Text

Reg Guide 1.97 Compliance Evaluation for Pilgrim Nuclear Power Station I
	ML20204J401
Person / Time
Site:	Pilgrim
Issue date:	09/14/1988
From:	Jeffries J; BOSTON EDISON CO.
To:	;
Shared Package
ML20204J386	List: ML20204J380; ML20204J401; ML20204J417; ML20204J443; ML20204J494; ML20204J531; ML20204J537; ML20204J557; ML20204J579; ML20204J599; ML20204K042; ML20206Q053; ML20207A530; ML20207A535; ML20207A686; ML20207A766;
References
	FOIA-88-198, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8810250121
	Download: ML20204J401 (105)
	v • d • e

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9IMitt 1

4 teaulatorv tuide 1.97 Cameliance Evaluation M

Pilerie Nuclear Power Station I t

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1 Prepared by James A. Jeffries 80ston Edison Company l

9 8810250121 800914 PDR FDIA

> JOHNSON 88-198 PDR i

L wa _ _ -- a t

Table of Contents Sununary a

1 Ioston Edisen Analysis l

l-1 Regulatory Guide 1.97 Requirements [

l i 1-1.1 Type Variables ,

1-1.2 Quality Categories l l

l-2 Bostor. Edison Database of 1.97 Variables i 1-3 Evaluation Methodology !

Results of Evaluation 1-3.1 1-3.1.1 Conf .nnance 1-3.1.2 Dev ,tions and Corrective Actions 1-3.1.3 Exceptions to Design and Qualification criteria ;

!! Conclusions 11-1 Database Maintenance 11-2 Corrective Actions on Completion of Database Information ,

11-3 Environmental Qualification '

11-4 Seismicity )

11-5 Commitment Action Plan References Appendix A l

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4 Sununary Regulatory Guide (Reg Guide) 1.97, Rev. 3 was issued to identify an acceptable method for evaluating design requirements of instrumentation necessary to monitor plant variables and systems during and following an accident. This report prestnts the results of the Pilgrim Nuclear Power Station (PNPS) Reg 1 Guide 1.91 evaluation. Its objectives are (1) to identify how 80ston Edison (IEco) meets the Reg Guide 1.97 guidance, (2) to identify deviations from the guidance, along with corresponding resolution (s) of those deviations, and (3) j to identify the consettaent schedule for correctir.g identified deviations.

The results of the PNPS Reg Guide 1.97 evaluation are sungnarized below:

Fif ty six (56) variables have been reviewed for the PNP 5 Reg Guide

] 1.97 evaluation and :'epresent the following scope:

21 Category 1 variables (779 instrument loops) 21 Category 2 variables (99 instrument loops) 14 Category 3 variables (158 instrument loops) ,

The large number of Category 1 instrument loops is attributed to the large number of isolation valve position indicators evaluated.

^

Thirty nine (39) variables comply without any need for exception or corrective action. These are iden ified in Tabid 3, Section

! 1-3.1.1. Four (4)varisbles were downgraded (see Table 2, Section l-1.2) to allow compliance. This downgrading has been based on arguments provided by the Reg Guide 1.97 8WR Owner's Group and concurred in by BECo. .

t Thirteen (13) variables do not cemply at thij time, these variables are identified on Table 4, Section I-3.1.2. Of these ;

i variables, 11 will comply when upgraded. The upgrading will require a modification, retrieval of 3dditional documentation er a combination of the two (see Table 1, Sunesary). l j Two (2) of the 13 variablet have been detignated as ' leave-as-is'

(see Table 1, Sunenary), This disposition has 'een o applisd based

I generally on one of the followinC:

(1) design configuration of the cog enents involved I (2) physical limitations (i.e., spatial) ,

(3) satisfying earlier design requir:ments (i.e., previously '

responded to in NUREG 0737) !

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The Post Accident Sampling System (PA55) will be evaluated and is i

anticipated to meet or exceed the design and qualification

! criteria for the following four (4) variables, i

RCS Soluble Boron Concentration (Sample) 4 -

Analysis of Primary Coolant (Gansna Spectrum)

- Primary Coolant and Sump I -

Radiation Level in Core Recirculation loops 1

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- One variable has varying degrees of compliance. A total of 743 l Instrument loops tere reviewed for the variable, Primary ,

Containment Isolation Valve Posttion. Of these, 598 instrume t

! locos were found not be comply vtth Reg Guide 1.97. It should te noted that a majority of the non-conformances identified for this variable could be attributed to instruments not needed to follow l . an accident. This was especially true for the insert and ,

withdrawat valves (i.e., 580 instrument loops) where the 1.97 '

l design and qualification criteria could not be applied. The l

rationale for taking exception to upgrading these I mps is l provided in Section I-3.1.2 of this report. .

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- Two (2) broad areas of exception to the Reg Guide 1.97 guidance !

were electrical isolation and channel redundancy. The bases for these exceptions are evaluated in Section I-3.1.3 of this report.

- Quality Category 1 variables reviewed for PNPS will be environmentally quallfted. The Category i variables requiring environmental qualification as a result of 1.97 guidance, will not be schedularly constrained by the 50.49 effort. Those variables are: , ,

Primary Containment Pressure Primary Containment Isolation Valve Position Post Accident Sampling System Containment and Drywell oxygen Concentration .

Drywell Temperature

- Seismic qualification review for PNPS has been deferred pending (

resolution of Unresolved Safety Issue A-4(i. The basis for this <

deferral can be found tr: Section !!-4 of this report.

- Implementation activities during Phase !! will be completed by the end of Refuel Outage 6.

This report is presented in two (2) parts:

!. Boston Edison Analysis Methodology -

The approach taken to establish conformance with Reg Guide 1.97 or need for action is shown on Figure 1. A statement regarding dotton [dtson's intent to meet Rev. 3 of Reg Guide 1,97 is provided. Design and qualtftcation information for entsting plant equipment has been collected and entered into a computertted database. A brief esplanation of the headings used in that database is presented on Figure 2. Enceptions were taken to the criteria in Reg Guide 1.97.

Theseexceptionsresultedindowngradingfour(4)variablesandare based on arguments presented by the 1.9e BWR Owner's Group and are i presented in Section I-1.2. l The technical approach used to perform this evaluation utilizes a

threshold acceptance criteria. The weighting factors used in I development of this methodology and consistently applied throughout ;

this evaluation have been based on engineering judgement and I convprsations with NRC. Boston Edison believes that its methodology i does satisfy the basic intent of Reg Guide 1.97. Corresponding results ;

indicating conformance to, exception to, or deviation from Reg Guide !

1.97 are evaluated. Improvements to correct identifled deviations are l provided, j 1

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!!. Conclusions 4 A description is gravided of how the PNPS 1.97 database will be i

! i maintained. Some of tne variables found to conform to 1.97 guidance I

may require additional information regarding specific design criteria.

. Attention to this sitVation is oddressed. A general statement of >

4 Sotton Edison's position regarding environmental Qualification of l applicable variables is Grovided. Setsmic Qualtf tcation Yecuirements i for Pilgrim are reviewed in light of Unresolved Safety !ssue. A-45. I Finally. 4 statement regarding Boston Edison's intent to complete Phase i

!! requirements per Supplement I to NUREG 0737 is eroviced.

As prescribed by Supplement I to NUREG 0737. Boston Edison has attempted to -

perform its Reg Guide 1.97 evaluation in an integrated fasnton with other l related programs. Realtzing this, it is anticipated that future sccee changes j 1

(e.g.. changes in th6 [OP's) may Cause scope changes to Reg Gulce 1.97 ;

4 compliance which will be performed under 10CFR50.59 requirements without celer notificAttor, to NRC. !

i I In submitting this document. Boston tetson satisfies its Phase ! commitment in response to Supplement 1 to huR(G 0737. ;

i A commitment sumary of PNPS tirgrovements to be implemented and e:Ceptions ,

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taken in leaving an instrument loop (s) in their present configuration are

j identified in Table 1. Sracketed numeers in the lower left-hane corner of l j eich bon represent the present degree of conformance of each varta?le, while ;

j those numbers in the lower right-hand corner identify the espected degree of '

conformance, once improvements are made. !

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Table 1 d

1 l t PNPS Comitment Sumary !

s t i I Variable !merovements' (vCeDtions' l l i

1. RPV Pressute', Type A Vartable upgrade ....... .

(This is tne same as RCS (provice for !

Pressure for Type B & C connection to !

variables. (Pressure is redundant, I indicated twice under Type safety-related l C variable.) power sources, Y3 & Y4 via I safety cabling) i i

(281 (921 i i

2. RPV Water Level' upgrade -------

j (This is a Type A & 8 (connect to re.

variable.) dundant, safety related power sources) .

(541 (1001 [

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3. Hydrogen Concentration' ------- leave as is (This acclies to the Type a and C variable designations) ;

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(621 (801 __

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'See Section I-3,1 2 for details j i

'The PNPS 1.97 evaluation indicates that this variable does not cceply with !

Reg Guide 6.97 ;

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l Table 1,_(cont'd) l Variable imorove.4mts' faceptions'_

8 4 Primary Containment Isolation f valve Positten' ;

257011 A & 5 (301---->(94) upgrade -------

(connect to ;

reduncant safety-related ;

power sources ;

via safety t cabitng) '

- '57017

. A & 5 (301---->(941 upgrade -------

(satPe as above) l

- 254002 ------- leave as is t

- Z54356 ------- leave as is !

- 259068 A & 5 (101---->(94) upgrade -------

l (Add a ,

j redundant ,

safety-related power source !

and new i position !

sultches) ,

- 258000 ------- leave as is

- Z58001 ------- leave as 15

- FCV-302-120 & 123 l

leave as is i

- SV302-121 & 122 --- --- leave as is !

- IS5065-34 & 38 ------- leave 45 is l

- Z55065-32 & 36 -- ---- leave as is l l

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S. Core Spray Flow' upgrade ------- i (insttil re-dundant in- {

ternal pceer '

supply) j (661 (96) __,

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'The PNPS It97 evaluation indicates that this variable dces not cceply with Reg Guide 1.97 Page 2 of 4

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Table 1 (con?'d)

VarlaAle Improvements

Exceptions

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6. RHR Heat Exchanger Outlet -------

Temperature' (provide QA documentation and use 3 existing com-puter hockup for trend in- )

formation) l l

{641 (801

7. Cooling Water Temperature "se existing -------

to ESF System Components' ) computer hockup ,

to provide j trend informa- 1 tion (641 (801 l

8. Radiation Exposure Rate' upgrade -------

(increase range of monitor &

continuous loop availability)

(58) (941

9. Primary Containment Pressure' Environmental -------

Qualification only (861 (Cat 11 (861 l

10. Primary Containment Isolation Environmental ------- -

Valve Position' Qualification l only (Cat 11 (76)

'The PNPS It97 evaluation indicates that this variable does not comply with Reg Guide 1.97

'This Category 1 variable will be environmentally qualit' led since it is a key variaDie. (This is exclusive of the insert and withdrawal valves position Indication)

Page 3 of 4

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I Table 1 (cont'd) 1 Variable Improvements' Exceptions' !

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11. Post Accident Sampling Environmental- --------

System 8 Qualification only 8 j 1

(Cat Il (later] !

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12. Containment & Orywell Environmental --------

Oxygen Concentration 8 Qualification only i

(Cat 11 (81) , .

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13. Drywell Temperature 8 Environmental --------

Qualification only -

(Cat 11 (90)

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This Category i variable will be environmentally qualified since it is a ;

key variable.

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- Page 4 of 4

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I-I Regulatory Guide 1.97 Requirements A tabulation of the design and qualification critoria used in performing the PNPS 1.97 evaluation l', provided in Appendix A. Although Boston Edison originally responded to Supplement I to NUREG 0737, by referencing Revison 2 of 1.97, Revision 3 was used in performing the PNPS Reg Guide 1.97 evalcation, cloce it represents the Staff's "latest thinking" regarding this guidance, s

To evaluate PNPS Accident Monitoring Instrumentation (AMI) against the criteria in Reg Guide 1.97, the following major steps were executed:

- Identification of plant specific variables (Type A thru E). See Tables 3 and 4.

- Development of a PNPS database. See Figure 2.

- Development of a methodology for evaluating PNPS Accident Monitoring Instrumentation (AMI). See Section I-3.

- Identification of those PNPS variables found to comply with dr deviate from Reg Guide 1.97. Exceptions to criteria also identified. See Sections I-3.1.1 and I-3.1.2.

- Identification of Boston Edison plans to correct identified .

deviations. See Section I-3.1.2.

- Identification of schedule for completing the above corrections.

See Section II-5.

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l Attachment to Figure 2 l

Description o' Headings Used in PNPS Reg Guide 1.97 Database ,

o AMI VAR - a unlaue number provided for each Accident3 Monitoring Instrumentation variable. This is to be used in retrieving applicable information from the computerized database.

o Equipment Number - refers to the alphanumeric designation used to identify individual plant components.

o PNPS Description - brief description of what the component is, o Location - indicates where the component is located in the plant.

o Type - refers to the type of variable (i.e., A. B, C O, or E) as defined by Reg Guide 1.97.

o CAT - refers to the design and qualification requirements that corresponds to the applicable type variable as defined in Reg ,

Guide 1.97.

o Reg'd Range - refers to the range requirement specified in Reg Guide 1.97.

o Actual Range - refers to the range provided by the actual plant component.

o MSIGI - refers to the component providing the measured signal (i.e., RTO).

o STYPE - refers to the signal output type (i.e., analog or digital),

o Actual Accuracy - refers to limits which bound the departure of a measured value from the true value of a quantity. Includes accumulated errors, o Ref Owgs - refers to drawing (s) and or supporting documentation used in identifying actual component / system configuration, o MFR - identifies the manufacturer of the components, where available, o H00 - identifies the model number of the component.

o SYS and Q-List headings are provided for internal use, e

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1-1.1 Tv9e Variables Because of plant configuration it was appropriate to group the following variables under a dif ferent single variable:

- RCS Soluble Boron Concentration (Sample) 3

- Analysis of Primary Coolant (Gamma Spectrum)

Primary Coolant and Sump

- Radiation Level in Core Recirculation Loops In these cases, the Post Accident Sampling System (PASS) will be used to evaluate conformance with Reg Guide 1.97, pending completion of system installation and associated documentation by the end of Refuel Outage #6.

