.0 with Naoll. Beyond 255 F - 190 hr 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> simlar solution with a 7 to 9.

NA-1313 Post LOCA thermal aging is Main Steam Line Break (MSLB) equivalent to 429 days @ 150 F FUNCTION 430 F 0 to 2 min ACCURACY REQUIREMENTS Supplies Power to Saf ety Systems 280 F 2 to 60 min 150 F >60 min Not Required 45 psig 0 to 30 min Reduce from 45 LOCATON to O psig 30 to 60 min 0 psig >60 min Inside Containment 3.4 5 104 rads 40 yr dose MARK NO. ENVIRONMENT To killCH EQUIIt!ENT IS QUALIFIED N/A LOCA Radiation: 2.5 x 107 rads minimum 253 5 @ 25 psig 0 to 30 sec 282 " @ 45 psig 30 to 60 sec 285 F @ 45 psig 60 to 90 sec 298 F @ 57.5 psig 90 to 120 sec 282 E @ 48 psig 2.5 to 4 min 289 F @ 49 psig 4 to 5 min 300 F @ 56 psig 5 to 10 min 293,F @ 47 psig 10 to 15 min 297 F @ 47 psig 15 to 30 min

m s 19a MANNER OF QUALIFICATION ENVIRONMENT TO WHICH EQUIPMENT IS QUAllFIED (Cont'd)

LOCA & MSLB Range Test Thermal aging 300 F for 74 hr SEL*I:

Solution boron 1,900 ppa Buffeged to 7.7 pH at a

+ 190 F, 10 gpm for 30 mia.

140 F @ psig for 240 hr QUALIFICATION DEFICIENCIES QUALIFICATION DOCIMENT AND RECOMMENDED SOLITTIONS Conax Corporation Test LOCA Report IPS-107 A. Deficiencies Conax letter " Qualification of Electric Penetrations" Test solution - 1,900 pre vs No. IPS-411, P/N 7280-10001-01, 2,000 - 2,100 IPS-369, IPS-325 dated 1/5/80 B. Solutions Letters from Union Carbide, Belgium, N.J., dated 12/19/67, LOCA New Jersey, dated 1/22/68 The terminal block is of a polysulfone Stone & Webster Calc. #11715-ES-169-0 material which has been shown to be dated 3/10/77. resistant to all diluted alkaline solu-tions. Therefore, we believe that since the LOCA spray is in the range of a diluted alkaline solution, it should have no significant effect on the terminal blocks.

MSLB A. Deficiencies

1. Does not meet maximum temperature for MSLB B. Solutions

1. Temperature qualifications accep-table since temperature reduced to 280 F af ter 2 min, due to thermal inertia, internal temperature rise stay within qualified limits. See Temperature Calculation Document Reference #ES-169.

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[ QUllffENT, DI.SC,ki PTION DESCRIPTION OF_ENVIRONMFE OITRABIL_ITY, HF,yl]IREME NTS I.evel Transmitters Imss of Coolant Arcident (!JDCA) LOCA & Main Steam Line Break ( MSI.h )

MANltFACTUltER

" ~ ' ~ ~ ~ ~

280"F 0 to 30 min 120 days 61 150*F keduce from 280 F I)claval Turbine, Gems Sensor Division to 150"F 30 to 60 min OPERABILITY DEMONSTRATE!)

- - - ~ ~

Hodel Cens #XrI-29400 150"F >60 min 45 psig 0 to 30 min IM.A & MSI.H StjtPIM.R Redure frum 45 to O psig 30 to 60 min After test, f.ransmitter functioned Same as abuse O psig >b0 min properly. Manufacturer's norm.sl 4.8 s 107 rads environment is rated to 300"F.

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Spray - O to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> solution of boric ACCURACY REQUIREMENTS NA-13.13 arid (2,000-2,100 pre boron) buffered to a pit of 8.5 to 11.0 with NaOH. IDCA & MSLI) p l%CT ION licyowl 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> similar solution with a 7 to 9. 35% of range Post Accident Honitoring MSI.11 ACCURACY DEMONSTRATED 1.OCATION

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430 W 0 to 2 min IJDCA & MSLB Insi.fe Containment 280 / 2 to 60 min 150 F >60 min 1.4% af ter test H_ANK, Ng. 45 ps.". O to 30 min Redun from 45 LT-RS251A Containment W. ster Level to O psig 30 to 60 min LT-RS25111 Cont ainment W. iter Level O psig >60 min 3 x 10' rads 40 yr dose ENVikONNENT To WillCil EQUl_lffENT IS_ QUALIFIED IJDCA (FIRL Test) 282t"F 0 to 60 min 2801450"F >60 to 180 min 150"F 180 min to 14 days 45 psig 0 to 60 min 45 0 psig >60 to 150 min 13.4 psig 150 min to 14 days 8

R.i.fiation Exposure 2 x 10 rads (Isomedix fur.)

Sprav - 15,000 pre borir acid buffered to a pil of 10.5 with NaOH solution for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Spr.ay density = 0.15 gre per itz,

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ENyiRON!H,NT TO Mt!C[1,fyl]I_pMENT IS QtJALIF1FD (Cont'd)

MSI B As ab..we QtlALIFICATION DEFICIENCIES MANNEN OF,sjtlAl IFICATION OljAI.lFICATION IMmtENT AhD RFCOMMENDED SOLl!TioNS thCA & MSI.B IDCA & MSI.B LOCA FIRL Test - Sequent i a l R4. fiat ion Franklin Institute None and Envi r onment.nl t.xposure Rese. arch Laboratories (FIRL)

Report F-C3834 MSI.B Isomedix Inc. Test - Sequential Envirorumental .and Spray Exposure Isomedix Inc. Test Report dated A. Defiriencies:

November 1975

1. Test Temperature ut 2H2"F is below accident tempes.ature of 430 F

2. Spray not performed on same R. Solution:

1. As measured by thermorouple on circuit board, internal components reached qual *tscation temperature 282"F only .3ter 27 minute exposure to 450 F.

Actual required exposure at 450"F is 2 minutes, thereforr, qualification is satisfattory.

2. Effect at spray must be determined.

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21 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Aalal Flow Fans Loss of Coolant Accident (LOCA) LOCA MANLTACTl'RER Radiation 40 yr dose - 5 x 10' rads 5 x 10s rads Joy Manufacturing Company Model #600263-5533 SUPPLIER OPERABILITY DEMONSTRATION Same as above ENVIRONMENT TO MIICH EQUIPMENT IS QUALIFIED LOCA P.O.- IDCA None NA-1201 None FUNCTION Safeguards Area Ventilation LOCATION ACCURACY REQUIREMENTS Safeguards Building Not Required MARK NO.

i 2-HV-F-71A, Ventilation - Safeguards Area 2-HV-F-71B, Ventilation - Safeguards Area

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21a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES l

MANNER OF QUALIFICATION QUALIt'ICATION DOCUMENT AND RECOMMENDED SOI.UTIONS i LOCA LOCA IDCA l Ncne None Deficiencies Equigeent not qualified for exposure to:

Radiation - 5 x 10" rads I

Solutions Replace drivers with qualific.1 motors Replacement motors have ucen purchased capable of withstanding the radiation dose of 5 x los rads.

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KA 22 Que .fication and Evaluation EQUll11} NT IW.SCRIPTION DESCkiPiloN OF ENVIRONMENT OPERARILITY REQUIREMFNTS Hutor Control Centers Loss of Coolant Arrident (LOCA) IDCA MANtit;A_Cll:kERS 1x 10 6rads (based on 120 day LOCA). 1.04 x 10 8 In adilition, the 40-year rads must t>e Klockner Hueller consndercel f or .s total possible radiation dose of 1.04 x 10 8 rads.

Sl[lf1._I ER Same as above Main Steam I.ine Itreak (HSLB)

P.6.. Wil. not see a changing environment due to OPERARILITY DEMONSTRATED HSLB NA - I l ?t> LOC _A, FUNCTION ENVIRONMENT TO k1lICII EQUIPNENT IS_ QUALIFIED I.4 x 108 rads Supplies Power to Safety Systems IDCA Minimum total integrated dose of 1.4 x l # rails of gasuna source radiation.

ACCURACY REQUIREMENTS I.OCATION

~ ~ ~ ~ ~

Not Re<guired Auxiliary fluilding Zone f LI'% .N9-Hotur Control Centers 2-EP-NC-19 HCC-2111-2N 2-EP-HC-20 NCC-2ill-2S 2-EP-NC-21 tiCC-2Ji-2N 2-EP-HC-22 HCC-2J1-2S l

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QUALIFICATIOni (4.FICIEhCIES fiu3tR (T_4flALIFICATION OUALIFICATJoM IKIMENT MD kLffeetEADED SottJTICAs l

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3/16/79 See Qualification Deficiencies Qualif' ration document is in letter form (i.e. o<. toraat test

, report with approved i ssgnature and date) l B. Solutnons:

Letter has been sent to supplier requesting j copy of test report, or arrangement made for audit of records at ven. tor's plant.

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' s 23 Qualification and Evaluation LQtillt1FNT isESCRil" TION DESCRIPTION OF ENVIRONMENT OPERABILITY RfYp11REMENTS Hotor OpriatcJ Valve Loss of Coolant Arriaient (LOCA) ll)CA MANUFAtTirNLR 5x 10 8rads (based on 120 days) 5.00 x 10" rads 40 yr dose negligible.

Limi t orepac OPERABILITY DEMONSTRATED Operatur - Reli.ence Class B lasulatson ENVikONilENT T* k1llCH EQUIPMENT IS Qt!AI.lFIED MO sifrPLitk WA See Qualification Deficiencies Same as aluwe 40 yr integrated - 2 x 10s rada 2x 10" rads 11 0 ACCURACY REr;*llREMENTS NA-1242 Not Required FilNL'TiuN

1. Engineerrel Safrty Feature

2. DHA (LOCA) Hitigation l{yATION Safeguar.is Area (L\H5_N%

tt)V-QS-201A, Quenth Spray Pump Discharge th iV-90-20 llt, Quench Spray Pump Discharge Ptov-RS-255A, Recirculation Spr.sy Sustion MOV-RS-2% R, ket Trt ulation Spray Suction floV-RS-256A, Recirrulation SprJy DisthJrge iklV-RS-2560, Recarrulation Spray Dire'harge

23a Qualification and Evaluation (Cont'.1)

Qt!AllFICATION DEFICIENCIES PL)NyEN OFJIAl.lFit:ATION QtiALIFICATION DoCitlENT AND kECitf1 ENDED SOLintoNS INA LOCA If_CA - Comments Test Limiturque llave supplied Limitorque with the serial Report No, h0003 and work order numbers. Limitosque is in the process et .letermining st-l.clule for 2.0 x 10" rads gesuma saliation p rov i d a ng. information if supplie.1 mL 1somedix, Inc. Parsippany, N.J. equipment wa ll f all under the ref erent ed

.locument.

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T V O 24a Qu.aliferation and Evaluation (cont'd)

QUALIFICATION IWFICIENCIES tt\NNtk OFMt'ALIFirArlON ([UAllflCATION DOCUt!ENT AND REttet* FENDED SOLUTIONS IDCA IDCA LOCA Priwtration .nssemblics were tested by Conax report "ttaximum Emergency A. Deficiencies:

using .s prutotype wit h chas.orte ristit s Environmental Test Repott for pce t a nwet t o eac h a niti vsitual t ype. Elettric.sl Penetration Assemblics" I. pil of' chemiral spray was 5 Thas w.es liest expose.1 tu radiation No. IIP 73.4 dated 5/l3/75 to 8 for duratit..*, not 8.5 then pressure anel temperature an.1 t o 11.0 f or l o r st 4 hr or fin.sily themeral spray. R.s.liation Test almaraz service 7.0 to 9.0 fur rem inter test conax report IPS-137.

2. Temperature range was 146" to 170 i s om I h r t o en.l not 150" B. Sol _utinns:

1. The cler scal penet rat inn Conax let t er "Quali fication of assembli 2 are l atir i ca t ed Elettrat Penetrations" f roen t h. following non-No. IPS-4tl, P/N 7280-10001-01, metallir .satessals; poly-IPS-3tM. IPS-325 dated 1/5/R0 imides anel polysulfone.

These maters.ils have been shown to be resistant to

,all ilsluted alkaline solu-tions. Theref ore we lu lieve that since t he IJKM spray a s in the range el a diluted alkaline solution it shoul.1 have no signitisant ettett on t he penet rat ion assemblics.

2. Very short dur.stion of ten-perature Lelow 150" when compascal to t u t .e l test duration m.akes this item acceptahic.

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24 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPEPABILITY REQUIPEMENTS Penetration Assemblies Loss of Coolant Accident (LOCA) Q MANLTACTURER 280 F 0 to 30 minutes 120 days @ 150*F Reduce from 280 F Conaz Corporation tof50F 150 F 30 to 60 minutes

>60 minates OPERABILITY DEMONSTRATED St'PPLIER 45 psig 0 to 30 minutes LOCA Reduce from 45 to Conax Corporation 0 psig 30 to 60 minutes 225 F-190 hrs 6.8 x los rads P.O. -ay: Post IDCA thermal aging is

.- brs solution of boric acid (2,000- equfvalentto429 days @

NA - 1313 2,100 ppa boron) buffered to a pH of 150 F 8.5 to 11.0 with NaON beyond 4 bra WNCTION similar solution with a pH of 7 to 9. ACCURACY REQUIRE *fENTS Supplies Power to Safety Systems ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED Not Required E

IDCATION Pressure and Temperature Inside containment, outside Pressure 45 psig @ 280"F 0 to 30 minutes cranewall and Auxiliary Building. psig to O psig 0 to 30 minutes Zone F Decrease from 45,F 30 to 60 minutes and280Fgo245 150 F + 20 F @ 0 psig I br to 10 days MARK No. or 150 F - 4 F @ 0 psig Type IA - Instrumentation Radiation IB - Control

10. IIA, IIB, IIC, IID and I x 10' rads gamma radiatior. minimum IIE - Low Voltage Power III - Triaxial Chemical Spray:

IV - Thermocouples From 0-30 minutes. No chemical spray was introduced from 30 minutes to 10 days assembly was subjected to spray solution: Boron content was .23 molar as H B03 3 NaOH = 5.0 to 8.0 Note:

MSLB environment and qualification continued on page 25.

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24a Qualification and Evaluation (cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCLMEh7 Aht RECOMMEhtED SOLL710NS lhCA IJDCA LOCA Penetration assemblies were tested by Conax report " Maximum Emergency A. Deficiencies:

using a prototype with characteristics Environmental Test Report for pertinent to each individual type. Electrical Penetration Assemblies" 1. pH of chemical spray was 5 This was first exposed to radiation No. IPS-73.4 dated 5/13/75 to 8 for duration, not 8.5 then pressure and temperature and to 11.0 for first 4 hr or finally chemical spray. Radiation Test almaraz service 7.0 to 9.0 for remainder test conax report IPS-137.

2. Temperature range was 146*

to 170 from I hr to end not 150*

B. Solutions:

1. The electrical penetration Conax letter " Qualification of assemblies are fabricated Electric Penetrations" from the following non-No. IPS-411, P/N 7280-10001-01, metallic materials; poly-IPS-369, IPS-325 dated 1/5/80 imides and polysulfone.

These materialm have been shown to be resistant to all diluted aikaline solu-tions. Therefore we believe that since the LOCA spray is in the range of a diluted alkaline solution it should have no significant effect on the penetration assemblies.

2. Very short duration of tem-perature below 150" shen compared to total test duration makes this item acceptable.

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26 Qualiferation and Evaluation EyullHENT 11SCHitTION DESCRIPTION OF ENVIINMfENT OPERARILITY REQUIREMFEIS Splires (Field and Factory) .sb part of less of Coolant Accident (IDCA Loss of Cooland Arciefent (LOCA) penetration assemblics 280"F 0 to 30 min 120 days @ 150*F PLANT!FACTUkER keduce from 280 F no F 30 to 60 min CONAX Corp. 150*F >60 min OPERABILITY DEMONSTRATED insulatson: Karton 45 psig 0 to 30 man Reduce from 45 to Loss of Coolant Arcident (LOCA)

SilPPLIER 0 psig 30 to 60 min 0 psig >t,0 min 10 days @l46 F Same as above 6.8 x IOS rads Spray: Post IDCA operations do not meet O to 4 hrs solution of boric acid operability requirements P . fl.