This evaluation will be completed by Refuel Outage #8. Functionally, PASS will be used to monitor the above variables. The addition of this system provides Pilgrim with the capability of obtaining representative liquid and gas samples f rom within the primary containment for radiological and/or chemical analysis in association with a possible LOCA. It should be noted ,

that the recent meeting (May 2,1984) of the BWROG-TMI generated some concern about the PASS dissolved gas capability for BWR's. It is likely that Boston Edison will take exception to the 1.97 guidance pending results of near term meeting (s) with NRC (i.e.,1.97 required range is 0 - 2000 cc/kg, BWROG recommended range is 0 - 400 cc/kg). The remainder of the type variables are.

categorized in accordarce with Reg Guide 1.97.

1-1.2 Ouality Categories in the course of performing the Reg Guide 1.97 evaluation, general design requirements for certain Reg Guide 1.97 variables were reduced consistent with positions provided by the Reg Guide 1.97 BWR Owners Group. A particular variable may have been identified as Category 1 by the Reg Guide, but was reduced to Category 3, for example, based on the rationale submitted by the Reg Guide 1.97 BWR Owners Group. The effected variables and their corresponding rationale are identified in Table 2.

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Table 2 i Downcrace of 1.97 Design Requirements Variable R.G. Cat./PNPS Cat. Reason

1. Drywell Sump Level 1/3 % sed on the Bd Owner's Group reccmmendation, the drywell sump level neither automatically initiates safety related systems nor alerts the operator to the need to take safety related actions during and following an accident. The designation has been changed from Category 1 to Category 3.

2. Drywell Orain Sump 1/3 Based on the BWR Owner's Level Group recommenJation, the drywell sumo level neither ,

automatically initiates ;

safety related systems nor alerts the operator to the I need to take safety related actions during and following an accident. The designations has been changed ,

from Category 1 to Category 3. l l

3. ' Standby Liquid 2/3 Based on the BWR' Owner's Control Group recomendation, it was felt that the tank level should be designated Category 3 because of anticipated future changes to the SLCS design as a result of ATHS.

At such time, the SLCS instrumentation should be reevaluated to ensure adequacy.

i The current design basis for the SLCS recognizes that tht system has an l Importance to safety that is less than the importance to safety of the l RPS and the engineered safeguards systems. Therefore, in accordance I with the graded approach used for design and quality criterla specified l inRe$ Guide 1.97,itisunnecessarytoapplyafullqualityassurance . 1 program to this Instrumentation. This variable is more appropriately I considered a Category 3 variable.

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l Table 2 (cont'd) l Downcrade of 1.97 Design Recuirements l

Variable R.G. Cat./PNPS Cat. Reaso6 l

4. Neutron Flux 1/2 Based on the BWR Owner's l Group recommendation. It is concluded (this variable not considered to be a key variable) that a Category 2 i classification is responsive l to the intent of R.G. 1.97. l (At the time of this )

evaluation Boston Edison was not aware of the availability 1 of a suitably quallfled drive j unit.) The operator is !

alerted to a rise in neutron i flux as identified in the PN'S E0P's. At 3% power the !

APRM dowfiscale lights come on. l l

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) I-2 Boston Edison Database of !.97 Variables Boston Edison has tabulated design and qualification information of existing instrumentation at Pilgrim. This information has been entered in a computer database. Detailed evaluation of each variable is also identified in this _

database.

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I-3 Evaluation Methodology To establish a framework for evaluating specific instrument loops, an Accident l Monitoring Instrumentation (AMI) variable list (see Appendix 8) for PNPS I was developed. It identified those variables required to be monitored during and

{ following an accident. A typical database printout of instrument loop parts list as shown in Figure 2 was used in comparing the installed plant instrumentation to the guidance provided by Reg Guide 1.97.* Oda gathered in support of each Identified variable was placed into individual documene files. These document files were established to facilitate an auditable record and to assure BECo of adequate instrumentation for safe operation. An evaluation was then performed to identify areas of conformance and non-conformance related to PNPS I instrument design and Reg Guide 1.97 design and qualification criteria. A typical Matrix Evaluation sheet is shown in Figure 3. The evaluation results have only been shown on the first line or entry of an AMI variable number. However, the results apply to all appropriate entries within a particular AMI variable number series (i.e.,

001-01 thru 001-xx). The first six columns of the evaluation sheet have been copied from the "Instrument data sheet" (Figure 2). Finally, the format used to identify the justification or resolution related to a particular,to be

. deviation is shown in Figure 4.

Consistent with the graded approach used in Reg Guide 1.97, a prioritized ilsting of design and qualification criteria was developed. Prioritization t.s reflected by weighting factors used to quantitatively identify the degree of' importance of each design and quality criteria in Reg Guide 1.97. The ranking is as follows:

MOST IMPORTANT Weighting

_e Factor

( 1. Instrument Range environmentally qualifted for event conditions and the range needing to be 20 measured;

2. Power Source for reliable operation of the 16 instrument loop;

3. Seismic Qualification of equipment for 14 durability and reliability;

4. Availability of the display instrumentation 12 when needed;

5. Independence from a redundant channel, and 12 from event conditions, ;

1

'Please realize that this page is an example of a very large printout.

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MODERATELY IMPORTANT Weighting Factor

6. Display and/or recording methods; 8

% 7.~ Redundancy of display channels when needed; 6

8. Isolation of electrical interfaced needing 6 greater independence; $

9. Cuality Assurance requirements satisfied 4 )

and documented; I

LEAST IMPORTANT ,

10. Operational considerations including I l periodic test and access; l l

11. Identification markings to distinguish AMI 1 l

displays. ,

A value of 74 or above has been selected as a conformance index number. This value was selected to preclude not satisfying any two major design and qualiftcation eriter1a. This approach was based on conversations with the NRC during development of the listing. This value Indicates that the variable. *.

and thus, the instrumentation designated to monitor that variable, meets the' l Intent of Reg Guide 1.97. Not achieving this value indicates a number of deviations, a need for addltional information (NI) or a combination of the two (2). Note that a NI designation is not grounds for stating that a variable does not comply with the guidance in Reg Guide 1.97, unless a point total of 74 or greater cannot be met because of the number of N!'s. Where further information is required, further research will be performed for completenet:

If the information was not found, the variable was conservatively evaluated with respect to the missing information.

These weighting factors were al:o used for identifying alternative solutions for correcting deviations resulting from the BECo evaluation. Overall, the following crite i were used for identifying those alternatives that may have warranted further consideration:

- The overall best technical solution in terms of meeting the Reg Guide 1.97 and

- The sets of corrective actions that produced a conformance index number greater than 74, where conformance index number represents the degree of conformance (DC) of plant equipment in comparison to Reg Guide 1.97 guidance.

A decision tree approach was used to assess the merit of ceabinations os alternative solutions to resolve deviations (see Figure 5).

Beyond identifying specific results, the basic intent of the 1.97 evaluation

, for PNPS I was to ensure that a consistent, systematic, and documentable process be* developed and used in the generation of these specific results.

Boston Edison believes that its methodology for evaluating PNPS instrumentation loops is consistent and systematic and also provides the foundation for assuring traceability.

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eps.. . T e l

ggn ! e l l 8 41 5

, .e . i t i i

l I

.ec,D - . .

.. l t it e

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e i

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i it .e e b

a.6.m l . t

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i v.

.d. see a > .

w ;

l

<p. . .

i i

1 c.e , I ,

. t 3 g p .

l' gi . 3 3 1 . ,"- - 1.. { ,

w$. . .

= -

4 .,. ..p se .e.

l e i

I, f s z.

c.

e oeo

.e.3e..e -

o..

>m M.W t g.3

' - ,e se s 6 >m* = . s l 1 - l em.sa..So o g W

g. z w 6 A

I Na.

,w 6 .e c .= i.6. .a i s.

e

, .a . . w t

w.e i <a a-a o

o-.

a..

..e.,..

. I.

. . .e i

w w

... .h. e , .... .+. ,

i

,=

aa

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6 .

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, c I

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m, f :

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un

. 4.- . .

l l l

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. 1, 7. g .s h R *RE.R P R E E E R, R RR$ASE RRE.E A REREEE 1

.;e. ,v o a. n l onon onnnon anpnen amen n<3nnnnn ,

' >=! ->..w a in a n a <nanomolnanana ,n o m a n o l=anace = ,

l'I .

l l l i I I

s. innas nene .'

e s e.<o .. . e. s..e. s b. e o. 3 I.

Ren a, .. m.

- 3 J i

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i

,' w w

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l c. c R , ,

( i .

4nao... . o. , > o. . ==F Je. o. ii e

, 4 3- ~ - Bd 1

. i v=.v.A&.o.i -r <r.

g w a. wwhh w .44 o ... .. ...v m< < r 4 ' o ' e. m . c /,,8ee-a m..enaseo,o o

o oooo o--- ----- nn unRn. n,. 4. n f... . R m.

v <Q L

t' . ,v l .. .

r 4 ;,

1; io i l446 a,s.A444.,-

coSoi)o o o o oisoCoco'

< . sa.

r . i. 4 6 4 A, .$ .4 4 4 4 A.,.L .i. .'. e. .' .'.r

.> c o c. oois o o o o oi?

---.n- - - - - --- - - - . - - - - - - - - - . - - - - - - - , . - . - . , , - - - - , - - - - -

GCG f ~ t 01 ,

Riv. r$

8 .

OATC .3 .A T E984 NAPIC .

EVALUATSON OF DEVIATIONS ,

................ .. ...............e

#EACTOR COOLANT PRESSURE SOUNDARY e Y

AMI EGUIPPENT Y C REG IDENTIFICATIOpt OF PLANT DEVIATIONS. RESOLUT ION /.AfST IF IC AT ICDI REF.

VAR MurieCR t.OC PA 197 FR0rt RQ.197 REOUIREPENTS OF Pt. ANT DEVIATION 90tAtCE ET 003-01 *NIo C2203 C 1 23 .

003-02 263-134 8 . ".O C & 23 .

003-03 263-2-15A *NIe C 8 23 003-04 263-2-19A *NI* C 1 23 003-03 PT-64FA C2203 C 1 23 003-06 C2203 C2203 C 1 23 00 3-O F sese2C C2203 C 1 23 ~ ~

00 3-09 .N t * *Nt* C 1 23 .

003-09 640-34 C9tS C 3 23 ,

003-10 NAM 2C/S C989 C 3 23 ,

003-18 C918 C988 C 1 23

003- 82 Es- 40 C98. C 1 23 '

003-13 NAM 2C/O CT10 C 1 23 -

l 003-14 PM-640-27 C903 C 1 23 ,

003-33 9eAM2D C903 C 1 23 ;

003-16 PI-640-23A C903 C 1 23 .

003-t7 otAN2O C985 C 3 23 ,

003-te C903 C903 C 1 23 003-19 *NIo C903 C 1 23 , , , , . . .

003-20 SUS V2 C915 C 1 23 003-21 Y2090/A CSR C 1 23 ,

004-01 *NI* CJ206 C 3 23 004-02 263-138 1.30 C 3 23 004-03 263-2-138 *NI* C 1 23 004-04 263-2-198 *NI= C 1 23 .

004-03 PT-6478 C2206 C 1 23 004-06 C2206 C2206 C 1 23 004-07 N31SC C2206 C 1 23 004-0e ONIe eNt* C 1 23 004-09 640-35 C9te C 1 23 004-80 N319C/99 C988 C 3 23 .

004-18 C985 C9tS C 1 23 004-82 Es-640-SS C989 C 1 23 .

034-13 N3teC/SO C9te C 1 23

. 004-14 PM-640-27 C903 C 1 23 004-13 esAN2O C903 C 1 23 004-16 FI-640-238 C903 / 3 23 .

i 004-37 N3180 C903 C 1 23 004-tB C903 C903 C 8 23 -

! 004-19 eMI* C903 C 1 23 004-20 SUS Y2 C9 t ts C 1 23 , .

004-25 v2090/A CSR C 3 23 -

003-01 *NI. C22c3 C I :s

! . Figure 4

% J~'

'1 - I- '* *-

' ..;l.1,..$;.i, 57y: ?'.' : p.:,;*i:. '?; . ?+

. .., y.g* v a:.::. hT ..*C,4.. w

. i. . : .. .- t ,

.-.c.