(2,000-2100 pgw boron) butfered NA-131) to a pH of 8.5 to 11.0 with NaOli beyond 4 hrs similar solution with ACCtIRACY RE(pIREMENTS H'NCTION a pil ot 7 to 9 Not Required Sugirlies Power to Safety Systems (used fur terminating cables at penetratnons) I.NVIRON*tFNT To bli!CH EQUIIHENT IS OPl.t.lFIED IDCAIION LOCA Inside s ontainment , outside cranewall Spray - From 0+ -240 hr spray continuously

,an.1 Auxiliary Building wi*h a solution of the following contents:

Zone F Boron content = .23 molar (1,900 l'lH)

HWK NO_.

NaOli content = 10 to 4 x 102 MOLAR Pil = 7. 7 to 7.8 N/A 280 F @45' psig 0 to 30 min Reduc e from 45 to O psig 30 to 60 min Reducc f rom 280 F to 144 F Raised from I40 F 30 to 60 min 150*F I to 240 hrs 1x 10" rads gamma radiation,minimus Note: MStit environment and qualification continued on page 27.

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,f QI '%J 264 Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES ttANhEk OF ytfAL1FiCATION (f!A_LQiCAT!ON l[CL9tFNT AhD REC _OrtMENIA D_S011TI(JNS M (M INA Splices were made using various representative Conas Report " Test Procedure and Report A. Deliciencies:

cahic t yges and sizes wisich had l>ccu at tac hed on Electrical Termanations Suhjected to a prototype penetration assembly. The t o Design Basis Accident Environment" 3. Chemical spray solutsi,n had prototype was first suljected to radiatius No. IPS-107 dated October 5, 1973 pH of 7.7 to 7.R not 8.5 to exposure, then temperature, pressure and 11.0 for first 4 hr.

<!weiral spray roucurrent ly. kadiation: Almaraz Service Test 2. Temperature below 150" tu 140 +

Conas Report IPS-137 on various occasions .turang test

3. Time, temperature envelcaw not adequate Conan letter " Qualification of B. Solutions:

Electrical Penetrations" No. IPS-411, P/N 7280-10001-01, 1. The Penetration splicing IPS-369, IPS-325 dated 1/5/80 maternal is a polyotelie.

material which has licen shown to be resistant to all diluted alkaline solu-tions. Therefore we believe that since the LOCA spray is in the rarge of a dilute.1 alkaline solution at should have no significant etfcct on the spiace material.

2. Overall temperature was within test tolerances.

3. The splices are atualified for 120 days 48 150"F per Canas letter "Qualifata-tion of Electrical Penetia-tions " ho. IPS-4tl, P/N 7280-10001-01, IPS-3h9, IPS-325, dated I/5/80.

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27 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Splices (Field and Factory) as part of Main Steam Line Break (MSLB) 120 days @ 150 F pentration assemblies 430*F 0 to 2 min MANITACTl!RERS 280 F 2 to 60 min OPERABILITY DEMONSTRATED 150 F >60 min Conax 45 psig 0 to 30 min MSLB Insultation: Kapton Reduce from 45 to O psig 30 to 60 min 255 F - 190 br SUPPLIER 0 psig >60 min Post LOCA thermal aging is 3.4 x 104 rads 40 yr dose equivalent to 429 days @ 150 F Same as above P.O. ENVIRONMENT TO MIICH EQUIPMENT IS QUALIFIED ACCURACY REQUIREMENTS NA - 1313 MSI.B MSLB FUNCTION Raisefrom109F Not Required to 253 F 0 to 30 see Supplies Power to Safety Systems Raise from 253 F (used for terminating cables at to 290 F 1 to 2 min penetrations) 282 F 2 to 30 min 44 F LOCATION Range}F to 294 30 to 60 min Rangeg40F Inside Containment, Outside Cranewell and to 150 F >60 min to 240 hr Auxiliary Building 0 to 24 psig 0 to 30 sec Zone F 45+ psig 1 to 30 min 0 psig 30 min to 240 hr MARK No. 2.5 x 107 rads gamuna radiation minimum N/A NOTE: Temperature qualification by analysis per Qwlification Document No. 2. (See Page 21a) thCA environment and qualification continued on page 26

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27a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNEN OF QUALIFICATION QUALIFICATION Doct! MENT AND RECOtt* TENDED SOLUTIONS MSLB MSLB MSLB Splices were made on various 1. CONAX Report " Test Procedure and A. Deficiencies:

representative cable types and Report on Electrical Terminations sizes which had been attached Subjected to Dcsign Basis Accident Pressure excursion was maintained to a prototype penetration assembly. Environment" No. IPS-107 dated for 30 min duration not 60 min The prototype was first subjected to October 5,1973.

radiation exposure, then temperature and pressure, concurrently. 1. FSAR Appendix 3C " Safety-Related B. Solutions:

Equipment Temperature Transients During the Limited Main Steam Line During the LOCA test the Break" and NRC Comment 7.17 of the pressure was held for the same subject. required time period.

Conax letter " Qualification of Electric Penetrations: No. IPS-411, P/N 7280-10001-01, IPS-369, IPS-325 dated 1/5/80.

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r 28 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Inside Recirculation Spray Pump Motor Loss of Coolant Accident (LOCA) 120 days @ 150 F MANUFACTURER 280'F 0 to 30 min Reduce from 280*F to General Electric Company 150*F 30 to 60 min OPERABILITY DEMONSTRATED Model SK6319XJIB 150*F >60 min 300 HP, 460V 1.15 SF, 45 psig 0 to 30 min 130'F - 750 days Class H Insulation Redt:e from 45 to O psig 30 to 60 min SUPPLIER 0 psig >60 min 6.8 x los rads Same as above ACCURACY REQUIREMENTS Spray: 0 to 4 hr solution of boric P.O. acid (2000-2100 ppe boron) buffered Not Required to a pH of 8.5 to 11.0 with NaOH.

NA-1355 Beyond 4 hr similar solution with a pH of 7 to 9.

FUNCTION

1. Engineered Safety Feature ENVIRONMENT TO Mf!CH EQUIPMENT IS QUALIFIED

2. DBA (LOCA and MSLB) Mitigation LOCA LOCATION Pressure and Temperature - 45 psig at Inside Containment, Outside Cranewall 275-280*F from 0-30 sing Pressure was reduced to O psig at 10 F within next MARK NO. 30 min. During this 60 min. steam exposure motor was sprayed with chemical 2-RS-P-1A, Inside Recirculation Spray Pump solution at 20 gpe. Motor was at full 2-RS-P-1B, Inside Recirculation Spray Pump load thruughout. Four cycles were run as described above, stopping motor between each cycle to take readings. At the fifth cycle till end of 7 days, temperature reduced to 150 F at 0 psig and sprayed continuously with chemical solution.

Note:

MSLB Qualification on Page 29.

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28a Qualification and Evaluation DESCRIPTION OF ENVIRONMENT (Cont'd)

Radiation - Motor was exposed to an equivalent dose of 2 x 106 rads at a dose rate of <0.5 x 10s rads /hr.

Chemical Spray - Spray continuously 0-7 days with a water solution of boric acid, lithium hydroxide and solium hydroxide with the following concentrations:

Baron - 0.23 molar (as boric acid)

Lithium hydroxide - 1.0 x 10~4molal Sodium hydroxide - 1.0 x 108 solal The above will result in a pH of 5.5 to 6.5 QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA M LOCA Motor was tested sequentially by Topical Report on C.E. Vertical A. Deficiencient first subjecting it to the cumulative Induction Motors Inside Containment radiation dose and then the steam- Recirculation Spray Pump Motors - 1. Chemical spray pH levels chemical spray with elevated temperature Surry Power Station -Second in test do not agree with and pressure. Addendum to Cover Heat Aging, design levels.

Radiation Exposure, Vibration, 2. Temperagurevariedfrom Steam / Chemical Spray Exposure 275-280 F.

Qualification Tests - Docket Number 50-280 and 50-281 by M.W. Sheets, B. Solutions:

Vertical Motor Products Section General Electric Company, 1. Lower pH levels (5.5 to 6.5)

San Jose, California June 12, 1973 maintained during motor (Pages 36 to 64). test have been reviewed with regard to motor mat-erials and it has been deter-eined that the higher design pH levels would not have any additional effect.

2. Tengerature variation of 275Fto280Ffallswgthin the tolerance (265-280 F) of the IDCA tenperature trans-ient profile (FSAR Fig. 2.4-2).

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29 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Inside Recirculation Spray Pump Motor Main Steam Line Break (MSLBJ 120 days ti 150 F MANt:FACTURER~ 430 F 0 to 2 min OPERABILITY DEMONSTRATED (2) 280 F 2 to 60 min General Electric Company 150 F >60 min 130 F - 750 days Model 5K6319 x JIB 45 psig 0 to 30 min 300 IIP, 460 V, 1.15 SF, Class 11 Insulation Reduce from 45 ACCURACY REQUIREMENTS to O psig 30 to 60 min SUPPLIER 0 psig >60 min Not Required 3.4 x 10' rads 40 year dose S.sne as above P.O.. ENVIRONMENT TO WHICH EQUIPMENT ISJ UALIFIED NA-1355 M_S t.B FUNCTION Temperature - Motor was qualified to the design environment by analysis.

1) Engineered Safety Feature

2) DBA (LOCA and/or MSLB) mitigation Pressure - See LOCA qualifications for this motor.

LOCATION Radiation - Motor was exposed to an inside Contaisument, Outside Crane. all equivalent dose of 2 x los rads at a dose rate of <0.5 x 10" rad /hr.

51g_NO.

NOTE: LOCA envirorunent and qualification 2-RS-P-IA, Inside Recirculation Spray Punp continued on page 28 2-RS-P-lH, inside Recir ulation Spray Pump

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! 29a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES M,mER OF (&ALIFICATION (CALIFICATION DoctmENT A%D RECOMMEAliD *~.4LL"TIO%S MSLB MSLB MSLB

The motor was qualified by utilizing the 1. Final Safety Analysis Report - A. Deficiencies

1 LOCA qua l s f icat i on t es t results i.e., raJia- Section 3C, (pages I to 21) tion exposure, temperature, pressure. A 1. Accuracy not stated in test heat t ransfer calculation was performed 2. Topical Report on CE Vertical report for pressure.

(Ref. FSAR, Section 3C) to obtain the Induction Motors - Inside Containment maximum surface temperature that will Recirculation Spray Pump Motors - 2. Test report is not dated on be czperaenced during a MSLB. This Surry Power Station - Second Addendum signature page.

value (271 F) was then compared to the to Cover Heat Aging, Radiation Exposure j value (280 F) that the motor was tested Vibration, and Steam / Chemical Spray 3. Pressure was maintained at i

for. Since the motor was qualified for Emposure Qualification Test - Docket 40 psig tor 30 man and not the LOCA at a terperature of 280 F, the Docket Number 50-280 and 50-281 60 man.

3 lower surf ace traperature of 271 F proved by M. W. Sheets. Vertical Motor the acceptable operation of the motor Freducts Section, General Electric B. Solutions:

during a MSLB. Company - San Jose, Calafornta a

June 12, 1973 (pages 36 to 64) 1. The actual max; mum design pressure is 40 psig. Thesc

motors were tested for 45 psig (ref. LOCA qualification

, for these motors). 40 psig is i a conservative salue and test

! pressure accuracy within

• 5 psig from 45 psig tested

, would be reasonable to assume.

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dated oc the cover sheet.

3. I n t he G . E . LOCA t es t , the motor was tested for five l cy<les at 45 sig for a i perical of 30 min per cycle.

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30 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIRL' TENTS Solenoid Operator Loss of Coolant Accident (LOCA) LOCA 8

MAhUFACTURER 5 x 10 rada (based on LOCA) In SOV will perform its f unction of closing addition, the 40 yr radiation dose of the isolation valve within 60 sec of Automatic Switch 4 x 104 rads must be considered for a receiving signal.

Model #ifT8321A5 tot.al possible radiation dose of 5.04 x 10* rada.

SUPPLIER Same as above PA. ENVIRONMENT TO MtICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED NA-Il25 IDCA IDCA FUNCTION Valves not specifically tests to SOV performed required safety function Containment Isolation 5.6 x los rad integrated dose. When after receiving radiation dose.

exposed to 5 x 107 rad, leakage develop-LOCATION oped which exhausted the pressure vessel. ACCURACY REQUIREMENTS Solenoid valves will have achieved Auxiliary Building safety-related function within 60 sec Not Required Zone C of an initiation signal. The long-term failure mode will not reintroduce air MARK NO. to a control valve, therefore, the valve will maintain its fail-mafe positon.

SOV-BD-200A, C, E Steam Generator Blowdown Isol Viv SOV-CC-200A, B, C Containment Recirculation Air Clr Outlet - Outside Containment SOV-CC-201A RCP Thern Barriers Return Hdr SOV-CC-202A, C, E RCP Coolers Return Hdr SOV-CC-203A, B kHR Heat Exchanger Return 50V-CC 204A-1,2 RCP Coolers Inlet - Outside Containment SOV-CC-204B-1, 2 RCP Coolers Inlet - Outside Containment SOV-CC-204C-1, 2 RCP Cooler Inlet - Outside Containment SOV-CV-250A, B, C, D Containment Vacuum Pump Suction SOV-DA-200A RC Sump Pump Discharge SOV-RM-200A Radiation Monitor SOV-SI-200A, B Nitrogen Supply Line SOV-SI-201A, B Nitrogen Supply Line SOV-VG-200% Pri Drn Xfer Tk Vent m _ _ _ _ _ _

~ w) 30a Qualification and Evaluation (Cont'd)

QbALIFICATION DEFICIENCIES tL_\NhlN, ((J,NJAl.l> ICAT![*N QllALIFICATION DOCUttENT AND RECtWtT NDED SottJTIOhS IDCA IICA LOCA Test Franklin Institute Research A. Deficiencies:

1.atmratories (FIRL) Test Repo rt F-C4',39, Failure during radiation exposure.

Cat a' og #30 West >nghouse letter B. Solutions:

NS-S.57706 khen exposed to a radiatia.n dose at 5x 10' rads, st.mc plast ic anards of the SOV did disintentrat e (aansirig the valve to leak. Howc*er, the valve was able to exliaust it s accumulated pressure and perte,rm its seiety function. (V Letter NS-SS77060)

D ls 31 Qualification and Evaluation IQilit1ENT l'ESrRIPTioN DES-:RII' TION OF ENVIRONMENT UPERABil.'s TY ErajU_l RE* FEN TS 460V Switshgrar an.1 Transfors.er Los, of Coo'eant Accident (l>)CA) 1.DCA NANUVAC'ItkE_R 1.9 x 10 % ra.ls (based on 120 days 2 x loi rads l> C'6 ) . In addition, the 40-year 3

rad,ation . lose of Ia 10 rals 11E Impesial Corpo ation s.u s t be tonsidered f or a total httPLIER pos sibic radiation dose of 2 x 10 4 r.e d s .

Sam.e as al.ove OPER ABill ni DEMONSTR A{D I' _U u Il50 NA - 10M8 Ix '0" rads HiNCTinN ENVIRONMENT To b1 tlc 11 EQJiltfENT IS y ALIFIFD Supptses Powes to Saf et y Syst ems flea 1x 10" ra.1 ACCURACY REQLIREMENTS 1/ k:A flON Not Required Auxiliary Ituilding Zone N MAAK NO.

2-EE-SS-U , 480V Sws tc h Gear (zill) 2-EE-SS-t 4, 480V Swi t ch Ce.s r (2J I) 2-EE-ST-01, 480V Trans t r,rswr (2111) 2-EE-ST-02, 480V Transforew-r (2J I )

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QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECftetENDED SOLUTIONS I

' WA WA LOCA Tested Gould letter dated A.DEFICIE?CIES:

April 25, and March 21, 1979 Qualification Document is a Letter.

B.SOI17TIO?E:

Letter has been sent to the supplier requesting a copy of the test report, or arrangement made for audit of records at supplier's plant.