..'? .~~~~'~

~~~'"

"ih'/'g%ALUATION WORT 5 MEET IIAMPLt -Ji.'.' .

'f ' .I'- . ~.' .-

.- .~ - -

: T.7.* .' ~. ..:a. . . ... . . ... T z**..:

. vr. '.

VARIABLE: REACTOR PRE 33RRE ~* -. " .* _'. .- . , , . ,

99

. -. . .; . .....;,.<.+. p .:. 0- + e . *- ~ -. . . , .. -

l Deviations { s. * . . .

?

'3: .

- s,

. r ,

g .,

t. P! Range is 3200, not 1500 psig

2. Seismic Qualification not doce ,

E,,

e * -f

85

3. Ilon-It Power Bus Source -

'd. Panel 905 Wiring not separated !

5.. Pow < Source not battery-backed 57 6 ID Markings not en displays

7 Redundant Aecorder for PT-6478 -

'71 8

Environmental Qualification not done .

57 .

l Base-Line inces calculation l .. , 57 -

20 E0, Range .

16 Power 0 14 Seismic 12 Avail. '

. 4? l 12 Indep.

8 Disp / Rec. '

6 Redund.

78

(

6' Isol.

% 4 OA *

. ?R ..

( ,,1, AMI Display .

99 Out of 100 possible 0

1a

- - ~ '

.. 0 ,

. l 0

1 1

1 Alternate Alternate h1 ternate 1 2 3 _

G' y

Add recorder Add two Analyze

.. P"g- ' to Panel 905 inverters Seismic .

..., observieg fromE3F.'palifica-

'3 '#'

, separation tfon of and having, batteries.8 for d. equipment a 1500 psig existing ? and I

t range. IO. Instrument mounting.

is ceferred. loops.

, Figure 5 -

1 I-3.1 Results of Evaluation This section of the report contains identified areas of conformance, deviation, and exception relative to the guidance in Reg Guide 1.97. Tables 3 and 4 in Section I-3.1.1 and I-3.1.2 respectively, Evaluation Results Matrices, identify the results of the PNPS I Reg Glide 1.97 evaluation of all 56 variables. Four (4) designations have been used to denste the degree of conformityofvariablesevaluatedforeachdesignandqualitycrjteria. They are:

A acceptable ANJ acceptable with justification NI need informa6, ion (further review or documentation required) 1, 2... deviation Bracketed numbers in the lower left-hand corner of each variable box in Tables ,

3 and 4 identify the quality category designation (i.e., Category 1, 2, or 3) !

for each variable. Bracketed numbers in the lower right-hand corner identify the nunerical value of the Cegree of conformity for each variable which is l compared with the acceptance value of 74. . - l l

' l e

f 7 ,

I

I-3.1.1 Conformance Table 3 is a tabulation of all variables reviewed and found to ccnform to Reg Guide 1.97 guidance. Acceptance of these variables was predicated on the degree I

( of conformance of plant equipment being equal to or greater than the 74 conformance inder number. For the PNPS 1.97 evaluation, Category 1 variable is considered acceptable if the rt.nge criterla is met along with other design and conformance qualitycriteria,thesumofwhicheitherequalsofexceedthe7) index number. The necessity for meeting environmental cualification requirements for Category i variables has been deferred (to be completed by RF0

8) for the PNPS conformance evaluation.

The neutron flux variable quality category was downgraded from Category 1 to l Category 2 and was subsequently found to conform with Reg Guide 1.97. Part of '

the reason for this downgrade 'vas based on the unavailability of a suitably qualified drive unit as noted in Reference 3.

(

l 4

1 f

f 8

1

,1

sbl9 3 Py grin Nuc 2r Power Station I

(

Evaluation Results Matrix -

Conformance IYPE A EQ/ Power Selsmic toop Chan. Display Chan. Elec. OA Test ID Range Source Qual. Avall. Indep. Record Redund. 1501. Reqmt. Access Mark Torus Temperature A' A A A A A A A A A A

[1 P 71001 "

Torus Mater Level A' A A A A A A A A A A

[1] [100]

Primary Containment A' A MI A A A A A A A A Prcssure

[1] E86)

Daywell Temperature ANJ' A NI A A A A 1 NI A A

[1] [761 TYPE S EQ/ Power Selsmic toop Chan. Display Chan. flec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. 1501. Reamt. Access Mark REACTIV'TY CONTROL Neutron Flus f. A NI A A A A A AWJ A NI UPRM/SRM)

[2] [85)

Control Rod A A A A A A A A A A A Position o

[3] [1001

' This equipment is being environmentally quallfled under the scope and schedule requirements of 10CFRSO.49.

Category 1 variables will be environmentally quallfled by the end of Refuel Outage #8.

[ ] This number identlfles the quality category. ..

- [ ] This number identlfles the degree of conformance.

Page 1 of 11 .

m' 9 bla 3 Pilgrin A._ .ir Power Station I Evaluation Results Matrix -

Conformance r-TYPE 8 EQ/ Power Selsmic Loop Chan. Olsplay Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. Isol. Regat. Access Mark RCS Solunje Boron Concentra- See Section I-1.2 tion (Sample)

(31 MAINT. RX 000LANT

SYSTEM INTEGRITY 8

Drywell Pressure A A NI A A A A A A A A (11 [861 Drywell Sump A A A A A A A A A A A

[3] [1001 MAINT. CONTAINMENT INTEGRITY Pristry Contaln- A* A NI A A A A A A A A ment Pressure

[1] [861

Category I varlables will be environmentally quallfled by the end of Refuel Outage #8.

Page 2 of II J

4

'bla 3 (

Pl_lgria Nuc ar Power Station I

_ Evaluation Results Matrix -

Conformance l TYPE 8 EQ/ Power Selsmic Loop Chan. l Display Chan. Elec. QA Test ID Range Source Oual. Avall. Indep. Record Redund. 1501. Reemt. Access Mark i Primary Contala-

ment Isolat6on Valve Position AK)* A NI A A AW.] A I NI A A (escluding check valve)

(1) (76)

TYPE C EQ/ Power Seismic Loop Chan. Display Chan. Elec. 0A Test ID

'. 1s01. Regat.

Ra.sge Source Qual. Avall. Indep. Record Redund. Access Mark i FUEL CLADDING

! See Section I-1.2 Rad. Level in Core Recirc. Loop (1)

Analysts of Prl-mary Coolant See Section I-1.2 (r - Spectrum)

I

[3]

RX COOLANT PRESS.

1 BOUNDARY i

Drywell Drain i Sumps Level "

(Identifled & A A A A A A A A A A A l

l Unidentifled

] Leakage)

(3) [1001 Cctegory 1 variables will be environmentally quallfled by the end of Refuel Outage' #8.

t l Page 3 of 11 i

I 3 N bla 3 %.

Pilgrin No. ar Power StAtton I l

Evaluation Results Matrix -

Conformance i

TYPE C EQ/ Power Seismic Loop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. Isol. Regat. Access Mark Suppressign Pool A' A A A A A A A A A A 4

Nater Level

[1] [100]

Drywell Pressure A' A MI A A A A A A A A i

[1] [861 CONTAINMENT l

l-Containment and ANJ" ANJ NI A A A A A NI NI A Drywell Ozygen Concentration (for inerted con-tainment plants)

[1] [81)

Containment Ef- A A A A A A A A A NI A fluent Radio-activity Noble l Cases (from

Identifled re-

! lease potats including Stand- d' by Gas Treatment System Vent) *

[3] [99)

' This equipment is being envirosmentally quallfled under the scope and schedule requirements of 10CFR50.49.

CategoryIvarlableswillbeenvironmentallyquallfledbytheendofkefuelOutage#8.

1 Page 4 of 11

. ~1 bla 3 -

W gria Nut .ir Power Stestion I Evaluation Results Matrix -

Conformance TYPE C EQ/ Power Selsmic Loop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. F.ecord Redund. Isol. Reget. Access Mark l Effluent Radlo- NI A A ANJ A A '

A , A A A A

! activity --. Noble Gases (from i

i

)

buildings or areas where penetrations and hatches are located, e.g.,

secondary con-tainment and aualllary buildings and fuel handling

! taulldings that l

are in direct contact with ~

primary contain-aent j [2] [801 Primary Contala- ANJ' A NI A A ANJ A A A A A i ment Pressure

[1] [861 TYPE D EQ/ Power Seismic Loop Chan. Display Chan. Elec. 0A Test ID Range Source Oual. Avall. It.dep . Record Redund. 1501. R20st. Access Mark CONDENSATE & FEED-MATER Main Feedwat*r A A A A A A K A A A A Flow '

[3] [10C1 Cctegory I variabies will be environmentally qualified by the end of Refuel Outage #8.

Page 5 of 11 1.

.. = ._ . - - _. . _. _ -

'abl7 3 %

3 Pilgrin Nus er Power St?tton I Evaluation Results Matrix -

Conformance TYPE D EQt Power Selselc Loop Chan. Display Chan. Elec. QA Test, ID Range Source Qual. Avall. Indep. Record Redund. Isol. Reget. Access Mark CondensatesTank NI . A A A A A A A A A A

.l Storage Level i

f3] E80)

PRIMARY CONTAlletEri

) RELATED SYSTEMS Crywell Pressure A A NI A A A A A A A A i f2] [863 Supprassion Pool A* A A A A A A A A A A h ter Level f21 (1001 1

Drywall Atmos- AK) A A A A A A I NI A A phere Temperature

'!?) (90)

Drywell Spray AK3 A MI A A A A A N1 A A l Flow (21 fS21 , .

Suppression Pool A' A A A A A A A A A A

> h ter Temperature i . I21 [1001

This equipment is being environmentally quallfled under the scope and schedule r'equirements of 10CFR50.49.

Page 6 of 11

.I

m. "(bl9 3 Pilgria i... er Power Station I

~

Evaluation Results Matrix -

Conformance TYPE D EQ/ Power Selsmic Loop Chan. Display j Chan. Elec. QA Test ID '

Range Source. Qual. Avall. Indep. Record A dund. Isol. Reget. Access Wrk 1

'i SLCS Storage A A A ANJ A A A A A A A Tank Level I

[3] [100) ._.

2 LPCI Systes Flow AWJ A NI A A A A A 1 A A

, _2] [ [821 h

RNR SYSTEMS

),

RNR Systes Flow AHJ' A ,

NI A A A A A 1 A A (2) (82). __

COOLIleG MATER SYSTEM l

NI A A Coollag h ter ANJ A l A A A 1 2 A Flow to ESF Sy5 tem Componeat5

[2] [811 i

This equipment is being environetntally quallfled unoer the scope and schedule requirements of 10CFR50.49.

l I

I a -

l j Page 8 of 11 1

j-

- . _ . _ - ___ .__- . - _ _ . = _ ._ ._ _ .

1 l 'nb12 ? f

! Pilgria Nut ar Power Station I Evaluation Results Matrix -

Conformance TYPE D EQ/ Power Selsalc Loop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep _ Record Redund. 1501. Reemt. Access Mark RADMASTE SYSTQlS j

! Nigh Radioac- NI A A A A A A A A A A j tivity Liquid Tar? 8 . vel I (31 [801 i VENTILATION SYSTEM

.i 1

Emergency Venti- AWJ A A A A A A A Ni A A 1 lation I (21 (961 -

POWER SUPPLIES i

i Status of Stand- AK) A NI A A A A A NI A A

by Power and J status of other energy sources l Important to i Safety .

(pneumatic) e w

j l l21 la21 4

I d

Page 9 of 11 l ' - - - _ _ _ _ . _ _ _ _ - _ . _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ - - - _ _ _ _ _ - - _ _

m # 4bl9 3 ^

Pilgrim ar Power Station I Evaluation Results Matrix -

Conformance TYPE E EQ/ Power Selsmic Loop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. 1501. Regat. Access Mark AIR 90RNE RAD. MAT *LS RELEASED FQ PIANT

} Primary Contala- A' A NI A 1 A A A A A A

ment Area 2adla-tion - Nigh Range 4

[1] [741 1-j~ Noble Cases and A A A A A A A 1 NI . A A Vent Flow Rate -

rn==ng Plant Vent or Multi-purpose Vent Discharging any of Above Releases (if drywell or SGTS purge is included.'

l

j. [2] [90]

l a

This equipme.1t is being environmentally quallfled under the scope and schedi,le requirements of 10CFRSO.49.

I i .

4 J

Page 10 of 11

)

k Dr I a A A A M

s

( t s se ec A A A Tc A

w t

Ae Qc A A A e

R cl eo A l s A A EI

.d nn au A A . '

hd A I Ce R

n -

i o a t i y

a r .d t t l r S a po A A .

M sc A 1 r e ie 1 e s c DR 3 w t n f ol a o l

a P su rm .

1

.p b r e o ne 1

aR f ad A A A e n hn g n o CI

<t o C a u i P N t a .

i n ul pl r a ol g v oa Lv A A A l E i A P

c l .

al sa A A A l u eQ S

2 1

- e -

rc I er wu A A A n oo PS i o

t c

e

_ / g e S Qn A A A e E a e

- R S

. 1 ) 1 0 0 0

=

i t

n o

0 1

[

0 1

[ f c c 0

1

[

G N

I L

l t

n a

o c d ni ory P o C p E e e M

._ Y r ep iet A ym E G l thi SY P O O S a pl T ru Y L msi TI aS T O d d iob NL m

._ A a a t ma EI id 0 l l stt DB rn E M M EAS IA Pa T CP E ] ] ] CA ]

.- M 3 3 3 AC 3

[ [ [ [

lllI l l l ll ll ll l l 1

1-3.1. 2 Deviations and Corrective Actions I Table 4 provides a summary of identified variables that do not meet the 74

( confonnance index number. A detailed evaluation of each of these variables is provided on At"ix Evaluation Sheets found in this section of the report.

This section also identifies the resolution of those deviations.s Where 1 taprovements will be made, a decision tree shows alternates considered and the action planned. Where more than one quality category is applied to a variable, the corrective action meets the inre stringent of the quality categories. Some deviations wre found to be acceptable upon further ex'a ination. In these cases, a rationale is provided indicating the justification for leaving the affected portion of ths instrument loop as is.

(

1 l

1 9

9

, f l

ibla 4 f P_llgria Nue. er Power Str.tlon I Evaluation kesults m trix -

Deviations e

TYPE A EQ/ Power Selsmic Loop Chan. l Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. 1501. Regat. Access krk RPV Pressura. A40' 1 NI 2 3 4 5 A NI A A

[1)* [283**

RPV h ter Level A40' 1 NI NI A A A A N1 A A

[1] [541 Cydrogen Concentra- l' A NI A A A A A NI A $

tion

[1] [62) '

TYPE 8 EQ/ Power Selsmic Loop Chan. Dis,31ay Chan. Elec. QA Test ID Range Source Qual. Avall. Irdep. Record Redund. Isol. Reget. Access krk CORE COOLING Coolant Level in Reactor AlO' 1 NI NI A A A A NI A A

[1] [5f]

' This equipment is being environmentally quallfled under the scope and schedule requirements of 10CFRSO.49.

Category I variables will be cavironmentally quallfled by the end of Refuel Outage as.

[ ] This number identifies thr quality category.

- [ ] This number identlfles the degree of conformance.

Page 1 of 6

---. .- . - ., . . . . _ _ _ . - _. -__ . - - - - _ _ _ - . . _ _ . - =-

m $ bla 4 -%

Py gria Nu er Power Station I Evaluation Results Matrix -

Deviations TYPE 8 EQ/ Power Selsmic t.oop Chan. ' Display Chr.n. Elec. QA Test ID Rar.ge SJurce Qual. Avall. Indep. Record Redund. Isol. Regat. Access Mark MAINT. RX C00LANT SYSIEN INTEGRITY RCS Pressure ANJ' 1 NI 2 3 4 S A NI A A

[1] [28] -

MAINT. CONTAINMENT INTEGRITY Z57011 A & 8 ANJ' 1 NI 2 3 ANJ 4 5 NI A A

[Il [301 257017 A & 8 ANJ' i NI 2 3 ANJ 4 5 NI A A i

[1] [301 l

1 I

l

Category 1 variables will be environmentally quallfled by the end of Refuel Outage #8.

e i

1

)

Page 2 of 6 1

g S bla 4 A Pilgria Nu, Jr Power Station I Evaluation Results Matrix -

Deviations TYPE 8 E0/ Power Selsmic Loop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. 1s01. Reget. Access Mark Z54002 ,, ANJ' A NI AWJ 1 ANJ ANJ 2 NI A A

[1] [641 254356 ANJ' 1 NI ANJ 2 ANJ ANJ 3 NI A A

[1] [481 8

259068 A & 8 1 2 NI 3 4 AWJ 5 6 NI A A

[1] 1101 258000 AWJ' 1 NI 2 3 ANJ 4 5 NI 6 7

[1] [281 I l 258001 ANJ' 1 NI 2 3 ANJ 4 5 NI 6 7

[1] [281 FCV-302-120 & 123 18 2 3 4 5 6 7 8 9 10 11

'[1] [0]

SV-302-121 & 122 la 2 3 4 5 6 7 8 9 10 11

[1] [0] '

Category 1 variables will be environmentally quallfled by the end of Refuel Outage #8.

l Page 3 of 6

% Nbl9 4 %

Pilgria No. ar Power Station I Evaluation Results m trix -

Deviations TYPE 8 E0/ Power Self-tc Loop Chan. Display Chan. Elec. QA Test ID Range Source Que ~, . Avall. Indep. Reccid Redund. 1501. Reget. Access Mark Z55065-34 & 38 l' A NI A A AWJ A 2 N1 A A

[1] [56)

ZS5065-32 & 36 l' A NI A A AWJ A 2 NI A A

[1] [561

.' TYPE C E0/ Power Selsmic Loop Chan. Display Chan. Elec. 0A Test ID

. Range Source Qual. Avall. Indep. Record Redund. Isol. Reget. Access Mark RX CDOLANT PRESS.

BOUNDARY RCS Pressure AWJ' 1 NI 2 3 4 5 A NI A A

[1] [28)

CONTAINMENT .

I RCS Pressure AWJ' 1 NI 2 3 4 5 A- NI A A fil [2s1 Containment and l' A NI A A A A A Ni A A Drywell Hydrogen " '

Concentration (11 [62)

' This equipment is being environmentally quallfled under the scope and schedule vequirements of 10CFRSO.49.

Category 1 variables will be environmentally quallfled by the end of Refuel Outhge #8.

Page 4 of 6

~i bla 4 (

Pil gla Not er Power Ste.tlon I Evaluation Results Matris -

Deviations TYPE D EQ/ Power Selsmic toop Chan. Display Chan. Elec. QA Test ID Range Source Qual. Avall. Indep. Record Redund. Isol. Regat. Access Mark SAFETY SYSTEMS Core Spray ANJ' 1 NI A A A A A 2 A A System Flow

[2] [66)

Rf3R SYSTEMS RNR Heat Exchang- ANJ A MI A 1 A A 2 3 A A er Outlet Tem-perature

[2] [66)

COOLING HATER SYSTEI:

Cooling Mater ANJ A NI A 1 A A 2 3 A A Temp to ESF System Compownts

[2] [64) .

' This equipment is being environmentai;; avallfled under the scope and schedule requirements of 10CTR50.'49.

Page 5 of 6

r ,r'cbla 4 Pilgrin No ar Power Station I Evaluation Results Catrix -

Deviations i

TYPE E EQ/ Power Selsmic L')op Chaa. Display Chan. Elec.I : QA Test ID Range Source Qual. Avall. Indep. Record Redund. 1501. Regat. Access Mark i

CONTAINMENT @ !A-TION l Radiation Ex- l' A A NI A A A 2 NI A A posure Rate (Inside bldg.

l access is re-gulred to service equipment impor-tant to safety)

(21 (581 g

Category I variables will be envircnmentally quallfled by the end of Re'uel Outage #8. .

i

)

l 1

1 1

l Page 6 of 6 i

Matrix Evaluation Sheet RPV PRESSURE

\-

EQ RANGE (20): (AWJ) The reactor pressure monitoring channels meet all plant emergency procedure operating requirements, and Reg Guide 1.97 range requirements for the identical Type 8 and C Category 1 variables. The PT.647A and B transmitters will be required to satisfy environmental qualification requirements. This Type A Category 1 design requirement is considered to be acceptable casec on satisfying the range requirement.

POWER SOURCE (16): (1) The bus Y2 vital instrument power source used for both PT-647A and 8 transmitters does not meet Reg Guide 1.97 requirements for redundancy and' independence.

SEISMIC QUALIFICATION (14): [*NI'] (Need to confirm seismic qualification of the reactor pressure transmitter, local racks C2205 and C2206, panel C918, and the recorder mounted on panel C905). Seismic qualification is required by Reg Guide 1.97 for Type A Category I variables.

LOOP AVAILABILITY (12): (2) Bus Y2 and panel C918 do not provide sufflctent redundancy to assure high availability; however, an independent transmitter it provided for each reactor pressure monitoring channel.

CHANNEL INDEPENDENCE (12): (3) The two channels of reactor pressure monitoring do not fulfill the independence reautrement of Reg Guide 1.97 for this variable because of the Y2 power source, single recorder, C918 and C905 panels, and cabling, which has been Identified as non-safety related, s

O! SPLAY RECORDED (8): (4) A single recorder with two pens covering a 0 to 1500 pstg range is provided on main control room panel C905. Because of the importance of trend information for reactor pressure, each channel is required to be recorded by Reg Guide 1.97.

CHANNEL REDUNDANCY (6): (5) Redundant pressure transmitters, local racks, and control room indicators are provided; however, other portions of the two reactor pressure channels do not meet the redundancy requirement of Reg Guide 1.97.

ELECTRICAL ISOLATION (6): (A) Confirmation that cable tray and conduit routing meets separation requirements in all respects has been and is assured by approved departmental procedure, vendor specifications, and industry standards (i.e., BECAM, Bechtel Design Criteria for Electrical Installations

and GE Specifications #22A1421. E-347. IEEE279-1971). This also appites to l confirming adequate separation and electrical isolation for existing wiring by

reviewing and approving associated pull cards.

) QA REQUIREMENTS (4): [*N1*] (Nced to determine whether sufficient QA controls were applied to the original design of the reactor pressure monitoring channels).

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I k IDENTIFICATION MARKINGS (1): (A) Identification marking for the pressure recorder on C905 is distinctively marked.

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RPV PRESSURE IMPROVEMENTS This is a Type A Category 1 variable. The intent of this variable is to provide the operator primary information for manual action when (1) depressurtzing RPV and maintaining safe cooldown rate by any of several systems, such as main turbine bypass valves, HPCI, RCIC, and RWCU and (2) manually opening one SRV to reduce pressure to below SRV setpoint if any SRV is cycling. Boston Edison presently intends to install an analog trip system which will replace certain reactor pressure switches. Use of the analog trip system which will be Class IE can be used to provide reactor pressure signals to the control room. Doston Edison, therefore, plans to implement the above improvements by taking advantage of derived benefits resulting from the analog trip system effort. (See figure 6)

It has been identified that a redundant pressure recorder on panel C905 should be installed in order to meet the Type A variable trend information ,

requirement. Closer examination of the panel indicates that there is - - '

physically not sufficient room for the additlen of another recorder. However, operator utilization of the SPDS will compensate for this. Boston Edison, therefore, intends not to install a redundant recorder.

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Matrix Evaluation Sheet

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EQ RANGE (20): C AW,1) Two overlapping reactor vessel water level instrumentation channels in each division provide measurement ranges that apprortmate, but do not precisely meet, Reg Guide 1.97 range requirements.

LITS 263-59A and 8 extend from +432 to +532 inches of water relative to vessel zero and are used to display reactor water level during both normal and abnormal operating modes. OPT 1001-650A and 8 extend from +205 to +505 inches of water and are used to display reactor water level during abnormal operating modes whenever the recirculation pumps are tripped. Un:'er accident conditions, the ovsrlapping range of these instruments does not fully encompass the Reg Guide 1.97 required range of +186 to +604 inches of water relative to vessel zero.

This Type A Category I variable will require full EQ review.

PDCR-81-34 added new differential pressure transmitters OPT 1001-650A/8 for the fuel zone (i.e., wide range) level measurement in lieu of existing LITS 263-73A/B instruments and requires that the water level modification comply wtth IEEE Stds 323-1974 and 344-1975 and USNRC Reg Guide 1.89 and 1.100. This Rosemount 115*, transmitter OPT 1001-650A and B will also require -

full EQ review. .

PCWER SOURCE (16): (1) Redundant, safety related power sources. Y3 & Y4 are used to power OPT 1001-650A and 5 channels, respectively. However, LIT 5263-59A

, ( and B are powered from a single non-safety power source, Y1. This design ts, therefore, not acceptable under Reg Guide 1.97 requireu nts.

SEISMIC QUALIFICATION (14): [*N!*] (Need to confirm seismic quellf!4ation of the four reactor vessel water level instrument channels). Seismic qualif tration is required by Reg Guide 1.97 for this variable. Seisste analysts of the C2251 and C2252 instru.nent racks 15 provided in PDCR-81-34 Appendix 8.

LOOP AVAILABILITY (12): (*N!*) (Need to confirm that each narrow range and wide range channel provides an indspendent sanser, a vital instrurnentation power source, and usec a portton of a PAM panel recorder).

CHANNEL INDEPENDENCE (12): (A) Two redundant and physically separate trains of reactor vessel level monitoring are specified on M-253 revision 12 design revision A.

DISPLAY RECORDE0 (8): (A) Redundant recorders covering a +205 to +505 inches of water range and an overlapping +432 to +532 inches of water range are provided on PAM panels C170 and C171 per P N R-79-60, i

CHANNEL REDUNDANCY (6): (A) Redundant trains (c. reactor vessel level monitoring are specified on M-253 revision 12 design revision A.

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ELECTRICAL ISOLATION (6): (A) Confirmation that cable tray and condult routing meets separation requirements in all respects has been and is assured by approved departmental procedure, vendor specifications, and industry standards (i.e , BEQAM, 8echtel Design Criteria for Electrical Installations

(, and GE Specifications #22A1421. E-347, IEEE279-1971). This also applies to confirming adequate separation and electrical isolation for existing wiring by reviewing and approving associated pull cards.

QA REQUIREMENTS (4): (*N!*] (Need to confirm implemented QA for PDCR-81-34 modif' ation and for existing LITS 263-59A and 5 and associated channel Instrumentation.

TEST ACCESSIBILITY (1): (A) Equipment mounted on panels C170 and C171 is accessible during all plant operating modes. Redundant differential pressure t-ansmitters are mounted on racks readily accessible for maintenance.

10ENTIFICATION MARKINGS (1): (A) PAM panels C170 and C171, which contain the wide and narrow range reactor vessel level monitoring recorders, are distinctively marked. -

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RPV WATER LEVEL 1

!MPROVEMENTS f

This is a Type A Category I variable. Its intent is to provide the operator primary information when restoring or maintaining water level. As identified in the PNPS I evaluation, LITS 263-59A & B are powered from a single non-safety power source, Yl. The cabling up to LITS 263-59A & B is safety related, with non-safety cabling for LI263-106A & 5. It is recommended based on Figure 7 that redundant, safety related power sources.be employed for this instrument loop and that seismic information be obtained for the four(4) reactor vessel level instrument channels. Activity is presently underway to replace the Yarway's at PNPS I with an analog trip system. LITS 263-59A & B has been designated for this replacement. As such, safety related cabling will be used throughout the loop along with redundant safety related power sources. Since i this would represent a new modiflestion, associated seismic qualification information and confirmation is required as part of Boston Edison's plant modification process and could, therefore, be obtained when implemented. l 4 Sultable QA documentation should then be obtained. Boston Edison intends to perform the above improvements.

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i Matrt Evaluation Sheet HYOROGEN CONCENTRATI0M k.

EQ RANGE (20): (1) The dydrogen Analyzer purchase specification, M-522, i

itsts its range as 0 to 10f, with 0.21. accuracy which does not meet the Reg l Guide 1.97 range requirbmene of 0 to 301.. Moreover, it is a plant addition to i

be installed in accordance sith PDCR's 80-09, 80-30, and 80-40, and must meet applicable environmental requirements. This Type C Category 1 variable will require full environmental qusilfication compliance.

POWER SOURCE (16): (A) Redund;it hydrogen t.nalyzer channels are on separate control room panels, and are powered by redundant on-site AC power sources (Y3 ;

and Y4) as required by Reg Guide 1.97 for this variable. l SEISHIC QUALIFICATION (14): ('NI'] (Need to confirm the seismic i

1ualification of the hydrogen monitor channels; in the intertm. the

' Ustrumentation is assumed te ba unqualified for Reg Guide i.97 Type C . -

t Ca6egory I applications).

LOOP AVAILABILITY (12): (A' Redundant hydrogen monitoring channels, redundant power sources and control room panels, and redundant PAM panel recorders are being added as specified in the previously itsted PDCR's. This:

PNPS 1 modification satisfles this Reg Guide 1.97 requirement.

CHANNEL INDEPENDENCE (12): (A) Two redundant trains for hydrogen monttering are specified in the aforementioned PDCR's. Cabling found to be safety related.

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DISPLAY RECORDE0 (8): (A) Redundant recorders are provided on PAM panels ,

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1 CHANNEL REDUNDANCY (6): (A) idundant trains are provided by the PNPS I design modification.

, ELECTRICAL ISOLATION (6): (A) Conftrretton that cabla tray and conduit i routing meets separation requirements in all respects has been and is assured by approved departmental procedure, vendor fpectftcations, and indestry standards (i.e., BEQAM, Sechtel Design Criteria for Elet.trical Installations and GE Spec 1fIcations 822A1421, E-347. IEEE219-1971). This also applies to confirming adequate separation and electrical isolation for entsting wiring by reviewing and approving associated pull cards. 3 QA REQUIREMENTS (4): (*N!') (Need information en the extent of QA !

requirements applied to the proposed modification).

J (EST ACCESS!8!LITY (1): (A) Tne redundant recorders n: anted on C170 and C171 i

) are accessible during all plant operattig modes. Local panels C172 and C173 l

' are located in low rad area outside secondary containment (mezzantne over i i "hot

machine shop).

) t IDENTIFICATION MARKINGS (1): (A) PAM panels C170 and C171, which contain the I hydrogen monitoring recorders, are distinctively marked. !

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HYOROGEM CONCENTRATION

- EXCEPTION This is a Type A. Category 1 variable. Based on Figure 8. Boston Edison will not increase the range (i.e., 0 - 30%) as identified in Reg Guide 1.97.

Boston Edison was committed to meeting NUREG-0737, !!.F.1, Attachment 6.

Containment Hydrogen Mon sot. As identiflid "Measurement capability shall be provided over the range of l 0 to 10?. hydrogen 'oncentration under both positive and negative ambient pressure."

boston Edison considers the range requirement to be satisfied. In addition, hydrogen concentration can be measured from 0 - 20% concentration.

Per Boston Edison's internal design modification report, the H 0 Monitoring System will be Installed to comply with IEEE344-1975, "Seismic i 4

Qualtftcation of Class IE Electrical Equipm'nt for Nuclear Power Generating .

Station". Boston Edison v111 investigate seismic qualification complianc'e for this variable.

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Matrix Evaluation Sheet.

PRIMARY CONMJNMENT ISOLATION val.VE POS!T!ON (ZS7011 A & 8)

EQ RANGE (20): (AWJ) The ZS7011A & 8 position switches for the Radwaste Collection, Drywell Equipment Sump isolation valves meets the ' closed-not closed" range reautrement of UShRC Reg Guide 1.97 for this Type 8 Category I variable. Justification for acceptance of these switches is based on meeting the range requirement. These switches will be reviewto to establish compliance with 10CFR50.49.

POWER SOURCI (16): (1) Power is provided for the position indication channel by a single power source, Y1. This source is not safety related. This existing design, therefore, does not meet 1.97 requirement.