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_ U 12 Qu lification .ind Evaluation Eylliitith f flESCRil' TION DESCRIPTION OF FNVIRONMENT OPERARILITY REQt3RDIENTS Terminal lilocks 1.oss of Coolant Accident (IDCA) Loss of Coolant Accident ( l>1CA )

HANilFM f ttNER Ix 10s rads (based on 120 days IDCA) 1.04 x 10" rads

'n addition, the 40 yr railiation Jose N arat hon Series 200 .an.1 1500 c.t 4 x 104 rails must be considered for OPERAHILITY DEMONSTRATED Tcominal hlutks (Phenolic) a total possible radiation dose of 1.04 x lo s rads. IACA Connerteosi Type NSE-3, NSS- 1, anel I"itP s Te r minal H.a n n Strans Liric Break (MSI.R) I'henolic I x 10" rails lilot h s (Nylun) Nylon I x 108 rads Will not see a thanging environment Thermo-electric Tesminal <!ue to NSI.B ACCtIRACY REQIllR1NFyp filotk No. '1225 (Thermosetting Phenolir) Not Required ENVIRONMENT TO WillCal EQUIPMENT IS QllAllFIED t.E Te min.il liiocks EHS and Elt25 (l'henolec) 1.oCA Westie.ghouse Tyle TitAl Unfilled phenolic can withstand a ganana Tenmin.el filos ks (Nylon) exposure dose of over 10" rails an.1 show minimal ef fects due to radiation.

Si tP_f. l F R Nylon can willist.end a gamma expossare Same as shove dose of over 10' rails

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N/A FiINCTION Supplies l'ower t o Sa fet y Systa ms IDCATIUN Outside Canitainment (Gener.sI Ascas)

HARK,No.

N/A

G 324 Qualification and Evaluation (Con't)

Ql!ALIFICATION DEFICIENCIES tlANNF R of QllAl.lFICA, TION AND REOtiMENi1ED sot.IITjoNS QtlAI.lFICATION DOCllMENT P4A  !!9 l.pCA Termin.nl Riosk m.iterial w.is re.mp.sied REIC Report No. 21 Radistion None with ident ical auterial for the rifccts Elfert Information Center, of high level rads.stion. Coluaibus, Ohio. Ruchanan Pro <fuct Manual Insert 2.I Rev. 8/23/76

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BWR Exposure:

A series of transient cycles each consisting of a rise to a speci f icit pressume and temperature for a specific.) time and a gradual return to initial conditions. Following transient cycles 100 day exposure to live steam O psig, 212 F.

HQI.H Same as " Description of Environment" QIIAl.IFICATION DEFICIENCIES AND RECOMMENDED SOI.trflONS MANNFk OF_ QUAI.lFICATION QilAl.IFICATION DOCllMENT YN4 I m'A !8'A_

Test - Sequential Okonite's F.ngineering Report A. Ik f i ci encies :

No. 141 ilated Fehauary 29, 1972 HSI.It None HSI.R

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S3.W Calculation ES-189 Pressure .in.1 Railiat ion - Test " Equipment Temperature Transient A. Deficienrics for Okonite Tape Splices" Heler ti.1.fM'A quali f icat ion Does rot sicet qualification temperature B. Solution Maximum calculated surf are t emperature during limit ing MSLB is 2 70"F which does not exceed qualification temperature of 324 F given in Okonite Engineerang Report No. 141

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) O 34 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERARILITY REQr!*i < s tS Splicing Material Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 280 F 0 to 30 min 120 days @ 150 F Reduce from 280 F Raychem tof50F 30 to 60 min MSLB WCSF type coated with Type N adhesive 150 F >60 min Heat Shrinkable Field Splicing Material 45 psig 0 to 30 min 120 days @ 150 F SUPPLIER Reduce from 45 to O psig 30 to 60 min Same as above O psig >60 min 4.8 x 107 rads P.O. OPERABILITY DEMONSTRATED Spray: 0-4 hr solution of boric acid N/A (2000-2100 ppm boron) buffered to a pit of IDCA 8.5 to 11 with Na0ll>4 hr similar solution FUNCTION with a pit of 7 to 9 212 F for 100 days Supplies Power to Safety Systems Main Steam Line Break (MSLBJ PostLOCAthermalaggngisgreater LOCATION 430,F 0 to 2 min than 2.9 years @ 150 F 280 F 2 to 60 min Inside Containment 150 F >60 min Mg 45 psig 0 to 30 min MARK NO. Reduce from 45 See above to o psig 30 to 60 min N/A 0 psig >60 min 3 x 107 rads ACCURACY REQUIREMENTS ENVIRONMENT TO WillCil EQUIPMENT IS QUALIFIED Not Required LOCA & MSLB Irradiated by cobalt-60 gamma source at 0.27 Mrads/hr to total dose of 200 Mrads.

360 F @ 70 psig 5 hr 320 F @ 70 psig 6 hr 250 F @ 21 psig 24 hr and 0.2% boric acid spray buffered to a pli of 9.5 to 11.0 221 F @ 2.5 psig 12 days 212 F @ 2.0 psig 100 days

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a~a-34a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS IpCA & MSLB LOCA & MSLB Combined thermal and radiation aging Raychem Technical Report F-C4033 A. Deficiencies:

period followed by a simultaneous exposure to steam, chemical spray Stone & Webster Calc. ill715-ES-169-0, Material was not qualified to and gamma radiation. dated 3/10/77. 430 F as required for MSLB.

B. Solutions:

Qualification test of 360 F was for 5 hrs, whereas the MSLB environ-ment was 430 F for 2 min. "

temperature environment dees not exceed qualified limits ue to thermal inertia and internal temperature.

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DESCRIPTION OF ENVIRONMENT (Cont'<!)

MSM See above QtIALIFICATION DEFICIENCIES NANNFk OF QtlALIFICATION QllALIFICATION DOCllMENT AND RECOMMENDF!) SolllTIONS lhCA IDCA LOCA Sr.luent ial Tes;t Rosemount Test A. Deficiencies:

Report #117415 NSLIt 1) Radialion level

2) Not subjected to Chemiral Analysas NStit Fpray

3) Aging Rosemount Test Report #117415 B. Solutions:

1) Trans.mitters are good lor FSAR Scotion 3C 40 yr radiation dose plus and response to Comment 7.11 200 hr into a IOCA. Optimum solution is sill being investigated.

2&3) WilI lic reptared durang 2nd retucting outage.

MSI.Il A. Deficienrics

1) Temperature envelope it . Solutions:

1) Qualification test of 350 F for ten minutes, 3lb F for one hour whereas t he envi ronment 430 F for two minutes, then dropping to 280 F af ter two minutes. The temperature environment does not exceed quaIified Iimits <lue to therma 1 inertia and internal trmper.sture.

See calculation #ES-lh9.

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'n N V 36 Qualification and Evaluation J

E UIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT _ OPERABILITY REQUIREMENTS Solenoid Operator Main Steam Line Break (MSLB) M_SLB MANUFACTl;RER See Deficiencies and Solutions SOV will perform its function of closing isolation valve within 60 sec of receiving Automatic Switch Company signal.

Model fHT8344A71 SUPPLIER ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Same as al>ove MSLB MSLB P.O. See Deficiencies and Solutions a. SOV will have performed its function prior to failure NA-1125

b. Failure of SOV will not cause valve FUNCTION to reopen.

1. Emergency Core Cooling / Core Heat Removal ACCURACY ?EQUIREMENTS

2. DBA (LOCA and MSLB) Mitigation

3. HELB Main Steam Valve house accident mitigation Not Required LOCATI6]

Main 5:eam Valve Building MARK NO.

SOV-MS-211A, Auxiliary Feed Pump Turbine Drive SOV-MS-211B, Auxiliary Feed Pump Turbine Drive

O C O 36a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS MSLB MSLB MSLB See Qualification Deficiencies See Qualification Deficiencies A. Deficiencies:

SOV's will not withstand the MSLB temperature.

B. Solution:

1. SOV's will have completed their operation before temperature causes it to fail.

2. Letter has been sent to supplier requestng copy of test report or arrangement made for audit of records at vendor's plant.

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{G \J 37 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Operated Valves Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5 x 10e rads (based on 120 day LOCA). SOV will perform its sunction of closing In addition, the 40 yr radiation dose isolation valve within 60 sec of receiving Automatic Switch Company of 4 x 104 rads must be considered fcr signal.

Model #1IT830281U a total possible radiation dose of 5.04 x los rads.

SUPPLIER Same as above l.

P ENVIRONMENT TO MIICH EUQIPMENT IS QUALIFIFED OPERABILITY DEMONSTRATED NA-Il63 LOCA LOCA FUNCTION Radiation exposure 5 x 107 rads Fungtioned properly for 14 days at 150 F af ter 50 Mrad radiation exposure Containment Isolation and will not misoperate if SOV fails Zone C due to radiation.

I.OCATION ACCURACY REQUIREMENTS Auxiliary Building Not Required MARK NO.

SOV-SS-200B, Pressure Liquid Space Isol Valve SOV-SS-202B, PRI Coolant Cold Leg Sample Isol Valve SOV-SS-212B, Steam Generator Sample Isol Valve SOV-SS-201B, Pressurizer Vap-er Sample SOV-SS-203A, RHR Outboard Isol Valve SOV-SS-203B, RifR Outboard Isol Valve SOV-SS-204B, Pressure Relief Tank Sample SOV-SS-206E, PRI Coolant Hot Leg Sample Isol Valve a

37a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCLTfENT AND REr0MMENDED SOLITTIONS LOCA LOCA LOCA Test Franklin Institute Research A. Deficiencies:

Laboratories (FIRL) Test Report F-C4539 Test document not available at VEPCO.

B. Solution:

Letter has been sent to supplier requesting copy of test report or arrangement made for audit of records at vendor's plant.

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r 38 Qualification and Evaluation EQUlltfENT DESCRIPTION DESCRIPTION OF ENVIRON 1ENT OPERABILITY REQUIREMENTS Solenoid Operator Loss of Coolant Accident (II)CA) LOCA MANUFACTURER 5 x 10 8rads (based on 120 day LOCA) SOV will perform its function of in addition, the 40 yr radiation dose closing isolation valve with Automatic Switch Company of 4 x 104 rads must be considered 60 sec of receiving signal.

Model #HB830281U for a total ossible radiation dose of5.04x10p' rads. OPERABILITY DEMONSTRATED SUPPLIER ENVIRONMENT TO WHIC11 EQUIPMENT IS QUAllFIED LOCA Same as ebove g 5 X 10 Hads ACCURACY REQUIREMENT FIINCTION Not required

1. . Containment Isolation

2. Post Accident Monitoring LOCATION Auxiliary Building, Zone C MARK NO.

SOV-SS-206R PRI Coolant flot Leg Sample Isolation ialve

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38a Qualification and Evaluation (Con't)

QUALIFICATION DEFICIENCIES 11ANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SCLUTIONS LOCA LOCA LOCA Test Fraralin Institute Besearch tione Laboratories (FIRL) Test Report F-C4539 1

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39 Qualification and Evaluation EQtJIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Terminations and Connectors LOCA LOCA MANUFACTURER 5 x 10 8rads (based on 120 day LOCA). 5.04 x 108 rads In addition, the 40 year radiation dose Raychem Incorporated of 4 x 104 rads must be considered for OPERABILITY DEMONSTRATED, HVT Temination a total possible radiation dose of 1.04 x HVMC Connectors 108 rads. UCA SUPPL.IER Main Steam Line Break (MSLB) 2 x 10s rads See above Will not see a changing environment ACCURACY REQUIREMENTS due to MSLB.

PA . Not Required ENVIRONMENT TO WIIICII EQUIPMENT IS QUALIFIED N/A LOCA FUNCTION Terminations & Connectors

~

Supplies Power to Safety Systems Irradiation of the materials in a cobalt -

60 gamma source at 0.50 Mrads per hour to a total dose of 2 x los rads.

I0 CATION Outside Containment MARK No, N/A

_ _ _ _ - _ _ - - _ - _ _ __ J

k 39a Qualification and Evaluation (Cont *1)

QUALIFICATION DEFICIENCIES QtlALIFICATION DOCIMENT AND RFCotMENDED SOI.UTIONS MANNER OF JJALIFICATION lACA LOCA LOCA Test: Thermal aging followed by Raychem Report #71100 Revision 1 A. Deficiencies:

irradiation for HVT and ifVMC Letter f rom Raychem dated 4/24/79 None and EPSERT FR0 Raychem Report RT1508/l

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r 40 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIROKMENT OPERABILITY REQUIREMENTS Solenoid operators Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5 x los rads (base on 120 day LOCA). SOV will perform its f unction of in addition, the 40 yr radiation dose closing isolation valve within Automatic Switch Company of 4 x 104 rads must be considered for a 60 sec of receiving signal.

Model THT 8320A102 total possible radiation dose of 5.04 x 10 8 rads.

SUPPLIER Same as above P.O. OPERABILITY DEMONSTRATED NA-Il63 LOCA

[ UNCTION ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED See qualification deficiencies and recommended solutions Containment Isolation IDCA See Qualification Deficiencies LOCATION ACCURACY REQUIREMENTS Auxiliary Building Not Required MARK NO.

Zone F SOV-LM200A, Containment Leakage Monitoring SOV-LM200B, Conta inment Leakage Monitoring SOV-LM200C, Containment Leakage Monitoring SOV-LM200D, Containment Leakage Monitoring SOV-LM200E, Containment Leakage Monitoring SOV-LM200F, Containment Leakage Monitoring SOV-LM200G, Containment leakage Monitoring SOV-LM200H, Containment Leakage Monitoring Zone C SOV-LM201 A, Containment Leakage Monitoring SOV-LM201B, Containment Leakage Monitoring SOV-LM201C, Containment Irakage Monitoring SOV-LM201D, Containment Leakage Monitoring I

I

40a l

Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS UJCA LOCA LOCA l

Not known None SOV will perform its function of closing isolation valve within 60 see of receiving signal.

Failure of SOV will not reopen valve.

Letter has been sent to supplier requesting copy of test report,

- or arrangement made for audit of

! records at supplier's plant.

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41 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Radiation Monitoring Pump Motor Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5.4 x lo s 5.4 x los Marathon Electric ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED CPERABILITY DEMONSTRATED Class A Insulation Model # BM56T170518A-W LOCA LOCA St!PPLIER None None llayes Pump Company ACCURACT REQUIREMENTS P.O. Not required NA - 108')

FUNCTION Post Accident Monitoring LOCATION Main Steam Valve Ifouse MARK NO.

2-SW-P-5 Radiation Monitoring Pump 2-SW-P-6 Radiation Monitoring Pump 2-SW-P-7 Radiation Monitoring Pump 2-SW-P-8 Radiation Monitoring Pump

\

41a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCl2fENT AND_ RECOMMENDED SOLUTIONS LOCA LOCA IDCA Nor ? None A. Deficiencies:

No nuclear qualification B. Solutions:

Replace motor (motor has been ordered with Class H Insulecion, Purchase Order dated April 15, 1980).

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42 Qualification and Evaluation Efl UIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABillTY REQUIREMENTS liydrogen Analyzer Loss of Coolant Accident (LOCA) _ Log MANiiFACTURER 1 x 10 8rads (based on 120 days LOCA). I x 10 8 In addition, the 40 yr radiation dose Bendix of 8.?S x 102 Model C Bendix 400-1, T/C analyzer SUPPLIER Same as above P.O. ENVIRONMENT TO W111CH EQUIPMENT IS QUALIFIED OPERABII.lTY DEMONSTRATED NA - 1332 LOCA LOCA FUNCTION None None Post Accident Monitoring LOCATION Auxiliary Building Zone 11 MARK No. ACCURACY REQUIREMENT ll 2A-HC-200, Hydrogen Analyzer +5% full scale ACCURACY DEMONSTRATED None

s 42a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUAI.lFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLtrrlONS IDCA LOCA IACA None None A. Deficiencies:

Qualification dacumentation is nonexistent.

B. Solutions Analy cr will be replace 1 by January 1981 with Category IE qualified equipment and documenta-tion.

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Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIFTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Hydrogen Recombiner Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 1.1 x los rads 1.1 x los rads for 120 days Rockwell International Main Steam Line Break (MSLBJ SUPPLIER Will not see a changing environment due to MSLB.