SEISMIC QUALIFICATION (14): (*NI'] (Need to confirm seismic qualtftcation of the valve position switches). Reg Guide 1.97 requires seismic qualification for this variable. . .

LOOP AVAILABILITY (12): (2) A*ithough, the comelnation of inboard and outboard position indication 'nannels is required to n et the single fatture criterton in order to sati d y the Reg Guide 1.97 loop availability requirement, the cabling has been iden'tfied as non-safety related therefore this design is unsatisfactory.

CHANNEL !NDEPENDENCE (12): (3) (Xeed to :onfirm that independence is maintained between the position indications of redundant isolation valves in piping penetrating primary containment). Note, again, that the cabling is

(. non-safety relsted.

O! SPLAY RECORDE0 (8): (AWJ1 Reg Guide 1.97 requires a continuous real- time indication display and recording of one channel for Type B Category I variables to provide direct and trenediate trend or transtant information to the plant operator. Primary reactor containment isolation valve posttion, whether "closed" or "non-closed", provides current status rather than either trend or transtant information even though it is a Type 8 variable. GE specification 22A1132AK requires that the indicating Ilghts provide a direct status indication of each respective isolation valve. Using the panel C904 p aphic mimic display, the plant operator can ascertain overall effectiveness of the primary containment isolation system based on color pattern recognition. Hence, ths present PNPS I design is satisfactory.

CHANNEL REDUNDANCY (6): (4) The combination of twc position Indication cnannels for isolation valves outside primary containment is required to meet the single fatture criterion in order to satisfy the Reg Guide 1.97 channel redundancy requirement. Therefore, aux 111ary equipment must ta safety related. This design does not meet this requirement.

ELECTRICAL ISOLATION (6): (5) As presently configured, fuses have been used in the valve position indication channel. However, Reg Guide 1.75 considers fuses to began unacceptable isolation device since they are actuated by fault current. The entsting PNPS I design does not meet this requirement.

QA RE(UIREMENTS (4): ('N!'] (Need to confirm that full QA requirements were applied to the isolation valve positten switches).

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1 TEST ACCESSIBILITY (1): (A) Equipment mounted on panel C904 15 accessible i during all plant operating modes. Loca'ly mounted isolation valve position switches may not W Imediately accessible during accident conditions.

( IDENTIFICATION MARKINGS (1): (A) Reg Guide 1.97 requires distinctive markings for this varleble which is satisfled by the PNPS I graphic mimic display on panel C904. I i.

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PRfKaRY CONTAINMENT ! SOLATION VALVE POS!?!ON (Z$7011A & 8)

IMPROVEMENTS These position switches are used to indicate valve position on the discharge line of the Drywell Equipment Orain Sump. These Class 8 valves are located outside of the drywell. The valves are isolated on drywell isolation. These valves serve to prevent transmission of radioactive effluent outside of seccndary containment. At present, the cabling and ocwer source for this Type 8 Category 1 variable are non-safety related. Because of its isolation function, the instrument channel loops for this variable must meet the single failure criterten. Boston Edison, based on Figure 9, intends to use redundant safety related power sources (i.e., Y3 and Y4). Entsting non-safety cabling vill be replaced wtth safety related cabling. Associated QA documents will also be obtained.

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1 Matrix Evaluation Sheet !

i PRIMARY CONTAINMENT ISOLATION VALVE POSITION (ZS7017A & 8)

EQ RANGE (20): (AWJ) The ZS7017A & 8 position switches for the Radwaste Collection Drywell Floor Sump isolation valves meets the ' closed-not closed" range requirement of USNRC Reg Guide 1.97 for this Type B Category 1 variable. Justification for acceptance of these switches is based on meeting i the range requirement. These switches will be reviewed to establish ;

compliance w1th 10CFR50.49.

POWER SOURCE (16): (1) Power is provided for the position indication channel by a single power source Yl. This source is not safety related. This existing design, therefore, does not Net 1.97 requirement. l 1

SE!SMIC QUALIFICATION (14): ('N!') (Need to confirm seismic qualification of the valve position switches). Reg Guide 1.97 requires seismic qualification for this variable. . -

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LOOP AVAILABILITY (12): (2) Although, the ccebination of Inboard and I cutboard positten indication channels is required to meet the single failure j criterton in order to satisfy the Reg Guide 1.97 loop availability i requirement, the cabling has been identifled as non-safety related therefore,:

this design is unsatisfactory.

CHANNEL INDEPENDENCE (12): (3) (Need to confirm that indecendence is maintained between the positten indications of redundant isolation valves in (A piping penetrating primary containment). Note, again, that the cabling is non-safety related.

O! SPLAY RECORDED (8): (AWJ) Reg Guide 1.97 requires a continuous real- time Indication display and recording of one channel for Type 5 Category.1 t variacles to provide direct and 1 mediate trend or transtant teformation to the plant operator. Primary reactor containment isolation valve position, whether "closed" or "non-closed", provides current status rather than either trend or translent information even though it is a Type 5 variable. GE specification 22All32AK requires that the Indicating lights provide a direct status indication of each respective isolation valve. Using the panel C904 4

graphic mimic display, the plant operator can ascertain overall effectiveness of the ';rimary containment isolation system based on color pattern

! recognition. Hence, the present PNPS I design is satisfactory.

CHANNEL REDUNDANCY (6): (4) The combination of two position indication I

channels for isolation valves outside primary containment is required to meet the single failure criterion in order to satisfy the Reg Guide 1.97 channel redundancy requirement. Therefore, austilary equipment must be safety related. This design does not meet this requirement.

ELECTRICAL ISOLATION (6): (5) As presently configured, fuses have been used in the valve position indication channel. However, Reg Guide 1.75 considers fuses to be$e current. T estating PNPS I design does not meet this requirement.an unacceptab l

QA REQUIREMENTS (4): ('N!') (Need to confirm that full QA requirements were applied to the isolation valve position twitches).

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TEST ACCESS!BILITY (1): (Al Equipment mounted on panel C904 is 4CCessible during all plant 00erating modes. Locally mounted Isolation valve position i switches may not be imediately 4CCessible during Accident ConditlCns. ,

10ENTIFIC/TIO% MARKING 5 (1): (A) Reg Guide 1.97 requires distinctive markings for this variable whlCh is satisfied by the PNPS ! graphlt slatt display on panel C904.

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1 PRIMARY CONTA!NNENT !$0LATION val.VC POSIT!ON (Z$7017A & B)

{ IMPROVEMENTS The valves for these position switches serve the same function as Z570llA & B. i namely to prevent transfer of radioactive effluent outside secondary !

containment. Soth valves and position switches are located outside the drywell. The same improveMnts indicated for ZS7011 A & B will be performed ,

for this Type A Category I varleble. (See Figure 10) '

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i Matrir Evaluation Sheet

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PRIMARY CONTAINMENT !$0LATION VALVE P05! TION (ZS4002)

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EQ RANGE (20): (AWJ) The 254002 posttton switch for the R8CCW Return

isolation valves meets the "closed-not closed" range requirement of USNRC Reg Guide 1.97 for this type 5 Category 1 variable. Justification for acceptance

of these switches is based on meeting the range retutrement. These switches ,

will be reviewed to establish compliance with 10CFR50.49.

PCHER SOURCE (16): (A) Power is provided for this position indicaticn channel by a single safety related power source, 818. This existing design. l 5

therefore, does meet 1.97 requirements. i SEISMIC QUALIFICATION (14): [*N!*) (Need to confirm seismie qualification of

the valve position switches). Reg Guide 1.97 requires seismic qualtftcation for this variable. .

LOCP AVAILABILITY (12): (AWJ) This indication channel reflects a design that j conforms to 10CFR50 Appendix A General Oestgn Criterion 57, covering closed Systems penetrating primary reactor containment (At least one containment .

1 isolation is required to be located outside containment). I

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CMANNEL tNDEPENDENCE (12): ,11 (Nead to confirm that independence is j mathtnined between the posttion indications of redundant isolation valves in piping penetrating primary containment). Note, again, that the cabitng is non-safety rw.ated.

015 6 , RECORDED (8): (ANJ) Reg Guide 1.97 recutres a continuous real- time I indication display and recording of one channel for Type 5 Category 1 l variables to provide direct and immediate trend or transtant information to the plant operator. Primary reactor contalement isolation valve position, i whether "closed" or "non-closed" provides current status rather than either )

, trend or transient information even though it is a Type 5 vartable. CE -

I spectftcation 22A1132AK requires that the indicating lights provide a direct

! status indication of each respective tsolation valve. Using the panel C904

grachte almtc display, the plant operator can ascertain overall effectiveness I of the primary containment isolation system based on color pattern

j. recognition. Hence, the present PNPS I design is satisfactory.

CHANNEL REDUNDANCY (6): (AWJ) This vertable is designed in conformanced with 4 10CFR50 Appendt A General Dostgn Critetton 57 covering closed system

!, penetrating primary reactor containment.

J ELECTRICAL ISOLATION (6): (2) As presently onfigured, fuses have oeen used

in the valve position indication channel. However. Reg Guide 1.75 considers fuses to be an unacceptable iso 14 tion device since they are actuated by fault g

current. The entsting PNPS ! design dces not meet this requirement.

QA REQJ!REMENTS (4): ('N!') (Need to confirm that full QA requirements were applied to the isolation valve positten switches).

i '

TEST ACCES$1BILITY (1): (A) Equipment mounted on panel C904 is accessible

{ during all plant operating modes. Locally mountvd Isolation valve posttion switches may not be tesneolately accessible during accident conditions. )

l i i i 24

10(NTIFICATION MRK!NGS (1): (A) Ret Guide 1.97 requires distinctive markings for this variable which is satisfied by the PNP 5 ! graphic elmic display on panel C904.

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k PRIMARY CONTAINNENT ISOLATION VALVE POSITION (ZS4002)

EXCEPTION

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This Type O Category I variable was found to deviate from the following 1.97 requirements:

- Channel Independence

- Electrical Isolation The cabling and power source for 254002 were found to be safety related. Only j one(1) valve serves as isolation for the RBCCW return line. Thus, only one instrument loop is available for position indication. Therefore, channel ,

independence can not be applied. The design configuration is acceptable based on original design criteria and meets the requirements under 10CFR50 Appendix A. Criterion 57. This variable will not be modified to meet 1.97 requirements, in light of the above information.

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1 j

i Hatrtr Evaluation Sheet PRIMARY CONTAINMENT ISOLATION VALVE POSITION (ZS4356)

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EQ RANGE (20): (ANJ) The 254356 position swi'tch for the Instrument Air isolation valves meets the "closed-not closed" range requirement of USNRC Reg !

Guide 1.97 for this Type B Category I variable. Justification for acceptance !

of these switches is based cc. meeting the range requirement. These switches will be reviewed to establish compliance with 10CFR50.49.

POWER SCORCE (16): [1] Power is provided for the position indication channel I by a single power source. Y1. This source is not safety related. This !

existing design, therefore, does not meet 1.97 requirement- I l

SEISHIC QUALIFICATION (14): (*N!*) (Need to confirm seismic qualification of l

the valve position switches). Reg Guide 1.97 requires seismic qualification for this variable. ,

i LOOP AVAILABILITY (12): (ANJ) Part of this requirement is accomplished with an outboard check valve in the PNPS I design in conformance wtth Class S l 1 solation valves identified in GE specification 22All32AK. In this 1 configuration maintenance and/or testing can be performed without .

l compromising system effectiveness. Therefore, the present design complies l wtth Reg Guide 1.97 requirements, i CHANNEL INDEPENDENCE (12): (2) (Need to confirm that independence is I' maintained between the position indications of redundant isolation valves in

( piping penetrating primary containme.'t). Note, again, that the cabling is l non-safety related. I DISPLAY RECORDED (8): CAHJ) Reg Guide 1.97 requires a continuous real- time indication display and recording of one channel for Type B Category 1.

variables to provide direct and 1 mediate trend or transient information to the plant operator. Primary reactor containment ' isolation valve position, whether "closed" or "non-closed", provides current status rather than either trend or transient information even though it is a Type B variable. GE specification 22A1132AK requires that the indicating lights provide a direct j status indication of each respective isolation valve. Using the panel C904 ;

graphic mimic display, the plant operator can ascertain overall effectiveness :

of the primary containment isolation system btsed on color pattern i recognition. Hence, the present PNPS I design is satisfactory.

CHANNEL REDUNDANCY (6): (AWJ) Part of thts requirement 1s acceeplished wtth an outboard check valve in the PNPS I design in conformance wtth Class B ;

isolation valves identified in GE specification 22A1132AK. In this !

configuration, maintenance and/or testing can be performed without co:.ipromising system effectiveness. Therefore, the present design complies with Reg. Guide 1.97 requirements. l ELECTRICAL "50LATION (6): (3) As presently configured, fuses have been used in the valvh position indication channel. However, Reg Guide 1.75 considers fuses to be an unacceptable isolation device since they are actuated by fault !

current. The existing PNPS I design does not meet this requirement. !