Same as above P.O. ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRA_TED NA-1365 LOCA l@

FUNCTION 1 x 10 8 rads 1 x 10s rads

1. Engineered Safety Feature

2. DBA (LOCA and MSLB) Mitigation LOCATION Hydrogen Recombiner Enclosure Zone J MARK No. ACCURACY REQUIREMENTS J-llc-HC-1, Hydrogen Recombiner Not Required 1- HC-liC-1, Hydragen Recombiner a

a

43a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA LOCA LOCA Analysis Al-ESG Report N139Til20002 Deficiencies:

Radiation level below that of qualification requirements.

Solution:

Have contacted Rockwell International to obtain further qualification data.

O mm 44 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Recirculation Spray Pump Motors Loss of Coolant Accident (LOCA) Lp HANUFACTURER 5 x 108 rads (based on 120 days 5.04 x 106 rads LOCA). In addition, the 40 year General Electric Company radiation dose of 4 x 10' rads OPERABILITY DEMONSTRATED Model SK6328xC264A must be considered for a total possible radiation dose of 5.04 x LOCA SUFFLIER

~

los rads.

1 x los rads Same as above ENVIRONMENT TO WHICil EQUIItfENT IS QUALIFIFD ACCURACY REQUIREMENTS P.O.. LOCA Not Required NA-1127 , 1 x 108 rads FUNCTION Engineered Safety Feature LOCATION Safeguards Area MARK NO.

2-RS-P-2A, kecirculation Spray Pumps 2-RS-P-2B, Recirculation Spray Pumps i

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44a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF_ QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA LOCA LOCA Unknohm Letter from Vendor C. Bell (CE) A. Deficiencies:

March 10, 1979 Qualification document is in Specification NAS#44 letter form (i.e. no tormal test report witla approved signature and date)

B. Solutions:

Letter requesting actual test report or audit has been sent t o

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45 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIROKMENT OPERABILITY REQUIREMENTS Exhaust Fans LOCA 120 days @ 1 x 108 rads 1 x 106 rads OPERABILITY DEMONSTRATED HANUFACTURER ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED See Qualification Deficiencies Westinghouse Electric Corporation See Qualification Deficiencies SUPPLIER ACCURACY REQUIREMENTS Westinghouse Electric Corporation Not Required P.O.

NUS - 71 FUNCTION

1. Emergency Core Cooling / Core Heat Removal

2. Engineered Safety Feature LOCATION Auxiliary building Zone M HARK NO.

2-IfV-F-8A, Auxiliary Central Area Exhaust Fans 2-ilV-F-83, Auxiliary Central Area Exhaust Fans 2-HV-F-8C, Auxiliary Central Area Exhaust Fans

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45a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS See Qisalification Deficiencies See Qualification Deficiencies A. De ficiencies:

No qualification data available B. Solutionsi llave contacted manufacturer for qualification test data and infor-mation.

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G y 46 Qualification and Evaluation EQUIPMENT DEiCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Operated Valves Loss of Coolant Accident (LOCA) SOV will perform its function of closing isolation valve within 60 sec. of receiving MANUFACTURER 5 x 10 8rads (based on 120 day LOCA). signal.

In addition, the 40 yr radiation dose ASCO of 4 x 104 rads must be considered for OPERABILITY DEMONSTRATED Model #HT - 831654 a total possible radiation dose of 5.04 x los See Qualification Deficiencies and SUPPLIER Recomunended Solutions Westinghouse P.O. ENVIRONMENT TO VillCH EQUIPMENT IS QUALIFIED ACCURACY REQUIREMENTS NA - 1010 LOCA Not required FUNCTION See Qualification Deficiencies and Recommended Solutions Containment Isolation IDCATION Auxiliary Building MARK NO.

SOV - 2204 SOV - 2519 l

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47 Qualification and Evaluation Eg lPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Ambient Temperature Monitors High Energy Line Break (HELB) HELB MANUFACTUREM Maximum accident temperature is 220 F. Alarm Control Room of high temperature.

220 F for 90 see.

Rosemount Engineering 78-81-17 SUPPLIER Same as above P.O.* ENVIRONMENT TO Mi!CH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED NA-1363 Normal Operating Condition J HF Temperature Range: -100 C to FUNCTION NormalOperagingEnvigonnent 325 C Range: - 100 C to 325 C HELB Mitigation ACCURACY REQUIREMENTS S&W Spec.

LOCATION tl.0*F f Operating Temperature Service Building Over a Span of 32 F to 212*F MARK No, 12.0 F @ 212 F to 400 F TE-AM215, Service Building Temperature ACCURACY DEMONSTRATED Monitoring TE-AM216, Service Building Temperature Vendor Product Data Sheet Monitoring 2179,78 Series TE-AM217A, Service Building Temperature Monitoring AccuracgLimfts:

TE-AM217B, Service Building Temperature Monitoring 10.2g@C@0,C

+0.5 C l00 C TE-AM217C, Service Building Temperature 11.6C@325C Monitoring TE-AM211D, Service Building Temperature Monitoring

e 47a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OFJ tlAI.lFICATION QUALIFICATION DoctHENT AND RECOMMENDF.D SOLUTIONS No Test Data Rosemount Catalog Information A. Deficiencies-No qualiff.ation data.

B. Solution:

Letter has been sent to supplier requesting a copy of test report or have arrangements made for an audit of qualification data.

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48 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Pressure Transmitter Loss of Coolant Accident (LOCA Radiation) LOCA MANUFACTURER LOCA: 5 x lo s rads 5.04 x los rads 40 YR: 3.5 x loi rads 120 days Foxboro TOTAL: 5.03 x 108 rads Model EllAH OPERABILITY DEN NSTRATED ENVIRONMENT TO WilCH EQUIPMENT IS QUALIFIED SUPPLIER ~

~

7.6x107 rads NO 148NL M 2.2x10s rads - N0148ND Same as above 7.6x107 rads for amplifier ACCURACY REQUIREMENTS assemblics N014BNL, which Accuracy to be determined P.O. consist of prototype amplifier designed for nuclear service and NA-1215 having radiagion - resistant and having a radiation-resistant FUNCTIOd wiring harness.

Post Accident Monitoring 2.2x10s rads for amplifier assemblies N0148ND, which consist LOCATION of standard E10 units with radiation resistant wiring harness.

Auxiliary Building Zane Y MARK NO.

PT-LM200A, Containment Pressure PT-LM200B, Containment Pressure PT-LM200C, Containment Pressure PT-LM200D, Containment Pressure

r 48a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNEP OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOPCf:.LJED SollTIONS LOCA 1.0CA IDCA Test WCAP-8541 Comunent s :

Manuf acturer contacted to determine type of amplifier used in transmitted at NA2, and also to determine applicability of WCAP-8541 tests.

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t EQUIPMENT DESCRIP'ilON DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Level Indicatiag Transmitter Loss of Coolant Accident (II)CA) 1.005 x los rad MANUFACTURER I x 10 rads 8 (based on 120 day LOCA) 40 yr dose 5.25 x 103 rads for a Delaval Turbine, GEMS Sensor Division total dose of 1.005 x 10s rads OPERABILITY DEMONSTRATED RE-31320/31411 Af ter test, transmitter functioned properly.

S_UPPLIER ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED See above P.O.. LOCA ACCURACY REQU1REMENTS NA-1333 280 F 0 to 60 min ~+5% of Range 280 - 150 F >60 to 180 min FUNCTION 150*F 180 min to 14 days 45 psig 0 to 60 min ACCURACY DEMONSTRATED Post Accident Monitoring 45-0 psig >60 to 150 min 13.4 psig 150 min to 14 days +1.4% After Test LOCATION Radiation Exposure 2 x los rads Auxilia y Building Zone F MARK NO.

LIT-RS251A, Containment Water Level LIT-RS251B, Containment Water Level

49a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS _

Sequenttal Test LOCA IDCA Franklin Institute Research None Laboratories (FIRL)

Report F-C3834 f

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r 50 Qualification and Evaluation EQUIItfENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator LOCA 5.4 x los rads and 120 days MANUFACTURER 5.4 x 10s rads (base on 120 day LOCA)

Limitorque Main Steam Line Break (MSLB)

Operator - Reliance Class B Insulation Will not see a changing environment due to SUPPLIER MSLB.

Same as above ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED P.O. 2X10 7 dads I 2 x iv nuas 25C P NA-1194 100% hamidity ACCURACY REQUIREMENT Test duration 15 Days FUNCTION Not Required

1. Engineered Safety Feature

2. DBA (LOCA and MSLB) Mitigation LOCATION Quench Spray Area MARK NO.

MOV-SW201A, Recirculation Spray Heat Ext. Header Inlet MOV-SW201B, Recirculation Spray Heat Exc. Header Inlet MOV-SW201C, Recirculation Spray IIcat Exc. IIcader Inlet MOV-SW201D, Recirculation Spray Heat Exc. Header Inlet MOV-SW203B, Service Water To Recirculate Spray Coolers MOV-SW204A, Service Water To Recirculate Spray Coolers MOV-SW205A, Recirculation Spray lleat Ex. Ileader Outlet MOV-SW2058, Recirculation Spray Heat Ex. Header Outlet MOV-SW205C, Recirculation Spray Heat Ex. Ifeader Outlet MOV-SW205D, Recirc.4et so Spray Heat Ex. Header Outlet MOV-SW206A, Recirculation Spray lleat Ex. Header Outlet MOV-SW206B, Recirculation Spray Heat Ex. lleader Outlet

50a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AKD RECOMMENDED SOI.UTIONS

Limitorque Corp. None Nuclear Qualification Sheet Dated 11/1/79 Comments Have supplied Limitorque with the serial and work order numbers. Lik torque is in the process of determining schedule for providing any qualification data which is available, to insure that these valve operators are covered under these tests.

,-- 51 Qualification and Evaluation

. [QUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABillTY REQUIREMENTS

-~ Solenoid Operated Valves High Energy Line Break (EELB) SOV will perform its function of closing the isolation valve within MANUFACTURER 1.5 x loi rads 60 second of receiving signal.

ASCO Hodel illT8321 A5 ' ENVIRONMENT TO WHICH F.QUIPMENT IS QUALIFIED OPERAn!LITY DEMONSTRATED

.SUPELIER When exposed to 5 x 107 rad, leakage developed SOV performed required safety function which exhausted the pressure vessel. Solenoid after receiving radiation dose.

Fisher. valves will have achieved safety-related function within 6u second of an initiation ACCURACY REQUIREENTNS P.O. signal. The long-term failure mode will not reintroduce air to a control valve, Not Required NA-!!25 therefore, the valve will maintain its fail-safe position.

FlWCTION Containment Isolation LOCATION Hain Steam Valve llouse MARK NO.

SOV-MS-213A-1, Steam Generator Trip Valve SOV-MS-213A-2, Steam Generator Trip Valve 50V-MS-2138-1, Steam Generator Trip Valve SOV-MS-213C-1, Steam Generator Trip Valve  ;

SOV-KS-213C-2, Steam Generator Trip Valve SOV-MS-209A, Steam Generator Trip Valve SOV-MS-2098, Steam Generator Trip Valve SOV-SV-202-1 Air Ejector Vent SOV-SV-203, Air Removal System L , j

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Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS HELB HELB KELB Test Franklin Institute Research A. Deficiencies:

Laboratories (FIRL) test Report F-C4539, Catalog #30 Failure during radiation exposure.

Westinghouse Letter NS-SS 7706 B. Solutions:

When exposed to a radiation dose of 5 x 107 rads, some plastic inarJs of the SOV did disintegrate causing the valve to leak. However, the valve was able to c>haust its accumulated pressure and perform its safety f unction.

(Westinghouse letter NS-SS77060).

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52 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) 5.4 x los rads and 120 days itWUFACTURER 5.4 y los rads (base on 120 days IDCA)

Limitorque Main Steam Line Break (MSLB)

Limitorque Motor Class B insulation OPERABILITY DEMONSTRATED W .1 not see a changing environment dut to St!PPLIER MSLB 2 x 107 Rads Same as above ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED ACCURACY REQUIRED P.O..

2 x 107 Rads 250 F Not Required NA-1194 100% Humidity Test Duration: 15 Days FUNCTION

1. Engineered Safety Feature

2. DHA (IDCA and MSLB) Mitigation LOCATION Quench Spray Area MARK NO.

NOV-SW203A, Service water to recirc spray coolers MOV-SW203C, Service water to recirc spray coolers i

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52a Qualification and Evaluation (cen't)

QUALIFICATION DEFICIENCIES M,NNER 3 OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS Test See Qualification Deficiencies Limitorque Nuclear Qualification Qualification information was inadequate.

Data Sheet, dated 11/1/79 Solution Have supplied Limitorque with the serial and work order numbers. Limitorque is in the process of determining schedule for providing any qualification data which is available.

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53 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIROMMENT OPERABILITY REQUIREMENTS Hotor Operated Valve - Valve Operator 1a lo srads (based on 120 day LOCA) 1 x los rads 120 days MANLTACTURER Limitorque ENVIRONMENT To VHICII EQUTFMENT IS QUALIFIED OPERABILITY DEMONSTRATED Operator - Reliance Class B Insulation 40 yr integrated - 2 x 10s rads 2 x 10s rads SUPPLIER Same as above ACCURACY REQUIREMENTS P;02 . Not Required NA-1193 FUNCTION

1. Emergency Core Cooling / Core Heat Removal

2. Engineered Safety Features LOCATION Auxiliary Building Zone D HARK NO.

MOV-SW208A, Inlet Header Valve MOV-SW2088, Inlet Header Valve MOV-SW213A, Fuel Pit Cooler Valve MOV-SW213B, Fuel Pit Cooler Valve MOV-SWil3A, Fuel Pit Cooler Valve MOV-SWil3B, Fuel Pit Cooler Valve

53a Qualification and Evaluation (con't)

Qt'ALIFICATION DEFICIENCIES t_ TAN!ER OF QUALIFICATION QUALIFICATION DOCUMENT ANT) RECOMMENDED SOLtrTIONS_

Test Linttorque Report #B0003 None Test at Isomedix, Inc.

Parsippany, N.J. Cogments Have supplied Limitorque with the serial and work order numbers. Limitorque is in the process of determining schedule for providing any qualification data wnich is available, to insure these operators are covered under the referenced testing.

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54 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERARILITY REQUIREMENTS Level Transmitter LOCA 120 days @ 150 F MANUFACTURERS'-~~ 250 F 0 to 30 min OPERABILITY REQUIREMENTS Reduce from 280 F 30 to 60 min Rosemount Model #115DP4A to 150 F >60 min 1,240 days @ 150*F 45 psig 0 to 30 min SUPPLIER Reduce from 45 ACCURACY REQUIREMENTS to O psig 30 to 60 min Same as above O psig >60 min 124 days @ 150 F 6.8 x 108 rads P ._O . . ACCURACY REQUIREMENTS Spray: 0-4 hrs solution of boric NA-1486 acid (2,00 - 2,100 ppm boron) buffered + .5%

to a pil of 8.5 to 11 with NaOH) 4 hrs FUNCTION similar solution with a pH of 7 to 9. ACCURACY DEMONSTRATED DBA (LOCA and MSLB) Mitigation MSLB + .25%

LOCATION 280 F 2 to 60 min ACING 430*F 0 to 2 min Inside Containment 150 F >60 min Rosemount transmitters have been 45 psig 0 to 30 min shown to have an aging problem.

MARK No. Reduce from 45 to O psig 30 to 60 min LT-2474 Steam Generator Flow Transmitter o psig >60 min LT-2475 Steam Generator Flow Trasmitter 3 x 104 rads LT-2484 Steam Generator Flow Transmitter LT-2485 Steam Generator Flow Trac' '.tter LT-2494 Steam Generator Flow Transmitter ENVIRONMENT _TO WHICll EQUIPMENT IS QUALIFIED LT-2495 Steam Generator Flow Transmitter LOC _A 350 F 0 to 10 min 316 F 10 min to I hr 303 F 1 br to 8 brs 230 F 8 hr to 50 hrs 60 psig 0 to 10 min 70 psig 10 min to 7 hrs 55.4 psig hr to 8 hrs 6 psig 8 hr to 50 hr 5 x 108 rads Spray: None HSLB See above

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54a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNFR OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS ILCA & MSLB LOCA LOCA Test Rosemount Report #117415 A. Deficiencies:

1. Radiation USbE

2. Transmitters were operational Rosemount Report #117415 at 5 x los rads; however needs further testing to assure compli-FSAR Section 3C and reponse to Comment 7.17 ance to 4.8 x 107 rads.

Stone & Webster Calc # ll715-ES-169-0, 3. No Spray Test dated 3/10/77

4. Aging B. Solutions Will be replaced during 2nd refueling MSLB A. Deficiencies:

Temperature envelope B. Solution:

Qualification test of 350 F for one hour whereas the environment is 430 F for two minuteu. The temperature environment does not exceed qualified limits due to thermal inertia and internal temperature. See referenced Calculation #ES-169.

f 55 Qualification and Evaluation (QUIPMENT DFSCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREML4TS Solenoid Operated Valves Loss of Coolant Accident (LOCA) 120 days @ 150 F K4NUFACTURER 280"F 0 to 30 min Reduce from 280 F Asco tof50F 30 to 60 min OPERABILITY DEMONSTRATED Model fifD-2068322V 150 F >60 min 45 psig 0 to 30 min See Qualification Deficiencies SUPPLIER Reduce from 45 and recommended solutions, to O psig 30 to 60 min Same as above O psig >60 min 4.8 x 107 rads (1)

P.O.- Spray: 0-4 hrs solution of boric ACCURACY REQUIREMENTS acid (2000-2?00 ppe boron) buffered NA - 1010 to a pH of 8.5 to 11 with NaOli > 4 Not required.

hrs similar solution with a pH of FUNCTION 7 to 9.

Containment Isolation Main Steam Line Break (MSLB)

LOCATION 430 F 0 to 2 min 280 F 2 to 60 min Inside Containment 150*F > 60 min 45 psig 0 to 60 min MARK No. Reduce from 45 to O psig 30 to 60 min SOV-IA-201A Containment Instrument Air o psig >60 min 3 x 10 7 rads ENVIRONMENT TO MIICil EQUIPMENT IS QUALIFIED LOCA See Qualification Deficiencies and recommended solutions

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55a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUA'll'ICATION QUALIFICATION DOC 1&fENT AND RECOMMENDED SOLLTIONS See Qualification Deficiencies See Qualification Deficiencies LOCA & MSLB A. Deficiencies No test data available.

B. Solutions Letter has been sent to manufacturer requesting a copy of the qualification test data, on arrangements will be made for an audit of records at vendors' plant.

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56 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Operated Valves Loss of Coolant Accident (LOCA) 120 days @ 150 F MANUFACTURER LOCA OPERABILITY REQUIREMENTS Asco 280 F 0 to 30 minutes See qualification deficiencies and recosamended Model #FT-8320A102 Reduce from 280'F solutions to 150 F 30 to 60 minutes SUPPLIER 150 F >60 minutes ACCURACY REQUIREMENTS 45 psig 0 to 30 minutes Same as above Reduce from 45 Nc* Required to O psig 30 to 60 minutes P.O. O psig >60 minutes 4.8 x 107 rads (1)

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Spray: 0.4 br solution of boric acid FUNCTION (2000-2100 ppe boron) buffered to a pH of 8.5 to 11 with NaOH) 4 hr similar Containment Isolation solution with a pH of 7 to 9.

LOCATION Main Steam Line Break (MSLB)

Inside Containment 430 F 0 to 2 minutes 280 F 2 to 6; J autes MARK NO. 150 F >60 minutes 45 psig 0 to 30 minutes SOV-SS-207A Rl!R sample line Reduce from 45 SOV-SS-2078 RHR sample line to O psig 30 to 60 minutes O psig 3 x 107 rads ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED See qualification deficiencies and recommended solutions I

s 56a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES PfANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOtt* FENDED SOLUTIONS See Qualification Deficiencies See Qualification Deficiencies A. Deficiencies:

No test data available B. Solutions:

Letter has been sent to manufacturer requesting a copy of the qualifica-tion test data, or arrangements made for an audit of records at vendors' plant.

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51 Qualification and Evaluation QUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Notor Operated Valve Loss of Coolant Accident (LOCA) LOCA HANLTACTURER 5 x los rads (based on 120 days) 5.00 x 10s rads 40 yr dose negligible.

Limitorque OPERABILITY DEMONSTRATED Operator - Reliance Class B Insulation ENVIRONMENT TO milch EQUIPMENT IS QUALIFIED LOCA SUPPLIER LOCA See Qualification s

Deficiencies Same as above 40 yr integrated - 2 x los rads 2 x lo rads P.O. See Qualification Deficiencies ACCURACY REQUIREMENTS NA-1242 Not Required FUNCTION

1. Engineered Safety Feature

2. DBA (LOCA) Mitigation LOCATION Safeguards Area MARK NO.

HOV-QS-200A, Refueling Water Storage Tank MOV-QS-200B, Refueling Water Storage Tank MOV-RS-200A, Supply Valve Component Cooling Recirculation Spray NOV-RS-200R, Supply Valve Component Cooling Recirculation Spray NOV-RS-201A, Supply Valve Component Cooling Recirculation Spray NOV-RS-201B, Supply Valve Component Cooling Recirculation Spray l

. 57a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS

!/)CA LOCA LOCA 2.0 x 10s rads gasssa radiation Limitorque Have supplied Limitorque with the serial at Isomedix, Inc. Parsip fany, N.J. Report No. B0003 and work order numbers. Limitorque is in the process of determining schedule for providing information if supplied equipment will fall under the referenced document.

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58 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERARILITY REQUIREMENTS Solenoid Operated Valves Loss of Coolant Accident (LOCA) IDCA MANUFACTURER 5 x 10 rads (based on 120 day LOCA).

8 SOV will pcaform its function of In addition, the 40 yr radiation dose closing isolation valve within Automatic Switch Company of 4 x 104 reds must be considered for a 60 sec of receiving signal.

Model IIT 830281J total possible radiation dose of 5.04 x 10s rads.

SUPPLIER Same as above P.O.- F.NVIRONMF.NT TO MilClf EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED LOCA lagA FUNCTION 460 F 0-2 min $ X 10IFads Reduce from 460 F to 340 2 to 8 min Containmert Isolation Reduce from 340 F to 240* 8 to 35 min 150 F 52 min to 14 day LOCATION 129 psia 0 to 2 min 118 psia 2 to 32 min Auxt:iary Building Reduce from 118 to 25 psia 32 to 34 min ACCURACY REQUIREMENTS Zone c 13.5 psia 52 min to 14 day 7

Radiation exposure 5 x 10 rads. Not Required MARK NO.

SOV-IA202A Containment Instrument Air Isolation Valve SOV-IA202B Containment Instrument Air Isolation Valve SOV-IA20lB Containment Instrument Air Isolation Valve SOV.CC2028 Reactor Coolant Pump bearing Cooling Water SOV-CC202D Reactor Coolant Pump bearing Cooling Water SOV-CC202F Reactor Coolant Pump bearing Cooling Water

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r 58a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOtefENDED SOLUTIONS LOCA LOCA LOCA Sequential Test Franklin Institute Research A. @ficiencies:

Laboratories (FIRL) Test None Radiation followed by Environmental Report F-C4539 Exposurechemical spray.

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O O 59 Qualification and Evaluation Egt!!PMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator 1 x 10s rads (based on 120 days LOCA) I x 10s rads for 120 days MANUFACTURER ENVIROMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Limitorque Operator - Reliance class B Insulation 2 X 10 7 :ada I 2 X 107 Hads 2500 F SUPPLIER 100/. humidity Test Dt. ration- 15 days Same as above W--,--

Not Re cired p

Unknown FUNCTION Containment Isolation LOCATION Auxiliary Building - Zone N Rod Control Room MMK NO.

MOV-IIV 200D 1.C Purge System Exhaust '.alve MOV-ifV 201 1;C Parge System bypass Valve i

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59a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCt!?fENT AND REDYetENDED SOLtrTIONS D-ficiencies and Solutions

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l Nuclear QualifLcation Sheet Have supplied data to Limitorque Dated L1/t /79 of serial and wor k order numbers.

Limitorque is in process of deter-mining schedule for providing any and all qualification data available.

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V 60 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERAEM YTv org qn m m Sr:lenoid Operated Valve ifELB SOV will perform ats function of closing isolation valve within 60 seconds of MANUFACTURER 1.5 x 104 rads receiving signal.

Asco ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Model #HT-8316-D47 See Qualification Deficiencies See Qualification Deficiencies SUPPLIER ACCURACY REQUIREMENTS Fisher Not Required P.O.

FUNCTION Containment Isolation IDCATION Main Steam Valve House MARK NO.

SOV-MS201A Main Steam line trip SOV-MS20lB Main Steam line trip SOV-MS20lC Main Steam line trip

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61 Qualification and Evaluation Equ!IttENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS E/P for Flow Control Valve Loss of Coolant Accident (LOCA Radiation) LOCA MANUFACTURER LOCA: 5 x los rads 5.04 x 108 rads 40 YR: 3.5 x 104 rads 120 days Copes-Vulcan TOTAL: 5.03 x los rads SUPPLIER ENVIRONMENT TO WillCH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Copes-Vulcan IACA See Qualification Deficiencies A.

P See Qualification Deficiencies ACCURACY REQUIREMENTS N/A Accuracy to be determined FUNCTION Normal Charging Flow Control I.OCATION Auxiliary Building Zone A MARK NO.

E/P for FC-2122 Charging Flow Control to Regenerative lleat Exchange

61a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCIMENT AND RECOMMENDED SOLITTIONS LOCA LOCA LOCA See Qualification Deficiencies None A. Deficiencies:

Information not available on component qualification.

B. Solutions:

Component manufacturer contacted to obtain existing data.

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I 62 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Valve Operator Loss of Coolant Accident (LOCA) LOCA & MSLB MANUFACTURER 280 F 0-30 min SOV will perf orm its function of closing Reduce from 280 F 30-60 min isolation valve within 60 see of receiving ASCO 150 F >60 min signal. Failure of SOV will not cause to 110830281U 45 psig 0-30 miu reopen.

Reduce from 45 >60 min SUPPLIER OPERABILITY DEMONSTRATED 4.8 x 10 7 rads Same As Above LOCA & MSLB Spray: 0.4 hr solution of boric acid 2

1:O;. (2,000-2,100 ppe boron) buffered to a Fungtioned properly for 14 days at pH of 8.5 to !! with NaOH >4 hr similar 150 F af ter 50 Mrad radiation exposure.

solution with a pil of 7 to 9.

ACCURACY REQUIREMENTS FUNCTION Main Steam Line Break (MSLB)

Containment Isolation 430 F 0 to 2 min 280 F 2 to 60 min LOCATION 150 F >60 min 45 psig 0 to 30 min Inside Containment Reduce from 45 30 to 60 min to O >60 min MtRK No. 3x10gsig rads SOV-CC-201H RCP Thermal Barrier Hdr ENVIRONMENT TO WHICII EQUIPMENT IS QUALIFIED SOV-CC-205A,B&C Cont Recirc Air Clr Outlet LOCA

& Ins Cont SOV-DA-2008 Cont Sump Pp Disch Isol Viv 460 F 0 to 2 min SOV-DG-2008 Pri Drn Xfer Pp Disch Reduce from 460 F to 340 F 2 to 8 min Isol Viv Reduce from 340 F to 240 F 8 to 35 min SOV-SS-200A Press Liquid Space Cont 150"F 52 min to 14 days Isol Viv 129 psia 0 to 2 min SOV-SS-201A Press Vapor Space Sample  !!8 psia 2 to 32 min Cont Isol Viv Reduce from 118 to 25 psia 32 to 34 min SOV-SS-202A Pri Coolant Cold Les Sample 13.5 psia 52 min to 14 days Cont Isol Viv SOV-SS-204A Press Relief Tk Gas Space Radiation exposure 5 x 107 rads Cont Isol Viv SOV-SS-206A Pri Coolant Hot Leg Sample HSLB Cont Isol Vlv SOV-SS-212A Stm Gen Sample Cont Isol Viv Encompassed by above LOCA test SOV-VG-2008 Pri Drn Xfer Tk Vent SOV-RM-200C Radiation Monitoring Isol Viv

r 62a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES QUALIFICATION DOCUMENT AND RECOMMENDED SOLL7 IONS MANNER OF QUALIFICATION LOCA & NSLB LOCA & MSLB LOCA & MSLB Sequential Test Franklin Institute Research A. Deficiencies:

Laboratories (FIRL) Test Radiation followed by Environmental Report F-C4539 I) Valves were not subjected to Exposure a chemical spray B. Solutions:

1) Valves not subject to spray since valves will have performed their intended function prior to initiation of spray.

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W-1 Qualification and Evaluation EQtRMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Flow Transmitter Loss of Coolant Accident (LOCA) LOCA and Main Steam Lit.e Break (MSLB)

MANUFACTITRER

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280 F 0 to 30 minutes 120 days at 150 F Reduce irom 280 F Foxboro tof50F 30 to 60 minutes Model E13DH 150 F >60 minutes O NRABILITY DEMONSTRATED 45 psig 0 to 30 minutes SUPPLIER Reduce from 45 LOCA AND HSLB to O psig 30 to 60 e6.ates Westinghouse Electric Corporation 0 psig >60 minutes 380 F Nuclear Steam Supply System 6.8 x 10s Rads 280 F 20 minutes 280 F to 220 F 20 minutes P.O. Spray: 0.4 hr solution of boric acid tog 4hr (2,000-2,100 ppm boron) buffered to a pH 220 F for 15 days N/A of 8.5 to 11 with NaOH > 4 hr similiar Solution with a pH of 7 to 9.

FUNCTION ACCURACY REQUI_REMENTS MSLB

1. Emergency Core Cooling / Core Heat Removal , See Qualification Deficiencies

2. DBA (LOCA and MSLB) Mitigation 280 F 2 to 60 minutes ACCURACY DEMONSTRATED 150 F >60 minutes LOCATION 45 psig 0 to 30 minutes See Qualification Deficiencies Reduce from 45 Inside Containment to O psig 30 to 60 minutes O psig >30 to 60 minutes MARK NO. 3.4 x 10* Rads FT-2414, Loop I Reactor Coolant Flow Indication ENVIRONMENT TO W:IICH EQUIPMENT IS QUALIFIED FT-2415, Loop 1 Reactor Coolant Fow Indication FT-2416, Loop i Reactor Coolant Flow Indication IDCA FT-2424, Loop 2 Reactor Coolant Flow Indication FT-2425, Loop 2 Reactor Coolant Flow Indication 0 to 280 F 0 to 3 see FT-2426, Loop 2 Reactor Coolant Flow Indication 280 F at 75 gsig 3 to 1,200 see FT-2434, Loop 3 Reactor Coolant Flow Indication 280 F to 220 F 20 minutes to 24 hr FT-2435, Loop 3 Reactor Coolant Flow Indication 220 F 1 to 15 dayt.

FT-2436, Loop 3 Reactor Coolant Flow Indication Radiation: 5 x 107 rads - Gamma Spray: 1.14 wt % boric acid and 0.17 wt 1 NaOH dissolved water for 24 hr.

MR 380 F at 75 psig, 100% RH Radiation: 1.13 x 105 rads - Gamma

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OUALIFICATION DEFICIENCIES MANNER OF QtlALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA AND HSLB IDCA LOCA AND NSLB l

l Test WCAP-8541 Comment MSLB In the process of verifying that the transmitters at NA2 are those l WCAP-8541 to which the qualifications data applies. Letter has been sent to manufacturer in this regard.

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LJ' W-2 Qualification and Evaluation EQUl_PMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Level Transmitters Loss of Coolant Accident (thCA) _LOCA MANUFACTURER 280 F 0-30 min 120 days @ 150 F Reduce from 280 F 30-60 min Westinghouse Electric Corporation 150"F >60 min OPERABILITY DEMONSTRATED (2)

Nuclear Steam Supply System 45 psig 0-30 min Reduce from 45 to 30-60 min M SUPPLIER 0 psig >60 min Barton 4.8 x 107 rads (1)

Model 386/752*

Spray: 0.4 hr solution of boric acid ACCURACY REQUIREMENTS A.

P (2,000-2,100 ppa boron) buffered to a pit of 8.5 to 11 with Na0ll >4 hr similar +10% for <5 min N/A 1010 solution with a pil of 7 to 9.