QA REQUIREMENTS (4): (*N!*] (Need to confirm that full QA requirements were l applied to the isolation valve position switches).

27

TEST ACCESSIBILITY (1): CA) Equipment mounted on panel C904 is accessible during all plant operating modes. Locally mounted 1 solation valve position switches may not be imediately accessible during accident conditions, IDENTIFICATION MARKINGS (1): (A) Reg Guide 1.97 requires distinctive markings for this variable which is satisfied by the PNPS I graphic simic display on panel C904.

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PRIMARY CONTAINMENT ISOLATION VALVE POSITTON (ZS4356)

{ EXCEPTION This (ype B Category I variable was found to deviate from the following 1.97 design requirements:

Power Source

- Channel Independence Electrical Isolation The cabling and power source for 254356 were found to be non-safety. Since this variable is considered to be containment isolation valve position, the single fatture criterion must be met. However, the present valve lineup (one check valve and one air operated valve) precludes meeting the channel independence requirement (note: check valves are not reviewed under 1.97).

One check valve and one air operated valve are provided, both outside containment. The air operated valve is operated manually from the Control .

ro)m with no automatic signals or diversity. Only the check valve is seismic Class I. .

This GE design, considered acceptable by the NRC in a letter dated 12/18/79, satisfies the original plant design requirements. -

Instrument air is maintained at a pressure in excess of the maximum accident pressure expected in the drywell. Should instrument air be reduced to less than :entainment pressure, the 3" check valve in series with thG remote manual air operated valve in the essential instrument air header will provide adequate isolation. '

Therefore, this variable will not be modified since the installation of redundant safety related position indicators for a single valve would not meet the single failure criterion. The instrument cor. figuration precludes meeting the single failure criterton specified in 1.97. Nevertheless, the original plant design requirements are satisfied.

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Matrix Evaluation Sheet PRIMARY CONTAINMENT ISOLATION VALVE POSITION (ZS9068A & B)

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EQ RANGE (20): (1) ZS9068A & B position switches for the HPCI Gland Seal Condenser do not meet the range for Reg Guide 1.97. Direct measurement of valve is requirement. The above switches employ relays (see E455 & E449) which must be energized before indication of valve closure is provided on control room panel C903. The above design does not meet the 1.97 range requirements for for this Type B Category 1 variable. This variable will be reviewed to establish compliance with 10CFR50.49.

POWER SOURCE (16): (2) Power is provided by a single safety related power source, 05.

SEISHIC QUALIFICATION (14): [*N!*] (Need to confirm selsnic qualification of the valve position switches) Reg Guide 1.97 requires seismic qualification for this variable. ,

LOOP AVAILABILITY (12): (3) The position switches for this Type O Category 1 variable does not provide sufficient latitude to accommodate testing and maintenance requirements that will be necessary during power operation. itte that cabling is safety related. This design does not meet Reg Guide 1.97

requirements.

CHANNEL INDEPENDENCE (12): (4) Sufficient independence is not provided ba'ed on installation of single power source.

OISPLAY RECORDED (8): (AWJ) Reg Guide 1.97 requires a continuous real- time indication display and recording of one channel for Type B Category i variables to provide direct and 1 mediate trend or transient information to the plant operator. Primary reactor containment isolation valve position, whether "closed" or "non-closed". provides current status rather than either trend or transtent information even though it is a Type B variable. GE specification 22All32AK requires that the indicating lights provide a direct status indication of each respective isolation valve. Using the panel C904 graphic mimic display, the plant operator can ascertain overall effectiveness of the primary containment isolation system based on color pattern recognition. Hence, the present PNPS I design is satisfactory.

CHANNEL REOUNDANCY (6): (5) Sufficient redundancy is not provided by the instrument loops for the condensate drain pot position switches. This design does not comply with Reg Guide 1.97.

ELECTRICAL ISOLATION (6): (6) As presently configured, fuses have been used in the valve position Indication channel. However, Reg Guide 1.75 considers fuses to be an unacceptable isolation device since they are actuated by fault current. The existing PNPS I design does not meet this requirement. I 1

QA REQUIREMENTS (4): (*N!') (Need to confirm that graded QA requirements I were applied to the isolation valve position switches).

\

TEST ACCESSIBILITY (1): (A) Equipment mounted on panel C904 is accessible l during all plant operating modes. Locally mounted isolation valve position l swttches may not be immediately accessible during accident conditions, j l

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IDENTIFICATION MARKINGS (4): (A) Reg Guide 1.97 requires distinctive markings for this variable which is satisfled by the PNPS I graphic mimic display on panel C904.

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i PRIMARY CONTAINMENT ISOLA 7!ON VALVE POSITION (ZS9068A & B)

( IMPROVEMENTS This is a Type B Category 1 variable. This indication is used to monitor the valve position of the Condensate Drain Pot Orain valves on the HPCI system. j Upon receipt of a low pressure isolatior, signal, SV9068A & B isolate. This assures that the HPCI exhaust line is properly isolated to preclude a possible breach of primary containment under accident conditions. A direct measuremer.t of valve position is, therefore, required to provide status on valve position. Based on Figure 11, Boston Edison will add a redundant, safety related power source to this variabis instrument loop. The addition of a redundant power source would preclude consequences of single failure. ,

Installation of direct measuring position indication will also be performed. '

The addition of new position switches would minimize any ambiquity regarding actual isolation of these valves. Again QA documents will be provided in support of proper installation of these switches.

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l Matrix Evaluation Sheet

[ PRIMARY CONTA!NMENT ISCLATION VALVE POSITION (ZS8000 & Z58001)

EQ RANGE (20): (AWJ) The 258000 & ZS8001 position switches for the Torus Makeup from Condensate Storage Tank isolation "alves meets the "closed-not closed" range requirement of USNRC Reg Guide 1.97 for t".is Type B Category 1 variable. Justification for acceptance of these switches is based on meeting the range requirement. These switches will be reviewed to establish compliance with 10CFR50.49.

POWER SOURCE (16): (1) Power is provided for the position indication channel by a single power source, Y1. This source is not safety related. This existing design, therefore, does not meet 1.97 requirement.

SEISMIC QUALIFICATION (14): (*NI*) (Need to confW :cirnic qualificattor. of the valve position switches). Reg Guide 1.97 requires seismic qualification for this variable. . -

LOOP AVAILABILITY (12): (2) Although, the combination of inboard ar.d outboard position indicktion channels is required to meet the sing 1r failure criterion in order to satisfy the Reg Guide 1.97 loop availability requirement, the cabling has been identified as non-safety related therefore; this design is unsatisfactory.

CHANNEL INDEPENDENCE (12): (3) (Need to confirm that independence is maintained between the position indications of redundant isolation valves in p'aing penetrating primary containment). Note, again, that the cabling is non-safety related.

DISPLAY RECORDED (8): (AWJ) Reg Guide 1.97 requires a continuous real- time indication display and recording of one channel for Type B Category 1 variables to provide direct and immediate trend or transient information to the plant operator. Primary reactor containment isolation valve position, whether "closed" o." "non-closed", provides current status rather than either trend or transien: information even though it is a Type 8 variable. GE specification 22A1132AK requires that the indicating lights provide a direct status indication of each respective isolation valve. Using the panel C904 i graphic mimic display, the plant operator can ascertain overall effectiveness I of the primary containment isolation system based on color pattern recognition. Hence, the present PNPS I design is satisfactory.

l l

CHANNEL REDUNDANCY (6): (4) The combination of two position indication channels for isolation valves outside primary containment is required to meet the single failure criterion in order to satisfy the Reg Guide 1.97 channel redundancy requirement. Therefore, auxiliary equipment must be safety related. This design does not meet this requirement.

ELECTRICAL ISOLATION (6): (S) As presently configured, fuses have been used in the valve position indication channel. However, Reg Guide 1.75 considers fuses to be,an unacceptable isolation device since they are actuated by fault current. The existing PNPS ! design does not meet this requirement.

QA REQUIREMENTS (4): [*N!') (Need to confirm that full QA requirements were applied to the isolation valve position switches).

33

TEST ACCESSIBILITY (1): (61 Locally mounted isolation valve position switches may not be immediately accessible during accident conditions.

IDENTIFICATION MARKINGS (1): (7) Since the panel indication is locally

\ mounted in a harsh environment (i.e. not in the control), this requirement is moot. Ci

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PRIMARY CONTAINMENT ISOLATION VALVE POSfTION (258000 & 258001)

(' EXCEPTION l These position switches provide valve indication when torus makeup from the Condensate Transfer System is required. The cabling and power source for this variable were found to be non-safety related. Neither the valves, nor the Condensate Storage Tank are seismically qualifted. No isolation signal is provided to automatically close the valve. In addition, the panel that provides valve position indication for this Type B Category 1 variable is located outside of the Control Room in the RHR and Core Spray Pump Room "B" which is considered to be a harsh environment. The operator, therefore, could not readily identify valve position for A08000 & 8001 during an accident.

To compensate for this situation, the Secondary Containment Control guideline in the Emergency Procedure Guideltnes identifies certain operator actions to be taken if, for example, torus water level were to fall below the downcomer level and a release path developed as a result of failure of non-seismic portion of the system located in the RHR & Core Spray Pump Room "B". ,

The instrument channels for ZS8000 and 8001 will not be upgraded to satisfy 1.97 guidance in light of the above information.

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35 )

l Matrix Evaluation Sheet

( PRIMARY CONTAINMENT ISOLATION VALVE POSITION (FCV-302-120 & 123 and SV-302-121

& 122)

EQ RANGE (20): (1) These directional control valves on the Hydraulle Control Units are not provided with position switches. FOC-302-120 & 123 (Insert) and SV-302-121 & 122 (withdraw) are tyolcal of the 145 Hydraulic Control Units at Pilgrim. Since no valve position indication is provided, the 1.97 range requirement cannot be met. This Type 3 Category 1 variable will be reviewed to establish compliance with 10CFR50.49.

POWER SOURCE (16): (2) Since there are no position switches designed for this variable, no power supply is available. The acceptability vs unacceptability of the power supply is, therefore, moot.

SEISMIC QUALIFICATION (14): (3) Since no instrument channels are designed for this variable, seismic qualification cannot be applied.

LOOP AVAILABILITY (12): (4) This criteria, again, cannot be applied to'this variable, in light of its design characteristics. j CHANNEL INDEPENDENCE (12): (5) This criteria cannot be applied.

O! SPLAY RECORDE0 (8): (6) This criteria cannot be applied.

CHANNEL REDUNDANCY (6): (7) This criteria cannot be applied.

ELECTRICAL ISOLATICA (6): (8) This criteria cannot be applied.

QA REQUIREMENTS (4): (9) This criteria cannot be applied.

TEST ACCESSIBILITY (1): (10] This criteria cannot be applied.

IDENTIFICATION MARKINGS (11): (11] Thiscriteriacannotbeapplied.h 2

(

36

PRIMARY CONTAINMENT ISOLATION VALVE POSI??ON (FCV-302-120 & 123 and SV-302-121

& 122)

( EXCEPTIONS These directional control valves (580), when energized and opened in coordinated pairs, facilitate rod movement either in the insert or withdrawal mode. These valves are normally closed, except during rod movement and are used during normal operation. These valves are, therefore, normally positioned in the safe direction. Where these valves are found to be inoperable, the control rods will be electrically disarmed and placed in such a position that the shutdown margin requirements are satisfled (NOTE:

observation of drive water flow during insert and withdrawal cycle on C905 will provide indication of directional valve problems, i.e., failed closed or open). It should be noted that there are 580 valves which would require position Indication. This appears to be very cost prohibitive and unnecessary, since these valves are not required for scram. No position switches will be provided for these valves in Ilght of the above information.

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37

I Matrix EvaluAtton Sheet l

, PRIMARY CONTAINMENT ISOLATION VALVE POSITION (ZS5065-34 & 38, 255065-32 & 36)

EQ RANGE (20): (1) The 255065-32, 34, 36 & 38 position switches for the Hydrogen Analyzer do not meet the range for Reg Guide 1.97. Direct measurement of valve position is required. The above switches emoloy relays (see E455 & E449) which must be energized before indication of valve closure is provided on control room panels C904 or C902. The above design does not meet the 1.97 requirements for range requirements. This Type B Category 1 variable will be examined for environmental qualification compilance.

PCHER SCORCE (16): (A) Power is provided by redundant safety related power sources, both AC and DC powered. The power sources are Y3 and Y4 and 04 and i

05. 4 SEISMIC QUALIFICATION (14): (NI] (need to confirm selsmic qualification of the valve position switches). RG 1.97 requires seismic qualification for.this variable.

LOOP AVAILABILITY (12): CA] The position switches for the hydrogen analyzer instruments channels provide sufficient latitude to accomodate testing and maintenance requirements that will be necess3ry during power operation. Note.

that cabling is safety related. This design meets Reg Guide 1.97 requirements.

CHANNEL INDEPENDENCE (12): (A) Sufficient independence is provided based on

( installation of safety related components in the channel DISPLAY RECORDED (8): (AWJ) Reg Guide 1.97 requires a continuous real- time indication display and recording of one channel for Type B Category I variables to provide direct and imediate trend or transient information to the plant operator. Primary reactor containment Isolation valve position, whether "closed" or "not-closed". provides current status rather than etther trend or transtant information even though it is a Type 8 variable. GE specification 22A1132AK requires that the indicating lights provide a direct status indication of each respective isolation valve. Using the panel C904 graphic mimic display, the plant operator can ascertain overall effectiveness ;

of the primary containment isolation system basGd on color pattern i recognition. Hence, the present PNPS I design is satisfactory. '

CHANNEL RE00NOANCY (6): (A) Sufficient redundancy is provided by the instrument loops for the hydrogen analyzer position switches. This design I ccepiles with Reg Guide 1.97.

~

i ELECTRICAL ISOLATION (6): (2) As presently configured, fuses have been used in the valve position indication channel. However, Reg Guide 1.75 considers fuses to be unacceptable isolation device since they are actuated by fault '

current. The existing PNPS I design does not meet this requirement.

QA RECO!REMENTS (4): (*NI'] (Need to confirm that graded QA requirements were applied to the (solation valve position switches).

I TES* ACCESSIBILITY (1): (A) Equipment mounted on panel C904 ts accessibit curing all plant operating modes. Locally mounted isolation valve position switches may not be imediately accessible during accident conditions.

33

IDENTIFICATION MARKINGS (1): (A) Reg Guide 1.97 requires distinctive markings for this variable which is satisfied by the PNPS I graphic mimic display on panel C904.

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PRIMARY CONTAINMENT ISOLATION VALVE POSITION (255065-34 & 38, Z55065-32 & 36)

EXCEPTION

[

This is a Type 8 Category I variable. The~ purpose of this variable is to monitor accomplishment of isolation. The position switches provide an ,

indirect measure of valve position. Drawings E449 and E555 indicate that a relay is used to energize contacts for light indicators on panels C904 and C902. Even tl.ough the PNPS 1.97 evaluation has identified that relays are used, this design is considered to meet 1.97 guidance. The use of relcys to energize contacts for lights on C904 and C902 in conjunction with diverse safety related power sources (i.e., 125v CC and 120v AC) provides sufficient assurance that the operator will have available sufficient information to establish accomplishment of isolation for this variable. This variable will not be upgraded in light of the above information.

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Matrix Evaluation Sheet

( CORE SPRAY FLOW EQ RANGE (20): (ANJ) The existing instrument range of 0 to 5000 gallons per minute meets the USNRC required range of 0 to 3960 GPM equivalent to 110% of design flow as snown in FSAR ',able 6.3-1. These transmitters, FT1461A and 8 are included in the BECo Envirer. mental Qualification Master List.

Justificatton for acceptance is based on range compitance.

POWER SOURCE (16): [1] The flow measurement in each core spray loop is supplied from a common E/Sla50-6 power supply in panel C919 (Reference I&CS 84-11/S&SA 84-14), and does not meet the Rag Gu!de 1.97 requirement for a reliabt; ocwor source for this Type O Category 2 variable. A safety related standby power source is not required for the flow measurement in either core spray loop; however, continued use of a comon power source for both flow measurements could lead to increased plant outage because of Technical '

I. Specification limits resulting from Reg Guide 1.97 section 1.3.2.c.

Independent and reliable power sources are recomended for the core spray loop A and loop 8 flow measurements.

SEISMIC QUALIFICATION (14): (*N!') (Need to confirm seismic qualification of the flow element and locally r 'unted flow transmitter). Core Spray local 4 racks C2201 and C2260 have basn seismically qualifted for PNPS I as described M GE Seismic Qualification Summary specification 17489075. Similarly, panels C919 and C903 used for portions of the Core Spray flow instrumentation have been seismically qualified as described by GE specification 235A1963 and 235A1958 in this same sumary.

LOOP AVAILABILITY (12): (A) This Cat 2, Type 0 variable meets the 1.97 design requirement in that the out of service interval is based on the Core Spray System Tech. Spec. 3.5 for Pilgrim.

CHANNEL INDEPENDENCE (12): (A) Channel independence has been established for the core spray flow measurement in C919 by approved departmental procedures, vendor specifications, and industry standards. This has been reflected via appropriate elementary drawings. Therefore, it is felt that sufficient assurance is provided for maintaining core spray loop independence from apprcpriate divisions of RHR, HPCI, ADS, and RCIC loops in C919.

DISPLAY RECORDED (8): [A] Reg Guide 1.97 does not require recording for this l

variable hence, the present PNPS I design is satisfactory.

CHANNEL REDUNDANCY (6): (A) Reg Guide 1.97 does not require redundanc,y for this variable; hence, the present PNPS ! design of one flow measurement per

core spray loop is appropriate.

, ELECTRICAL ISOLATION (6): (A) Confirmatica tnat c4ble tray and conduit i

routing meets separation requirements in all respects has been and is assured

by approve 4 departmental procedure, vendor specifications, and industry 1

str.ndards (i.e., SEQAM, Bechtel Design Gfiteria for Electrical Installations

, and GE Specifications #22A1421. E-347. IEEE279-1971). This also applies to

confirming adequate separation and electrical isolation for existing wiring by reviewing and approving associated pull cards.

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4 41

l QA REQUIRCHENTS (4): (3) The core spray flow. instrument looos are non-safety related based on the original plant design, and does not satisfy the application of graded QA requirements specified in Reg Guide 1.97.

( TEST ACCEf j!BILITY (1): (A) Equipment mounted on panets C919 and C903 is accessibit during all plant operating modes. Core spray flow transmitters mounted on instrument racks C2201 and C?.260 may not be accessible for certain design basis events.

IDENTIFICATION MARKINGS (1): (A) Reg Guide 1.97 does not require distinctive markings for Type O Carsgory 2 variables; hence, the present PNPS I design is satisfactory.

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CORE SPRAY FLOW I IMPROVEMENTS This Type O Category 2 variable is used to monitor operation of the Core Spray System. Because 1.97 specifies that the out-of-service interval should be based on the Tech Spec limitations for the system, a redundant, internal power supply will be added (see Figura 10 to minimize loop unavailability due to failure of the existing common power supply. Associated QA documents will be provided.

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Hatrix Evaluation Sheet

( RHR HEAT EXCHANGER OUTLET TEMPERATURE EQ RANGE (20): (AWJJ The existing instrument range of 0 to 600*F for RHR heat exchanger temperature elements meets the USNRC required range of 32 to 350*F. Temperature elements TE1047A and B will be reviewed to establish compliance with 10CFR50.49. Justification is based on the existing range will be required since the sensors may not be Quallfled for their service conditions.

l PCHER SOURCE (16): (A) The TR2340-9 temperature recorder used to record the RHR heat exchanger temperature values is connected to instrument bus YI, which meets the Reg Guide 1.97 reliable power source requirement for this Type O Category 2 variable.

SEISHIC QUALIFICATION (14): (*N!*] (Need to confirm seismic qualification of i the temperature element and control room kanel C921). - -

l LOOP AVAILABILITY (12): (A) The RHR heat exchanger temperature teasurement is subject to meeting the system's technical specification requirement as a .

result of Reg Guide 1.97. PNPS I Tech Spec Section 3.5 accomodates this l requirement. .

l CHANNEL INDEPENDENCE (12): (1) The comon recorder for RHR heat exchanger temperature monitoring and its single power source do not satisfy this Reg

( Guide 1.97 requirement. However, this design configuration could prove to be unnecessarily prohibitive, since the out-of-service interval fo.' the system could be limited to the failure frequency of the comon recorder, TR2340-9.

DISPLAY RECORDED (8): (A) Reg Guide 1.97 does not require recording for this variable. However, trend information regarding the temperature of the RHL RBCCW, or the SSW cooling loop is considered important. Since the rate of change of any one of these variables with time is relatively slow, recorded trend Information may assist the operator in detecting equipment malfunctions ,

in these three cooling loops. The present PNPS I design provides recording of RBCCW RHR heat exchanger outlet temperature for each RBCCW loop, and also provides recording of RdR heat exchanger outlet temperature for each RHR loop. Recording of one RHR loop temperature and one RBCCW loop temperature in each cooling train on one recorder fulfills the redundant channel requirement since these variables will behave in a similar manner.

CHANNEL REDUNDANCY (6): (A) Reg Guide 1.97 does not require redundancy for this variable; hence the present PNPS I design of one tem;:erature measurement per RHR heat exchanger Icop is appropriate.

ELECTRICAL ISOLATION (6): (2) The use of one recorder and one power source for RiR heat exchanger temperature monitoring does not meet physical separition or electrical isolation requirements.

QA REQUIREM(NTS (4): (3) The RHR heat exchanger temperature monttoring g instrument loops are non-safety related based on the original plant design, and do not satisfy the application of graded QA requirements specified in Reg Guide 1.97.

44 a

TEST ACCESSIBILITY (1): (A) Equipment mounted on panel C921 is accessible during all plant operating modes. RHR heat exchanger temperature s.;.* ors may !

not be imediately accessible during accident conditions.

k 10ENTIFICATION MARKINGS (1): (A) Reg Guide 1.97 does not require distinctive markings for Type O Category 2 variables; hence, the present PNPS I des 157 is satisfactory. , ;

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RHR HEAT EXCHANGER OUTLET TEMPERATURE IMPROVEMENT A single recorcer on panel C921 has been identified for readout of both channels for this Type D Category 2 variable. Space, however, does not permit installation of a redundant recorder. Therefore, a redundant recorder cannot be Installed. To compensate for this, credit can be taken for computer link-up which provides an update of the heat exchanger outlet temperature (i.e., A1084 & A1085). Additional credit can be taken for SPOS. Associated QA documents, will be provided for existing equipment design to establish extent of compliance with graded QA requirements. These improvements are Identified on Figure 13.

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Matrix Evaluation Sheet

. COOLING WATER TEPPERATURE TO ESF (RBCCW - RHR OR SSW - RBCCW)

EQ RANGE (20): (AWJ) The existing instrument range of +32 to +600'F for the Reactor Buildtrig Closed Cooling Water RHR heat exchanger outlet temperature element meets the USNRC required range of 32 to 200*F for this Type O Category 2 variable. The TE1045A and B sensors will be reviewed to determine compilance with 10CFR50.49. Acceptance is presently based on range capability.

POWER SOURCE (16): (A) The TR2340-9 temperature recorder used to record the RBCCW RHR heat exchanger outlet temperature value is connected to instrument bus Y1, which meets the Reg Guide 1.97 reliable power source requirements for this Type O Category 2 variable.

SEISMIC QUALIFICATION (14): (*N!') (Need to confirm seismic qualification of ;

the temperature element and control room panel C921). Reg Guide 1.97 does not _

require selsmic qualification for this variable.

LCCP AVAILABILITY (12): (A) Requirement related to out of service interval is related to RBCCW/SSW pump capacity as noted in PNPS I Tech Spec Section 3.5. Flow as opposed to temperature is the criteria used when determining operability of the system.

CHANNEL INDEPENDENCE (12): (1) The common recorder for RBCCW RHR heat exchanger outlet temperature monitoring and its single power source do not satisfy this Reg Guide 1.97 requirement. Reg Guide 1.97 does not require redundant channels within each RBCCW RHR neat exchanger loop; hence, the present PNPS I design of one temperature measurement per RBCCW train is appropriate.

O! SPLAY RECORDE0 (8): (A) Reg Guide 1.97 does not require recording for this variable. However, trend information regarding the temperature of the RHR, RSCCW, or the SSW cooling loop is considered important. Since the rate of change of any one of these variables with time is relatively slow, recorded

trend information may assist the operator in detecting equipment malfunctions in these three cooling loops. The present PNPS I design provides recording of RBCCW RHR heat enchanger outlet temperature for each RSCCW loop, and also provides recording of RHR heat exchanger outlet temperature for each RHR loop. Recording of one RHR loop temperature and one RBCCW loop temeerature in each cooling train on one recorder fulfills the redundant channel requirement since these variable will behave in a similar manner.

CHANNEL REOUNDANCY (6): (A) Reg Guide 1.97 does not require redundancy for

< thi5 variable; hence, the present PNPS ! design of one temperature measurement per RSCCW loop is appropriate.

ELECTRICAL ISOLATION (6): (2) The use of one recorder and one power source 1 for RBCCW RHR heat exchanger outlet temperature monitoring does not meet physical separation or electrical isolation requirements, e

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QA REQUIREMENTS (4): (3) The RBCCW RHR heat exchanger outlet temperature

, monitoring instrument loops are non. safety related based on the original plant design, and do not satisfy the application of graded QA requirements ;ecified g in Reg Guide 1.,97.

TEST ACCESSIBILITY (1): (A) Equipment mounted on panel C921 is accessible during all :lant operating modes. RSCCW RHR heat exchanger outlet temperature sensors may not be immediately accessible during accident conditions. ,

IDENTIFICATION MARKINGS (1): (A) Rag Guide 1.97 does not require distinctive markings for Type O Category 2 variables; hence, the present PNPS I design is satisfactory, t