FUNCTION Main Steam Line Break (MSLB) ACCURACY REQUIREMENTS

1. Emergency Core Cooling / Core lleat Removal 430 F 0 to 2 min 0 to 5 min <5%

2. Engineered Safety Feature 280 F 2 to 60 min Maximum error 5 minutes to 4 months

3. DBA (LOCA and/or MSLB) mitigation 150 F >60 min 17%

45 psig 0 to 30 min IDCATION Reduce frne 45 to 30 to 60 min 0 psig >60 min, to 24 hr Inside Containment MARK NO. 3 x 107 rads LT-2459 Pressurizer Level Transmitter ENVIRONMENT TO W1IIClf EQUIPMENT IS QUALIFIED LT-2460 Pressurizer Level Transmitter LT-2461 Pressurizer Level Transmitter LOCA

• 386/752 is prototype of 764 0 to 280 F 0-3 sec Lot I testing is applicable to prototype 280F@7gpsig 3-1,200 sec 280 F-220 F 20 min to 24 hr 220 F 1 to 15 days Radiation: 5 x 107 rads Spray: 1.14 wt % boric acid and 0.17 wt %

Na0li dissolved in water for 24 hr.

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f W-2a Qualification and Evaluation (Cont'd)

ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED (Cont'd)

MSLB 380 F @ 75 psig 100% RH Radiation: 1.13 x 105 rads QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION IXJCUMENT AND RECOMMENDED SOLUTIONS LOCA LOCA LOCA Test - Sequential Westinghouse Electric Corporation A. Deficienceis:

NS-TMA-1950 None Anderson to Stolz MR NS-TMA-2120 A. Deficiencies:

Anderson to Stolz Qualified to 380 F MSLB, peak temperature is 430 F.

Test B. Solutions:

Stone & Webster Calc # II715-ES-169-0 dated 3/10/77 Temperature qualification is acceptablesgneetemperaturere-duced to 280 F af ter 2 minute, due to thermal inertia, internal temperature rise stays within qualified limits. See Temperature Calculation #ES-169.

Comments Will be replaced after 2nd refueling

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W-3 Qualification and Environment Equ!PrtENT DESCRIPTION DESCRIPTION OF ENVikONMENT OPERABlf.!TY REQUIR_FMENTS Steam Pressume Transmitter Loss of Coolant Accident (LOCAJ 220 F for 90 seconds 1x 10 8 Rads MANUFACTlikER Foxboro Main Steam _Line Break (MSLB) OPERABILITY DEMONSTRATFD Model EllGM Approximately 220 F 300 F for 2 hr StiPP_L f ER 100% Relative Humidity Westinghouse Electric Corp.

Nuclear Steae 'bpply System ACCURACY REQUIREMENTS ENVIRONMEN1TO VIIICli EQUIPMENT IS QUALIFR P.O. 113 h03 Spray with 9.25 to 10 pli @ 300 F and 60 ps g for 2 hr, ther. reduced to 8.5 pH N/A 6244{Fand20psigfor22additionalhr.

Spray rate of 4 gal /hr/f t2 A_CCl: RACY DEMONSTRATED 8

Fl:NCTION

~ ~ ~ ~ ' ~

Ganana radiation dose of I x 10 rads /hr See Qualification Deficiencies for total of 7.6 x 10 7 rads for N0148NL DBA (LOCA and MSLB) Mitigation amplifier assemblies, which consist of prototype amplifier designed for nuclear service and having a radiation-resistant LOCATION wiring harness. A total dose of 2.2 x lo s rads for N0148ND amplifier assemblics, which Outside Containment - Quench Spray consist of standard E10 units with radiation-resistant wiring harness.

M\PK No.

PT-2476, Steam Generator 1 Steam Pressure Transmit ter PT-2486, S'eam Generator 2 Steam Pressure Transmitter PT-2496, .:iteam Generator 3 Steam Pressure Transmitter

t W-3a qualification and Evaluation (Cont'd)

QUALIFICATIONS DEFICIENCIES MANNER OF Qt/ALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS IDCA & MSI.fl LOCA LOCA & MSLB Test WCAP-8541 Conunen t MSLB In the process of verifying that the transmitters located at NA 2 are equipped with amplifiers which have WCAP-8541 been tested to the subject environment.

Letter has been sent to manufacturer in this regard.

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I W-4 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Limit Switches (Located on Valve) Loss of Coolant (LOCA) LOCA & MSLB MANUFACTURER 280 F 0-30 min Valve to close within 60 sec of isolation Reduce from 280 F tn 15 F 30-60 min signal. Switches shalt <wt fait so as NAMCO 150"F > min to reopen valves.

EA-180 45 psig 0-30 min Reduce from 45 to 0 psig 30-60 min See Qualification Deficiencies SUPPLIER 0 psig >60 min Westinghouse Electric Corp. 4.8 x 107 rada (1)

Nuclear Steam Supply System Spray: OPERABILITY DEMONSTPATED P.O.-

0-4 hr solution of boric acid (2000-2100 ppe LOCA & MSLB NA 1010 boron) buf fered to a pH of 8.5 to 11 with NaOH

>4 hr similar solution with a pit of 7 to 9. Limit switches shown to operate after FUNCTION sequential testing.

Main Steam Line Break (MSLB)

Containment Isolation 430 F 0 to 2 min LOCATION 280 F 2 to 60 min 150 F >60 min Inside Containment 45 psig 0 to 30 min

• Below Submergence Level Reduce from 45 to o psig 30 to 60 min MARK NO. O psig >60 min

• HCV-2200A Regeneration Heat Outlet 7 3 x 10 rads ACCURACY REQUIREMENTS

• HCV-2200B Regeneration !! cat Outlet

• HCV-2200C Begeneration Heat Outlet ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED Wot Required SOV-2842 Radiation Monitoring Line LOCA Heat aging @ 200*F for 200 hr, mechanical aging 100,000 cycles under electrical load 340*F 0 to 3 hr Reduce from 340'F to 120'F 3 to 5 hr SEQUENCE REPEATED 250'F to 3.5 days 200'F 3.5 to 30 days 70 psi 0 to 8 hr 10 psi . i- to 30 days

O O W-4a Qua18fication and Evaluation DESCRIPTION OF ENVIRONMENT (Cont'd)

Radiation Exposure 2.04 x los rads Spray: Boric acid and water buffered to a pH of 10-11 with Na0h solution for 4 days, water spray for 26 days, spray density = .015 gps /ft 2 HjlB Maximum surface temperature is 285'F per ESG calculation ll712-ES-197-0 dated 3/16/78, and is well below qualifi-cation temperature.

Radiation Exposure - See LOCA test QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION ACUMENT AND RECOMMENDED SOLtrfl0NS IDCA LOCA LOCA Sequential Test Report entitled: None

" Qualification of NAMCO controls limit switch Mode EA-180 to IEEE Standards 344

('75), 323 ( 74), and 382 ('72)," dated dated /3/7A and revised 4/7/78

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W-5 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5 x 10" rads (based on 120 days LOCA) 5.035 x luk Rads In addition the 40 yr radiation dose of Limitorque 3.5 x 104 for a total of 5.035 x 10' rads OPERABILITY DEMONSTRATED Operator - Reliance Class RH Insulation ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED 2 x 10s Rads SUPPLIER 180 C for 100 hrs ACCIMACY REQUIREMENTS Westinghouse Electric Corporation 2 x los rads, gamma source Nuclear Steam Supply System Not Required P.O.

NA - 1010 FUNCTION

1) Emergency Core Cooling / Core Heat Removal

2) Engineering Safety Feature LOCATION Safeguards Area MARK NO.

NOV-2860 A, Low Head Safety Injection Pump Suction Valve HOV-2860 B, Low Head Safety Injection Pump Suction Valve MOV-2885 A, Low Head Safety Injection Recirculation Valve NOV-2885 B, Low Head Safety Injection Recirculation Valve

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W-Sa Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCLHENT AND RECOMMENDED SOLIJTIONS Test Westinghouse Electric Corp. A. Deficiencies:

NS-CE-692 None B. Comment:

llave supplied Limitorque wi*b the serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available, to assure that these valve operators are covered under the referenced testing.

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W-6 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve Loss of Coolant Accident (LOCA) 120 days @ 150 F MANUFACTURER 28C F 0 to 30 min Reduce from 280 F Limitorque to 150 F 30 to 60 min OPERABILITY DEMONSTRATED 45 psig 0 to 30 min SUPPLIER Reduce frca 45 to O psig 30 to 60 min 2 x 107 rads Westinghouse Electric Corporation 0 psig >60 miu Nuclear Steam Supply System 4.8 x 107 rads P.O.- Spray: 0-4 hrs solution of boric ACCURACY REQUIREMENTS acid (2000-2100 ppe boron) buffered NA - 1010 to a pH of 8.5 to 11 with NaOH > 4 Not required.

hrs similar solution with a pH of FUNCTION 7 to 9.

Containment Isolation Main Steam Line Break (MSLB)

IDCATION 430 F 0 to 2 min 280 F 2 to 60 min Inside containment 150 F > 60 min 45 psig 0 to 60 min MARK No. O psig > 60 min 3 x 107 (rads)

MOV-2380 RCP Scalwater return ENVIRONMENT TO Mf!CH EQUIPMENT IS QUALIFIED LOCA 2 x 107 rads 250'F 100% humidity Test Duration: 15 days

. . , _ . - , -_ . . . . _ . . _ . . . . . _ . _ _ _ . . . . . . . - . . . . . . ~ , _ _ . . . . _ _ . . _ . . . _ _ . _ . . . _ . . . _ . . . _ . m. . _ . -. _ _ . _ . _ . _ _ . . . _ _ _ _ . . _ . . . , _ _ . _ . . _ , , _ , . . . _

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Qualification and Evaluation (con't)'-

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QUALIFICATION DEFICIENCIES l". HANNER OF QUALIFICATION . QUALIFICATION DoctlMENT- . AND RECOMMENDED SOLUTIONS

j. See Qualification Deficiencies Westinghouse was audited on May'29'and LOCA & MSLR j _30, 1980. ~ Insufficient qualification

i. information was available to determine - A. Deficiencies l acceeptability of Limitorque operators to j' accident environment. Qualification information was

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inadequate.

B. Solutions Have1 supplied Liaitorque with the=

l serial and work order numbers. 4i

j. Limitorque is in the process of determining schedule for providing  ;

any qualification data which is available, i .!

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W-7 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Pressure Transmitters Loss of Coolant Accident (LOCA LOCA & MSLB HANUFACTURER LOCA 120 days @ 150 F Barton- 280*F 0-30 min .

Model 763 (Lot 1) Reduce from 280*F to 150*F 30-60 min OPERABILITY DEMONSTRATED (2).'

! 150'F >60 min SUPPLIER 45 psig 0-30 min LOCA & MSLB Reduce from 45 to O psig 30-60 min

. Westinghouse Electric Corporation 0 psig >60 min 212 days @ 150 F Nuclear Safety Supply System i P.O.: . Spray: 0.4 hr solution of boric acid (2000-2100 ,

ppa boron) buffered to a pH of 8.5 to 11 N/A 1010 with NaOH >4 hr similar solution with a pH of 7 to 9.1.

FUNCTION

1. Emergency Core Cooling / Core Heat Removal

2. Engineered Safety Features

3. DBA (LOCA and/or MSLB) mitigation LOCATION Main Steam Line Break (MSLB) ACCURACY REQUIREMENTS Inside Cchtainment 430*F 0 to 2 min +10% for <5 min 280*F 2 to 60 min 5 min to I months 1 MARK No. 150*F >60 min 125%

, 45 psig 0 to 30 min PT-2455 Pressurizer Pressure Transmitters Reduce from 45 to O psig 30 to 60 min PT-2456 Pressurizer Pressure Transmitters O psig >60 min PT-2457 Pressurizer Pressure Transmitters 3 x 107 rads ACCURACY DEMONSTRATED t <5% for 5 min maximum ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED Error 5 min to 4 months 17 %

LOCA 0 to 280*F 0-3 sec 280*F @ 75 psis 3-1,200 sec (20 min) 280'F to 220*F 20 min - 24 br 220*F 1 to 15 days Radiation: 5 x 107 rads - Gamma Spray: 1.14 wt 1 boric acid and 0.17 wt % NaOH dissolved water for 24 hr

. . . . - . . . .- . . . . . . .. . - .. . , - . . -.. . . _ .. .. - - . . - . . . . . ~ _ ,_. .

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W-7a Qualification and Evaluation DESCRIPTION OF ENVIRONMENT (Cont'd)

MSLB -t 380*F @ 75 psig 100% RH Radiation: 1.13 x 105 rads -Gamma QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND REC 0t9 FENDED SOLl!TIONS Test-Sequential WWstinghouse Electric Corp. LOCA NS-TMA-1950 A. Deficiencies:

. Anderson to Stolz Test data does not match NS-TMA-210 B. Solutions:

1 Test satisfies overall envelope 3 Anderson to Stola requirements.

(Test) MSLB

. Stone & Webster Calc flI715-ES-169-0 A. Deficiencies:

dated 3/10/77 Qualified to 380*F HSLB, peak temperature is 430*F.

4

' B. Solutions:

! Temperature qualification is acceptable since temp reduced to 280*F after 2 min, I

due to thermal inertia, internal tempera-ture rise stays within qualified limits.

See Temperature Calculation #ES- 169.

I C. Comments:

r Will be replaced during 2nd

, refueling.

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W-8 Qualification and Evaluation EQUIMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5 x 108 Rads (based on 120 day LOCA) 5 x 108 Rads Limitorque Operator - Electrical Apparatus Class H Insulation SUPPLIER ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Westinghouse Electric Corporation 180 C for 100 hrs See Qualification Deficiencies Nuclear Steam Supply System 2 x 10a Rads, Gamma Source P.O.

NA-1010 FUNCTION

1. Emergency Core Cooling / Core IIcat Removal

2. Engineered Safety Feature LOCATION ACCURACY REQUIREMENTS Safeguards Area Not Required.

MARK NO.

NOV-2890A, Low Ilead Safety Injection Line Stop Valve

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W-8a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLlTTIONS Test Vestinghouse Electric Corporation A. Deficiencies:

NS-CE-692 None B. Conument:

Have supplied Limitorque with the i serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available, to assure that these valve operators are covered under the refer-enced testing.

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W-9 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Operated Valve Loss of Coolant Accident (LOCA) LOCA & MSLB HANUFACTURER 280 F 0-30 min Valve to close within 60 min Reduce from 280 F 30-60 min of isolation signal.

ASCO 150 F >60 min HT8300B64RU 45 psig 0-30 min Reduce from 45 to SUPPLIER 0 psig 30-60 min 0 psig >60 min OPERABILITY DEMONSTRATED Westinghouse Electric Corporation 4.8 x 107 rada (1) LOCA & MSLB Nuclear Steam Supply System Spray: Functioned properly for 14 days at 150 F P.O.. af ter 50 Mrad radiation exposure.

0-4 hr solution of boric acid (2,000-2,100 ppm NA - 1010 boron) buffered to a pH of 8.5 to 11 with HaOH

>4 hr similar solution with a pH of 7 to 9.

FUNCTION Main Steam Line Break (MSLB) ACCURACY REQUIREMENTS Containment Isolation 430 F 0 to 2 min Not Required LOCATION 280*F 2 to 60 min 150 F >60 min Inside Containment 45 psig 0 to 30 min Reduce from 45 to 30 to 60 min Below Submergence Level 0 psig >60 min MARK No. 3 x 107 rads SOV-2206A Letdown line ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED SOV-2200B Letdown line SOV-2200C Letdown line LOCA 460 F 0 to 2 min Reduce from 460 F to 340 F 2 to 8 min Reduce from 340 F to 240 F 8 to 35 min 150 F 56 min to 14 days 129 psia 0 to 2 min 118 psia 2 to 32 min Reduce from 118 to 25 psia 32 to 34 min 13.5 psia 52 min to 14 days

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W-9a Qualification and Evaluation (Cont'd)

ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED (Cont'd)

Radiation Exposure 5 x 10 7 rads MSLB Encompassed by above LOCA test QUALIFICATION DEFICIENCIES HANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA & MSLB LOCA & MSLB LOCA & MSLB Sequential Test Franklin Insitute Research A. Deficiencies:

Laboratories (FIRL), Test Report F-C4539 1. Valves were not subjected to a chemical spray.

2. Time, temperature envelope is not adequate.

3. Submergence (valve below submergence level).

B. Solutions:

1. Valves not subject to spray since valves will have performed their intended function prior to initiation of spray.

2. SOV will perform its function within 60 sec of receiving signal and will not misoperate if SOV fails due to temperature.

3. This codel is of water proof type.

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W-10 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Solenoid Valve Operator Loss of Coolant Accident (LOCA) Valve to close withir. 60 see MANUFACTURER 280 F 0-30 min Reduce from 280 F 30-60 min ASCO 150 F >60 min HT831654 45 psig 0-30 min OPERABILITY DEMONSTRATED Reduce from 45 >60 min SUPPLIER None 4.8 x 107 rads (1)

Westinghouse Electric Corporation Nuclear Steam Supply System Spray- 0.4 hr salution of boric acid (2,000-2,100 ppe boron) buffered to a P.O. pH of 8.5 to 11 with Nat.t >4 hr similar ACCURACY REQUIREMENTS solution with a pH of 7 to 9.

N/A 1010 Not Required Main Steam Line Break (MSLB)

FUNCTION 430*F 0 to 2 min Containment Isolation 280 F 2 to 60 min 150 F >60 min LOCATION 45 psig 0 to 30 min Reduce from 45 to 30 to 60 min Inside containment 0 psi >60 min 3x10g rads MARK NO.

SOV-2460A,B Letdown Line Loop 1 & 2 ENVIRONMENT TO WHICli EQUIPMENT IS QUALIFIED SOV-2842 Containment Isolation LOCA & MSLB None

)

r W-10a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS IDCA & MSLB LOCA & MSLB LOCA & MSLB None None A. Deficiencies:

No Qualification B. Solutions:

Westinghouse Electric Corporation Refer to NS-CE-755, dated August 15, 1975 " Fail Mode Analysis for Safety-related Solenoid Valves in an Accident F.nvironment" submitted to NRC.

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W-11 ou911f1 cation and Evaluation EOUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMFNT OPERARILI1Y REOUIREMENTS Hotor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA1 LOCA MANUFACTURER 5 x 10 6 Rads (based on 120 days LOCA) 5 x 10 6 Rads 40 dose negligthle Limitorque Operator - Peerless Motor Class R Insulation SUPPLIER Westinghouse Electric Corporation FNVIRONMENT_TO WIIICil EOUIPMENT IS OUALIFIED OPERARILITY DEMONSTRATED P.O.? 2 x 10 7 Rads 2 x 107 Rads 250 %

NA-1010 100% Humidity Test Duration: 15 days FUNCTION

1. Emergency Core Cooling / Core Ifeat Removal ACCURACY REDIIIREMENTS

2. Engineering Safety Feature Not Required LOCATION Safeguards Area MARK NO.

MOV-2862A, Low Head Safety injection Suction Valve MOV-2862B, Low itead Safety Injection Suction Valve MOV-28908, Low Ilead Safety injection Line Stop Valve MOV-2890C, Low !! cad Safety injection Line Stop Valve MOV-2890D, Low Head Safety injection Line Stop Valve I

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W-11a Oualification and Evaluation (Cont'd)

OUALIFICATION DEFICIENCIES OITA1.IFICATION DOCIntENT AND RECOMMENDFD SOLUTIONS MANNER OF OIIALIFICATION Limitorque Nuclear Qualification A. Def f e tencies_:

Test Data Sheet, dated 11/1/79 Qualification information was inadequate.

B. Solution:

Itave supplied Limitorque with the serial and work order number.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

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W-12 Qualification and Evaluation FQUIPMENT DESCRIFf!ON DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Resistive Temperature Detectors Loss of Coolant Accident (LOCA) and 30 sec Post MSIB and LOCA Main Steam Line Break (MSLB)

MANUFACTURER LOCA Rosemount These RTD's have been addressed during licensing OPERABILITY DEMONSTRATED 176KS for OL. The method of determining radiation environment was identified by the NRC (see SER, 30 see Past MSLB and LOCA SUPPLIER Supplement 10). The agreement reached is listed ACCURACY REQUIREMENTS under Qualification Deficiencies and Solutions Westinghouse Electric Corporation on Page W-12a. +0.2%

Nuclear Steam. Supply System P.O. A_CCURACY DEMONSTRATED NA - 1010 +0.21 FUNCTION Post Accident Monitoring LOCATION Inside containment, in piping MARK NO.

TE-2412B, RCS Temperature Wide Range RTD TE-2412D, RCS Terperature Wide Range RTD TE-2422B, RCS Temperature Wide Range RTD TE-2422D, RCS Temperature Wide Range RTD TE-2432B, RCS Temperature Wide Range RTD TE-2432D, RCS Temperature Wide Range RTD ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED LOCA AND MSLB

> 320 F @ 66 psig Radiation: 1 x los rads l

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r W-12a Qualification and Evaluation (con't)

QUALIFICATION UEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCt! MENT f)iD RECOrtMENDED SOI.tTTIONS Test - Sequential I.00A .U3 5'.c LOCA AND MSLB WCAP-9157 Comument

%EPCO Submittal #855A for NA 1 and 2 As part of the licensing dated 11/1/79. ccessi t men t , these RTD's will be replaced during each refueling outage, until qualified components a-, available.

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w J v' W-13 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONNINT OPERABILITY REQUIREMENTS Low Head - Safety injection Pumps Loss of Coolant Accident (LOCA) LOCA MANUFACTURERS 5x10s rads (based on 120 days LOCA) 5 x los rads and 120 days Westinghouse Electric Corporation MSLR SUPPLIER Wall not see a changing environment due to MSLB Westinghouse Electric Corporation Nuclear Steam Supply System P.O.

NA - 1010 FUNCTION ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED

1. L60rgency Core Cooling / Core Heat Removal Class H insulation has been qualified to LOCA

2. DBA (LOCA and MSLB) Mitigation 2 x los rads 2 x 108 rads IhCATION Outside Containment - Safeguards Area MARK NO. ACCURACY REQUIREMENTS 2-SI-P-IA, Low Heat Safety injection Pumps A Not Required 2-SI-P-1B, Low Heat Safety Injection Pumps B l

r V-13a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENLIES MANNER OF_ QUALIFICATION QUALIFICATION DOC'hENT AND RECOMMENDED SOLUTIONS LOCA IDCA IDCA Test of Insulation Material See Qual 4fication Deficiencies Insufficient Test Data.

WCAP-8754 and WCAP-7829 infer radiation qualification of 2x108 rads for the insula-tion system. The insulation system must te confirmed by the vendor.

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O O O-W-14 Qualification and Evaluation EQUll? TENT DESCRIPTION & MARK NO. DESCRIPTION OF ENVIRONMENT OPERARILITY REQUIRDtENTS Motor Operated Valve - Valve Operator Loss of Cnolant Accident (LOCA) 5.035.x10' Raas HANUFACTURER 5x10s rads (based on 120 days LOCA)

Limitorque In additio.i. the 40 yr radiation dose of Operator - Reliance Class B Insulation 3.5x104 for a total dose of 5.035x108 SUPPLIER ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Westinghouse Electric Corporation 2 x 10' Rads 2 x 107 Rads Nuclear Steam Supply System 250 F 100% llumidity Test Duration: 15 days P.O. ACCURACY REQUIREMENTS NA - 1010 Not Required FUNCTION

1. Emergency Core Cooling / Core Heat Removal

2. Engineering Safety Feature LOCATION AcMiliary Building Zone C MARK NO.

MOV-2863A, Low Head Safety Injection Discharge Valve fl0V-2863B, Low Head Safety Injection Discharge Valve

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N s O W-14a Qualification and Evaluation (cont'd)

QUALIFICATION DEFICIENCIES MANER OF QtlAllFICATION QUALIFICATION DOCLMENT AND RECortlLNDED SOLUTIONS See Qualification Deficiencies Westinghouse was audited on May 29 A. Deficiencies:

and 30, 1980. Insufficience qualification information was available to determine Qualification inform.ntion was acceptability of Limitorque operators inadequate.

to accident environment.

B. Solutions:

llave supplied Limitorque with the serial and work order numbers. Limitorque is in the process of determining schedule for providing any qualification data which is available

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r W-15 Qualification and Evaluation EQUIIHENT DESCRIPTION DESCRIPTION OF ENVIRONMSNT OPERABILITY REQUIREMENTS Hotor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA H UFACTURER g 5x108 rads (based on 120 days LOCA) 5x10s rads (based on 120 days LOCA) 40 yr Jose negligible Limitorque Operator - Peerless Class B Insulation SUPPLIER: ENVIRONMENT To kilICll EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Westinghouse Electric Corporation 2 X 107 Rada 2 X 107 Rads Nuclear Steam Supply System 2$0*F DX4 Humidity P.O.. Test duration- LS days NA-1010 FUNCTION

1) Emergency Core Cooling / Core lleat Removal

2) Engineering Safety Feature LOCATION ACCURACY REQUIREMENTS Safeguards Area Not Required MARK NO.

HOV-2864A, Low Ilead Safety Injection Discharge V ..e MOV-2864B, Low Head Safety Injection Discharge Valve MOV-2885C, Low Head Safety Injection Recirculation to Charging Valve HOV-2885D, Low Head Safety Injection Recirculation to Charging Valve l

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J W-15a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATIO?! DOCUMENT AND RECOMMENDED SOLUTIONS Test Limitorque Nuclear Qualification A. Deficiencies:

Data Sheet, dated 11/1/79.

Qualification information wis inadequate.

B. Solution:

Have supplied Limitorque with the serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

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I W-16 Qualification and Evaluation EJUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) 1.035xtos Rads MANUFACTURERS 1x10s rads (based on 120 days LOCA)

Limitorque .

In addition, the 40 yr radiation dose of Operator - Reliance Class B Insulation 3.5x104 for a total dose of 1.035x10s rads.

SUPPLIER Westinghouse Electric Corporation Nuclear Steam Supply System P.O.

NA - 1010 FUNCTION ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED

1) Emergency Core Cooling / Core Heat Removal 2 x 10 7Rads 2 x 107 Rads 250 F

2) Engineered Safety Feature 2001 Ilumidity Test Duration: 15 days LOCATION i

Auxiliary Building Zone L MARK NO. ACCURACY REQUIREMENTS MOV-2115C, Charging Pump Suction - Vol. Not Required.

Control Tank MOV-2tl5E, Charging Pump Suction - Vol.

Control Tank

r W-16a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECO*tMENDED SOLUTIoriS Test Limitorque Nuclear Qualification A. Deficiencies:

Data .>neet, dated 11/1/79.

Qualification information was inadequate.

B. Solution:

Limitorque has been supplied with serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

8 ...._._. ... -

W-17 Qualification and Evaluation EQUllitENT DESCRIPTION DESCRIPTION CF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCAJ 1.04 x los rads MANUFACTURER 1 x 10s rads (based on 120 days LOCA)

Limitorque In addition, the 40 yr radiation dose of Operator - Reliance Class B Insulation 3.5 x 104 for a total dose of 1.035 x 10s rads.

SUPPLIER I

Westinghouse Electric Corporation Nuclear Steam Supply System ENVIRONMENT TO Wil!CH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED

-P.O.. 2 x 107 Rads 2 x 107 Rads 250 F NA-1010 100% llumidity Test Duration: 15 days FUNCTION

1) Emergency Core Cooling / Core lleat Removal

2) Engineering Safety Feature LOCATION ACCURACY REQUIREMENTS Auxiliary Building Not required Zone I .

MARK NO.

MOV-2350, Emergency Boration Valve 4

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0 W-17a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICAT!nN QUALIFICATION DOCUMEW' AND RECOMMENDED SOLUTIONS Test Limitorque Nuclear Qualification Deficiencies:

Data Sheet, dated 11/1/79 Qualification information was

inadequate.

Solution:

Have supplied Limitorque with the serial and work order numbers.

Limitorque is in the process of l determining schedule providing any qualification data which is available.

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W-18 9

Qualification and Evaluation EQUIPMENT DESCRIPTION

• DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA} 5.035 x IOS Rads MANUFACTUNER 5 x 10 8Rads (based on 120 days LOCA)

Limitorque in addition, the 40 yr radiation dose of Operator - Reliance Class B Insulation 3.5 x loi for a total dose of 5.035 x 108 SUPPLIER Westinghouse Electric Corporation Nuclear Safety Supply System P9 1 4 NA-1010 . ENVIRONMENT TO Wil!CH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED FUNCTION 2 x 107 Rads 2 x 107 Rads

{50 F

1. Emergency Core Cooling / Core Heat Removal 100% 'sur;idity ACCURACY FEQUIby.1ENTS

2. Engineering Safety Feature Test duratione 15 days Not Required LOCATION Auxiliary Buuding MARK N0; Zone B HOV-2267 B, Low Head safety injectiou to charging pump MOV-2269 B, Low Head & Volume control tank discharge to charging pump NOV-2270 B, Low Head & Volume control tank discharge to charging pump NOV-2275 A, Charging pump to recirculation stop valve MOV-2275 B, Charging pump to recirculation stop valve NOV-2275 C, Charging pump to recirculation stop valve Zone E MOV-2370, Charging pump to seal water recirculation stop valve MOV-2373, Charging pump recirculation stop valve Zone C NOV-2836, High Head cold leg PA circulation isolation valve HOV-2869 A, Charging pump safety injection stop valve MOV-2869 B, Charging pump safety injection stop valve MOV-2381, Seal Water return stop valve

.- . . . . . - - - . . . . . , . . , - ,. - . . . - - . . - - . - - . _ . - - - . . . . - ~ ~ . . .. - . . . - - - . - -. . . , . . - . . - - . . . ~., .... , . .-.. _......

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}I Qualification and Evaluation'(ront'd)

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QUALIFICATION DEFICIENCIES  ;

j MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND REcoretENDED SOLUTIONS  ;

' Test, Limitorque Nuclear Qualifir ation A. Deficiencies: 7 Data Sheet, dated 11/1/79. Qualification informatioe was .,

inadequate.

5 B .' Solution: I f

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f. the process of determining i schedule for providing any j qualification data which is l

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r W-19 Qualitication and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA MANUFACTURER 5 x los rads (based on 120 day LOCA) 1.04 x 10s rads In addition, the 40 yr radiation dose Limitorque 3.5 x 10* rads for a total dose of Only requirements - operate to . 'ste Operator - Reliance Class B insulation 1.035 x 104 rad charging line break.

SUPPLIER High Energy Line Break (UELB) HELB Westinghouse Electric Corporation Maximum occident temperature 200 F 1. Not required to operate under adverse Nuclear Steam Supply System 100% llumiu3ty conditions for maintaining capability to (Letdown Line Break) borate after letdown line break.

P.O.

Based on a review of the postulated HELB's Coments NA-1010 it was determined that saf ety-related equipment required to mitigate the KELB 1. Valve normally open and 4-as not FUNCTION and bring the plant to a safe shutdown require change of positt-n under are not af fected by the break. However, addressed accident condition.

1. Emergency Core Cooling / Core llead Removal this equipment is being reviewed against

2. Engineered Safety Feature the effects of HELB to determine our ability Operability Demonstrated to maintain minimum location capability, LOCATION to ensure additional plant operational LOCA & HELB capabilit5 Auxiliary Building 2x107 rads 2x107 rads Zone B 250 F ACCURACY REQUIREMENTS 100% Humidity MARK NO. Test Duration: 15 days Not Required MOV-2286A, Charging Pump Discharge Valve HOV-2286B, Charging Pump Discharge Valve MOV-2286C, Charging Pump Discharge Valve MOV-2286A, Charging Pump Stop Valve MOV-2286B, Charging Pump Stop Valve MOV-2286C, Charging Pump Stop Valve

f W-19a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES ttANNER OF QUALIFICATION QUALIFICATION DOCINENT AND REcott*1 ENDED SOLUTIONS 7

Test Limit 9rque Nuclear Qualification Data Deficiencies:

Sheet, dated 11/1/79 Qualification information was inadequate.

Solution:

Have supplied Limitorque with the serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

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W-20 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF EKVIRONMENT OPERABILITY REQUIREMENTS Charging Pumps Loss of Coolant Accident (LOCA) LOCA MANUFACTURERS 40 yr integrated dose 3.5x10' rad accident 1.04x10s rads dose Ix10s rads (based on 120 days LOCA)

Westinghouse Electric Corporation MSLB SUPPLIER Will not see a changing environment Westinghouse Electric Corporation due to MSLB.