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i COOLING WATER TEMPERATURE TO ESF (RBCCW - RHR CR SSW - RBCCW)-

4 IMPROVEMENT .

The avaluation of channel independence for this Type 0, Category 2 variable indicatec that a single recorder is unacceptable. However, the addition of a i redundant recorder is precluded since sufficient space for installation of the i recorder is not available. Boston Edison will. therefore, not install a i redundant recorder. To compensate for this, a cceputer Itnk-up is available i to provide adequate information regardina ESF Terrperature (i.e. A1083 & '

A1082). Additional credit een be taken for SPDS. Figure 14 Identifies the !

modifications to be performed for this variable.

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Matrix Evaluat:en Sheet RADIATION EXPOSURE RATE i

EQ RANGE (20): (1) The ranges of the reactor, turbine and radweste building access area radiation monitor measurement do not meet the USNRC specified range requirement (10*' to 10" R/hr) for this Type E Category 2 ,

<. variables. According to GE drawing 112C2230, the RE10 (1802) area radiation >

monitor can cover a four decade range extending from 10 " to 10*' R/hr.

The area radiation monitor RE10 will be reviswed for environmental qualificattoa. The exposure rate monitor's upper range does not treet 1.97 guidance.

1 POWER SOURCE (16): (A) Electrical power is provided through YI, from panel C911 (see M1U-2-2). As such Y1 is powered from a reliable source (OG) and therefore the present PNPS design is satisfactory.

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1 SE!SMIC QUALIFICATION (14): (A) Reg Guide 1.97 does not require seismic' qualification for this variable; hence, the present PNPS I design is satisfactory.

LOOP AVAILABILITY (12): ('NI'] (Need to confirm that the reactor building -

access area radiation monitoring channel meets the system technical specification requirements since Reg Guide 1.97 places a Technical -

Specification availability requirement en this variable.

l CHANNEL INDEPENDENCE (12): (A) Reg Guide 1.97 does not require redundant channels for this variable; hence, the present PNPS I design 15 satisfactory, e t

O! SPLAY RECORDED (8): (A) Reg Guide 1.97 does require channel recording for effluent monitoring variables. The existing PN75 I rf.dlation monitoring channels satisfy this requirement by recorder RRis15-6 on the C902 main j control room panel.

CHANNEL REDUNDANCY (6): (Al Reg Guide 1.97 does not require redundancy for this variable; hence, the present PNPS I design is satisfactory.

1 ELECTRICAL ISOLATION (6) (2) Reg Guide 1.97 requires isolation devices f i having maintenance access provisions for this variable. The present PNPS I !

design does not include electrleal isolation devices, and therefore, does not '

satisfy this requirement.

i QA REQUIREMENTS (4): (*N!*) (Need to confirm application of graded QA i l requirements for this area radiation monitoring channel since Reg Guide 1.97 ;

requires graded QA for this variable). )

l TEST ACCESSIBILITY (1): (A) Equipment located on panels C911 and C902 is j accessible during all modes of reactor operation. Area radiation monitoring l Instruments locally mounted may not be immediately accessible during accident l conditions.,

IDENTIFICATION MARKING 3 (1): (A) Reg Guide 1.97 does not regelre identification markings for Type E variables; hence, the present PNPS I design is satisfactory.

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l RADIATION EXPOSURE RATE

( IMPROVEMENTS The evaluation for this Type E Category 2 variable indicates that the range requirement does not satisfy the 1.97 range requirement. Reg Guide 1.97 specifies a range of 10*' to 10' R/hr for this variable. PNPS I actual range is 10 to 10*' R/hr. In aedition, confirmation of loop availability is required to establish whether Tech Spec availablitty requirements are satisfied. The purpose of this variable is to provide a means of detecting significant releases inside buildings or areas where access :

is required to service equipment important to safety. Therefore, based on !

L Figure 15. the range of the RE-10 monitor will te increased to coincide with i range requirement in Reg Guide 1.97. Confirmation of loop availtellity will ,

be performed. ,'

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I-3.1.3 Erceotions to Oeston and Qualification Criteria ,

Two general areas of design and qualification criteria noncomollance were i identified as a result of the PNPS I evaluation centered on electrical '

isolation devices and channel redundancy.

Electrical Isolation It is Boston Edison's intent to forego reolacement of fuses for some othei-type of isolation devices (i.e., relays, fibre optics connectors, etc.). Reg Guide 1.97 indicates that Reg Guide 1.75 will serve as the standard for the separation of circuits and equipment that are redundant. Pilgrim, which ,

pre-dates Reg Gutae 1.75. was designed to meet proposed IEEE Criteria for '

Nuclear Power Plant Prctection Systems dated March, 1968. Boston Edison met this requirement which was subsequently approved by the Atomic Energy Commt15 ton.

Installed fuses are IJL approved and have been used at Pilgrim over the past 10 years althout any generic problems. Further assurance of fuse continutty is. E provided via pre-scheduled functional tests of Class lE systems. In light of the above information, Boston Edison will not replace instrument fuses.

Channel Redundancy Another po'nt of conNntion relates to the following design and qualification criteria spectfled in Reg Guide 1.97:

"Where failure of one accident monitoring channel results in

$nformation ambiguity (that is, the redundant displays disagree) that could lead operators to defeat or fall to accomolish a required safety function, additional information should be provided to allow the operators to deduce the actual ,

conditions in the plant."

Boston Edison takes exception to the criteria to provide a means of resolving information amoiguities caused oy an assumed single failure in one channel j based on the following: l

- the instrumentation channels are 8: 'ipendent and must meet class IE requirements and these channels are to be environmentally qualifted for quality category, thus minimizing the effects of comon mode failure Based on the above information, Boston Edison does not plan to make any modifications in order to conform to the above two criteria. However, to the extent possible, Boston Edison will identify alternate courses of action (i.e., cross checking with an independent channel which monitors a different variable which has known relationship to the primary variable.)

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SEGION II - CONCWSIONS ..

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!!-l Database Maintenance Supplement I to NUREG'0737 indicates that "staff review will be in the form of

, an audit that will include a review of the licensee's method of implementing Regulatory Guide 1.97 (Rev. 2) gulcance and the licensee's supporting technical justification of any proposed alternatives." The methodology used by Boston Edison has already coen discussec in this report. However, to assure that traceability is maintained, the PNPS 1.97 document flies and computerized database will be maintained in a controlled fashion. -

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!!.2 CorrecQ1ve Actions 9o Complete Da9 abase information As noted on Table 3. Additional Informatten (N!) is required for certain I variables. Even though the plant specific variables identifled on Table 3 have been found to be acceptable an attempt to replace NI with the associated information will be made for completeness.

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If-3 Environmental Qual 19tcation

! As indicated in Supplement I to NUREG 0737, e "It is acceptable to rely on currently installed equipment if it will measure over the range Indicated in Regulatory Guide i

1.97 (Rev. 2), even if the equipment is presently not environmentally Quallfled. Eventually, all the equipment reautred to monitor the course of an accident would be environmentally quallfled in accordance with the pending .

commission rule on environmental quellfication." J This has served as i basis for accepting (i.e., EQ/ Range design requirement) ,

many of the tilsting instrueent channels reviewed for the PNPS ! 1.97 l l

evaluation. All Category I variables reviewed for Pilgrim will te i s environmentally quallfled by the end of Refuel Outage #8. t Category 2 variables will not be environmentally qualified subject to the design and Qualification criteria in Reg Guide 1.97. This position is based on the fact that Category 1 variables will be environmentally quallfled as a :

result of Reg Guide 1.97 since they are key variables. The only Category 2 - !

variables that will be environmentally quellfied will be quellfied as a result i of 10CFR50.49 requirements. l 0

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!!-4 Setsmicity 1 A concern exists that the margin of safety provided in the electrical and '

( mechanical equipment important to safety of operating plants may vary ;

, considerably. Specificall", the implication 15 that the margins of safety that are provided in the existing equipment to resist selsmically induced J

loads and to perform the extended safety functions may vary considerably. The 1 concern, however, does not imoly that the safety margins are not adequate.

l This has arisen because seismic qualification criteria and methods have i i undergone rapid develocrrent in recent years. The methods for demonstrating i component operability have changed significantly and because the design of the operating plants were ccmpleted prior to the establishment of current selsmic ;

qualification criteria and guidelines. This would especially apply to older :

j plants Itke Pilgrim. Unresolved Safety !ssue A-46 was initiated to address ,

4 the above concern. When resolved, a NRC generic letter containing consistent l requirements for seismic and dynamic qualification will be applicable to ,

Pilgrim and other operating plants. Pending the issuance of the generic letter, Boston Edison will defer re-assessing the margin of safety of entsting

l electrical equipment to resist seismically induced loads at Pilgrim Station.-

This would apply to those items identified by R.G. 1.97 as requiring selsmic qualification. It should be noted, however, that Boston Edison will continued where deemed appropriate to use IEEE344-1975 in applying seismic qualification j r<quirements to future electrical equipment modtfications. IEEE344-1975 l provisions are included in Reg Guide 1.100 and are cited in Reg Guide 1.97. ,

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!!-5 Commt9 ment Ac9 ton Plan Per Sunnlement I to NUREG 0737, Sotton Edison will implement identified

( tmorovements (see Section I-3.1.2) by the end of Outage #8 at Pilgria Station. At such time, Boston Edison will notify the NRC of its completion of Phase II requirements.

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I References

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1. Regulatory Guide 1.97 Rev. 2, Instrumentation for Light-Water Cooled i Nuclear Power Plants to Access Plant and Environs Conditions During and Following An Accident. December, 1980.

j 2. Nuclear Utility Task Action Committee, Regulatory Guide 1.97 (Accident 1 Monitoring Instrumentation) Implementation Guideline, INPO 83-049 (NUTAC), December, 1983.

3. 8WR Owners Group, Posttion on NRF, Regulatory Guide 1.97, Rev. 2 July, 1982.

4. ANS!/ANS-4.5-1980, Criteria for Accident Monitoring Functions in

Light-Water-Cooled Reactors.

Supplement 1 to NUREG 0737 Requirements for I

5. Generte Letter #82-33:

Emergency Response Capability, December 17, 1982.

6. 8Eco Letter #83-97: Response to NRC Generic letter #82-33 dated !

Oecember 17, 1982. :

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7. IEEE 497-1981, IEEE Standard Criteria for Accident Monttering ,

3 Instrumentation for Nuclear Power Generating Stations, 1981. l I

I 8. INP083-048 (NUTAC), Guidance for an Integrated Implementation Plan for Emergency Response Capabilities.

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ADoendix A i

Reg Guide 1.97 Design and Qualification Criteria 9

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l R.G. 1.97. Rev. 3 Requirements Qual. Category 1 Qual. Category 2 Oual. Category 3 I. Seismic Qualification R.G. 1.100; Accuracy No ho After DBE

2. Environmental Qualification R.G. 1.89; NUREG 0588' Same as Cat. l' No. but must meet servl:e*

j environment conditions t

l 3. Single failure Criterla Yes No No aedundancy Yes. 2 maybe 3 channels No No Isolation from Safety System R.G. 1.75 Isol. Devices Same as Cat. I Not apolicable

4. Power from On-Site Standby Sources R.C. 1.32 No No Power from Battery-Sacked Bus Yes. If interruption Same as Cat. I No not tolerable f Power from Highly Rellable Bus No Yes No S. Display is continuou".. real-time Yes, I channel No No i Display is also recorded Yes, all channels

Effluent radioactivity. Effluent radioactivity, area area RAD monitors GD monitors. Meteorology

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monitors 1

Display is uniquely identlfled Yes, types A. 8. C Same as Cat. I No I

1 Display is Dedicated Trend Yes, if needed for Same as Cat. 1 Same as Cat. 1 I recorders op3rator info or action

6. Quality Assurance Yes Yes, but graded QA No 4

application possible

< 7. Periodic Test Capab!'*ty Yes. R.G. I.118 Yes, same as Cat. 3 Yes r .

1 Appendlu A Page 1 of 2 l

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R.G. l.97. Rev. 3 Requirements Qual. C6.tegory 1 _

Qual. Category 2 Qual. Category 3

8. Channel Availability Prior to Yes Conform to sys'em No Accident Tech. Spec.

9. Instruments overlay on range Yes Yes Yes

10. Direct measurement by variable Yes Yes Yes

!!. Haman factors consideratloas' Yes Yes Yes 1 Qualification delayed if ranges meet R.G. l.97 (Ref. 1. Page 13) 2 Meteorological Instruments OK If historically reliable (Ref. l. Page 13) 3 Cat. 2 Type C instruments quellfled per ANS 4.5 para 6.3.5 rather than just Cat. 1 Type C Relamation of requirements verius R.G. l.97. Rev. 2 4 All channels recorded rather than just one channel. Hintze (NRC) says this is n% changed to one channel 2/25/82 Escalation of requirements versus R.G. 1.97. Rev. 2

5. Please note that human factors consideration limited to identifying adequacy of instrument markings, since no relocation of displays was required as a result of the PlePS evaluation. ,

References:

(1) NURfG 0737 Supplement 1 12/17/83 .

Appendix A (cont'd) .

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ML20204J401

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References:

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