Nuclear Steam Supply System High Energy Line Break (HELB) HELB P.O.

Maximum accident tamperature 220 F 220"F for 90 sec.

NA-1010 Based on a review of the postulated HELB's, it was determined that safety-related equipment FUNCTION required to mitigate the HELB and bring the OPERABILITY DEMONSTRATED plant to a safe shutdown are not affected by

1. Emergency Core Cooling / Core Heat Removal the break. However, this equipment is being LOCA and HELB

2. DBA (LOCA and MSLB) Mitigation reviewed against the affects of HELB to determine our ability to maintain minimum 2 x 10s Rads boration capability, to assure additiooal LOCATION plant operations capability.

ENVIRONMENT TO WHICH EQUIPMENT 15 QUALIFIED ACCURACY REQUIREMENTS Outside Containment - Auxiliary Building Zone B Class H insulation has been qualified to Not R,equired 2 x los Rads MARK NO. HELB 2-CH-P-IA, Charging Pumps A (High Head See Qualification Deficiencies Safety Injection Pump) 2-CH-P-IB, Charging Pumps B (High Head Safety Injection Pump) 2-CH-P-IC, Charging Pumps C (High Head Safety Injection Pump)

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.-20a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA LOCA Q Test See Qualification Deficiencies Insufficient Test Data WCAP-8754 and WCAP-7829 infer radiation quali.Jeation of 2x108 rads for the insulation system. The insulation system must be confirmed by the vendor.

IIELB HELB KELB See Qualification Deficiencies See Qualification Deficiencies No Qualification Documentation available, actual accident environment will be developed.

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W-21 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) IDCA MANUFACTURER 40 yr integrated dose 3.5 x 10 4 rads 1.04 x 108 rads accident dose 1 x losrads (based Limitorque on 120 days LOCA) HELB Operator - Reliance Class H Insulation 220 for less than 90 see SUPPLIER High Energy Line Break (ifELB) 100% RH Westinghouse Electric Corporation Maximum accident temperature 220 F 1. Not required to operate under adverse Nuclear Steam Supply System 100% Humidity conditions for maintaining capability to (Letdown line break) borate af ter letdown line break.

13 Based on a review of the postulated IIELBs, it was determined that the safety-related 2. Required to maintain boration and NA-1010 equipment required to mitigate the HELB and charging capability for letdown bring the plant to a safe shutdoun are not line break.

FUNCTION affected by the break. Ilowever, this equipment is being reviewed against the Comments

1. Emergency Core Cooling / Core Heat Removal effects of HELB to determine our ability

2. Engineering Safety Feature to maintain minimum boration capability to Valve normally open and does not require assure additional plant operational change of position under addressed accident LOCATION capability. conditions.

Auxiliary Building ENVIRONMENT TO WlIICH EQUIPMENT IS QUALIFIED HARK NO. LOCA OPERABILITY DEMONSTRATED Zone B 2 x 107 rads -

LOCA HOV-2267A LHSI to charging pump valve 250 F NOV-2269A LSHI & valve control tank discharge 100% Humidity 2 x 107 rads to pump valve Test Duration 15 days HOV-2270A LiiSI & volume control tank discharge ACCURACY REQUIREMENTS valve Zone C Not Required MOV-2289A Charging pump discharge line stop valve MOV-2289B Charging pump discharge line stop valve

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W-21a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCLMENT AND RECOMMENDED SOLUTIONS See Qualification Deficiencies Westinghouse was audited on May 29 and 30, Deficiencies:

1980. Insufficient qualification information was available to determine acceptability of Qualification information was inadequate.

Limitorque operators to accident environment Solution Have supplied Limitorque with the serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

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v W-22 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTipN OF ENVaRONMENT OPERABILITY REQUIREMENTS tiotor Operated Valve - Valve Operator Loss of Coolant Accident (IDCA) LOCA 4 1.04 x los Rads MANUFACTURER 40 yr integratad dose 3.5 x 10 rads dose 1 x los rads (based on 120 days Limitorque IDCA)

Operator - Heliance Class B Insulation SUPPLIER High Energy Line Break (HELB) hELB Westinghouse Electric Corporation Maximum accident temperature 220 F 220 F for less than 90 sec Nuclear Steam Supply System 100% humidity 100% humidity (Letdown line break)

Based on a review of the postulated HELBs, Required to maintain baration and PA. it was determined that safety-related charging capability af ter letdown equipment required to mitigate the HELB and line break.

• NA-1010 bring the plant to a safe shutdown are not affected by the break. However, this OPERABILITY DEMONSTRATED FUNCTinN equipment being reviewed against the effects of liELB to determine our ability to maintain LOCA & HELB

1. Emergency Core Cooling / Core Heat Removal minimum boration capability to assure

2. Engineering Safety Feature additional plant operational capability. 2 x 10 7 Rad.

LOCATION ENVIRONMENT TO MIICH EQUIPMENT IS QUALIFIED ACCURACY REQUIREMENTS Auxiliary Building LOCA & IfELB Not Required Zone C 2 x 107 rads 250 F MARK NO. 100% llumidity Test Duration: 15 Days HOV-2115B, Charging pump suction from refueling water storage tank valve MOV-2115D, Charging pump suction from refueling water storage tank valve

r W-22a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS Test LOCA LCCA Limitorque Nuclear Qualification Data Sheet, Deficiencies:

dated November 1, 1979 Qualification information was inadequate.

Solution Have supplied Limitorque with the serial and work order numbers.

Limitorque is to the process of determining schedule for providing any qualification data which is available.

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W-23 Qualification and Evaluation EQUII? TENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Flow Transmitter Loss of Coolant Accident (IDCJ LOCA MANL'FACTURER 1 x 106 rads (based on 120 days LOCA) 1.04 x 10s rads Ba rton In addition, the 40 yr radiation dose of Model 384 4 x 104 rads aust be considered for a total possible radiation dose of 1.04 x SUPPLIER 10s rads. OPERABILITY DEMONSTRATED Westinghouse Electric Corporation MSLB TACA Nuclear Steam Supply System Will not see a changing environment due See Qualification Deficiencies A.

P due to MSLB.

NA - 1010 ENVIRONMENT TO WiiICH EQUIPMENT IS QUAllFIED ACCURACY REQUIREMENTE FUNCTION UQ See Qualification Deficiencies

1. Emergency Core Cooling / Core Ileat Removal See Qualificaton Deficiencies 2 DBA (IDCA and/or MSLB) Mitigation IACATION Auxiliary Building Zone C MARK NO.

FT-2940, Safety Injection lleader Flow Ilot Leg FT-2943, Boron Injection Tank IIcader Flow

W-23a Quzlification and Evaluation (Con't)

QUALIFICATION DEFICIENCIES HANNEH OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLlf7 IONS LOCA LOCA LOCA See Qualification Deficiencies See Qualification Deficiencies A. Deficiencies:

No environmental qualification data available from supplier.

B. Solutions:

Have contacted manufacturer for qualifications test information.

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W-24 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMEKT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA HANUFACTURER 40 yr integrated dose 3.5 x 10* rads accident 1.04 x los rads dose 1 x los (based on 120 days LOCA)

Limitorque ifELB Operator - Peerless Motor Class B Insulation liigh Energy Line Break (HELB) 220 F for less than 90 sec. 100% Humidity SUPPLIER Maximam accident temperature 220 f 1001 b umidity Comments Westinghouse Electric Corporation (Letdown line breakJ Nuclear Steam Supply System 1. Valve normally open and does not based on a review of the postulated HELB's require change of position under P.O.. it was determined that safety-related addressed accident condition, equipment required to mitigate the HELB NA - 1010 and bring the plant to a safe shutdown are 2. Only requirements to operate to not affected by the break. However, this isolate charging line break.

FUNCTION equipment is being reviewed against the af fects of HELB to determine our ability to 3. Not a temperature environment

1. Emergency Core Cooling / Core Heat Removal maintain minimum boration capability to assure problem.

2. Engineering Safety Feature additional plant operational capability.

LOCATION ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED Auxiliary Building LOCA and HELB LOCA and HELB Zone C 2 x 107 Rads 2 x 10 7 Rads HARK NO. 250 F MOV-2867C, Charging Pump Stop Valve 100% Humidity ACCURACY REQlJIREHENTS Test duration- 15 Days Not Required i

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r W-24a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANMER OF QtlALIFICATION

_ QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS LOCA LOCA and HELB IIXM and HELB Test Limitorque Nuclear Qualification Data A. Deficiencies:

Sheet, dated 11/1/79.

Qualification information was inadequate.

B. Solutior.

llave supplied Limitorque with the serial and work order numbers.

Limitorque as in the process of determining schedule for providing any qualification data which is availatie.

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r W-25 Qualification and Evaluation

• EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Hotor Operated Valve - Valve Operator Loss of Coolant Accident (LOCA) LOCA MAN 1WACTURER 40 yr integrated dose 3.5 x 10 4 rads 1.04 x los Rads accident dose 1 x 10s rads (based on Limitorque 120 days LOCA)

Operator - Reliance Class B Insulation SUPPLIER High_ Energy Line Break (HELB) KELB b'estinghouse Elect ric Corporation Maximum Accident Temperature 200 F 220 F less than 90 see Nuclear Steam Supply System 100% humidity 100% humidity (Let down line break) Required to maintain boration and charging capability after letdown line P.O.. Based on a review of the postulated HELB's, break.

it was determined that safety-related NA-1010 equipment required to mitigate the HELB OPERABILITY DEMONSTRAT D and bring the plant to a safe shutdown FUNCTI_0N are not affected by the break. However, 2 x 107 Rads this equipment is being reviewed against

1. Emergency Core Cooling / Corr Heat Removal the ef fec* s of HELB to determine our ability ACCURACY REQUIREMENTS

2. Engineering Safety Feature to maintain minimum boration capability to assure additional plant operational capability. Not Required LOCATION ENVIRONMENT TO kHICH EQUIPMENT IS QUALIFIED Auxiliary Building LOCA & llELB MARK NO. 2 x 107 Rads 250 F HOV-2867A, Charging pump stop valve 100% Humidity NOV-2867B, Charging pump stop valve Test Duration: 15 days MOV-2867D, Charging pump stop valve i

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W-25a Qualification and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS Test Limitorque Nuclear Qualification A. Deficiencies:

Data Sheet, dated 11/1/79. Qualitication information was inadequate.

B. Solutions:

Have supplied Limitorque with the serial and work order numbers.

Limitorque is in the process of determining schedule for providing any qualification data which is available.

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W-26 Qualifications and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUlkEMENTS Solenoid operated Valves 5. x 108 (based on 120 day SOV will perform its function LCCA dose) of closing the isolation valve 40 yr normal dose is negligible within to seconds of receiving signal MANUFACTUREI!

ASCO O_PERA31LITY DEMONSTRATED MODEL # 8321A5 SOV performed required safety ENVIRONMENT TO WHICH EQUIPMENT IS QUALIFIED function after receiving radiation dose.

SUPPLIER Wheu exps ed to 5 x 107 rads leakage developed which exhausted the pressure vessel. Solenoid Westinghouse Electric Corporation valves will have achieved safety-related function ACCURACY REQUIREMENTS within 60 seconds of an initiation signal.

P.O. The long-term failure mode will not reintroduce Not required air to a cont rol valve, therefore, the valve NA-1010 will maintain its fail-safe position.

FUNCTION Containment Isolation LOCATION Safeguards area MARK NO.

SOV-2859A- Safety injection accumulator SOV- 2859B-

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V-26a Qualifications and Evaluation (Cont'd)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION j QlALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS HELB HELB HELB Test Franklin Institute Research Laboratories A. Deficiencies:

(FIRL) Test Report F-C4539, Catalog #30.

Westinghouse Letter NS-SS-77060. Failure during radiation exposure.

t B. Solutions,i i When exposed to a radia-l tion dose of 5 x 107 rads, some plastic inards of the j SOV did disintegrate caus-i ing the valve to leak.

l However, the valve was i able to exhaust its accu-mulated pressure and per-form its safety function.

(Westinghouse letter NS-SS-77060).

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W-27 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Resistive Temperature Detectors Main Steam Line Break (MSLB) Two weeks Post MSLB KAKUFACTURER OPERABILITY DEMONSTRATED Rosemount These RTD's have been addressed during licensing Two weeks Post MSLB 176KS for OL. The method of determining radiation environment was identified by the NRC (see SER, SUPPIJER Supplement 10). The agreement reached is listed ACCURACY REQUIREMENTS under Qualification Deficiencies and Solutions Westinghouse Electric Corporation +0.2%

Nuclear Steam Supply System P.O. ACCURACY DEMONSTRATED NA - 1010 +0.2%

FUNCTION Post Acc. dent Monitoring LOCATION Inside containment, in piping MARK NO.

TE-2410, RCS Temperature Wide Range RTD TE-2413, RCS Temperature Wide Range RTD TE-2420, RCS Temperature Wide Range RTD TE-2423, RCS Temperature Wide Range RTD TE-2430, RCS Temperature Wide Range RTD TE-2433. RCS Temperature Wide Range RTD EKVIROKMENT TO WHICH EQUIPMENT IS QUALIFIED M.SLB

> 320 F @ 66 psig Radiation: 1 x los rads

W-27a Qualification and Evaluation (con't)

QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS Test - Sequential MSLB MSLB WCAP-9157 Comment VEPCO Submittal #855 dated 11/1/79 and #855A As part of the licensing for NA I and 2. commitaant, these RTD's will be replaced during each refueling outage, until qualified components are available.

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a, W-28 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve Loss of Coolant Accident (LOCA) 120 days @ 150 F MANUFACTURER

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280 F ' 0 to 30 min Reduce from 280 F Limitorque to 150 F 30 to 60 min OPERABILITY DEMONSTRATED 45 psig 0 to 30 min SUPPLIER Reduce from 45 to O psig 30 to 60 min 2 x 107 rads Westinghouse Electric Corporation 0 psig >60 min Nuclear Steam Supply System 4.8 x 107 rads P.O.. Spray: 0-4 hrs solution of boric ACCURACY REQUIREMENTS acid (2000-2100 ppe boron) buffered NA - 1010 to a pH of 8.5 to 11 with NaOH > 4 Not required, hrs similar solution with a pH of FUNCTIGN 7 to 9.

Engineered Safety Features Main Stear Line Break (MSLB)

LOCATION 430 F 0 to 2 min 280 F 2 to 60 min inside containment 150 F > 60 min 45 psig 0 to 60 min MARK NO. O psig > 60 min 3 x 107 (rads)

MOV-286aA Accumulator "ank 1 Cold Leg MOV-2865B Accumulator Tank 2 Cold Leg MOV-2865C Accumulator Tank 2 Cold Leg ENVIRONMrdT TO WHICH EQUIPMENT IS QUALIFIED I.:OCA See Qualification Deficiencies 4

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r W-29 Qualification and Evaluation EQUIPMENT DESCRIPTION DESCRIPTION OF ENVIRONMENT OPERABILITY REQUIREMENTS Motor Operated Valve - Valve Operator Loss of Coolant Accident (IOCA) 1.035x10s Rads MANtjFACTURERS 5x108 rads (based on 120 days LOCA)

Limitorque In addition, the 40 yr radiation dose of Operator - Hazardous Location will 3.5x10* for a total dose of 1.035x10 8 rads.

varify type as soon as possible.

SUPPLIER Westinghouse Electric Corporation Nuclear Steam Supply System P.O.

NA - 1010 FUNCTION ENVIRONMENT TO WHICII EQUIPMENT IS QUALIFIED OPERABILITY DEMONSTRATED

1) Eaergency Core Coolint/ Core Heat Removal Must Be Verified for Type Later

2) Engineered Safety Feature IOCATION Auxiliary Building Zone C MARK NO. ACCURACY REQUIREMENTS NOV-2836, Cold Leg Circulation Valve Not required.

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QUALIFICATION DEFICIENCIES MANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS La te r Later Later l

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O O O W-30a Qualification and Evaluation (Con't)

QUALIFICATION DEFICIENCIES NANNER OF QUALIFICATION QUALIFICATION DOCUMENT AND RECOMMENDED SOLUTIONS See Qualification Deficiencies IACA LOCA See Qualification Deficiencies We have contacted ASCO to obtain test reports, or arrange an audit.

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