Text

Notice of Consideration of Issuance of Amend to License DPR-80 & Proposed NSHC Determination & Opportunity for Hearing Re Conformance W/Generic Ltr 83-43 on LER Sys
	ML20128H550
Person / Time
Site:	Diablo Canyon
Issue date:	06/12/1985
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML19298B008	List: ML20128H507; ML20128H527; ML20128H550;
References
	GL-83-43, NUDOCS 8507100092
	Download: ML20128H550 (66)
	v • d • e

.

UhlTED STATES NUCLEAR REGULATORY COPAISSION PACIFIC GAS AND ELECTRIC COMPANY DOCLET EG. 50-275 h6TICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE A'ND FRGPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Comnission) is considering 5

issuance of an amendrent to Facility Operating License No. DPR-80, issued to Pacific Gas and Electric Company, the licensee, for the operation of the Diablo Canyon Nuclear Power Plant, Unit 1, located in San Luis Obispo County, California.

In accordance with of the licensee's applications for amendment dated May 14 (LAR85-01Rev.4andLAR85-03),May20(LAR85-04)andHay 30,1985(LAR 85-05andLAR85-06),theproposedchangeswouldrevisetheDiabloCanyon Unit 1 Technical Specifications to eliminate typographical errors, provide additional clarification, improve consistency, adjust nomenclature, modify the rcporting requirements to bring then into conformance with the guidance in Generic Letter 83-43 for the Licensee Event Report Systen, bring porticns of the Specifications into conformance with current NRC staff positions, incorporate Unit 2 inforretion where appropriate, and nuke other minor changes. A prin.ary cbjective of the amendment request is to achieve a single

/,

Technical Specifications document that is connon for the nearly identical Units 1 and 2 with individual specificiations for each Unit cleirly icentified, asapprcpriate.

In this regard, the proposed changes to the Unit *4 Technicti Specifications are consistent with the Unit E Technical Specifications recertly b N!!N$75 P

PDR m

2 issued as Appendix A to Facility Operating License DPR-81 and proposed changes to the Unit 2 Technical Specifications included in the licensee's, application for amendment to DPR-81 dated May 14, 1985.

Furthermore, most of,*t_he Unit 1 proposed changes have already been incorporated by the Comission into the

~

current Unit 2 Technica1' Specifications as a part of DPR-81. This becomes a pertinent consideration in evaluating whether or not the Unit 1 proposed changes involve a significant hazards consideration, and is so recognized in the proposed determination.

\\

The following is a description of the proposed changes to the current Unit 1 Technical Specifications:

1.

Page 1-2, item c of Definition 1.8, CONTAINMENT INTEGRITY, is changed from "c. Each air lock is OPERA 8LE pursuant to Specification 3.6.1.3" to "c.

Each air lock is in compliance with the requirements of Specification 3.6.1.3".

2.

Page 1-2 Definition 1.10, an "s" is added to the title of " CORE I

ALTERATION" ano " reactor pressure vessel" is changed to " reactor vessel".

l 3.

Page 1-3, in Definition 1.11, Table E-7 of NRC Regulatory Guide 1.109 Revision 1. October 1977 is added as an additional source of thyroid dose conversion factors, and the definition of the AVERAGE DISINTEGRATION ENERGY,1.12,ischangedto"Eshallbetheaverage(weightedin proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gama energies per disintegehtion (MeV/d) f for the radionuclides in the sample."

W

3 4

Pages 1-3 and 1-5 the tables referenced in Definition 1.15, FPEOUENCY NOTATI0tl, and Definition 1.21, OPERATIONAL i;0CE, are reversed to Table 1.1 and Table 1.?, respectively; Table 1.1 on page 1-8 becomes Table 1.2, and Table 1.2 on page 1-9 becomes Table 1.1.

These changes are made for consistency with tFe order in which the tables are cited in the text.

5.

Page 1-4, in Definitions 1.16 and 1.17, change " primary coolant systen" and " primary system" to "Peactor Coolant System", and change " secondary system" to " Secondary Coolant System". Make these changes, where applicable, throughout the document.

6.

Page 1-5, the last line of Definition 1.27, RATED THERMAL POWER, which only includes Unit I data, is changed to "..

3338 PP for Unit I and t

3411 Ph for Unit 2."

t 4

[

7.

Page 1-6, Definition 1.29 of REPORTABLE OCCURRENCE, is replaced with

" REPORTABLE EVENT shall be any of the conditions specified in Section 50.73 of 10 CFR Part 50.." and the term " REPORTABLE OCCURRENCE" is changed throughout the Technical Specifications to "REPORTABLF EVEi.'T."

P.

Pape 1-4,1-5,1-6 and 1-7, Definitions 1.19, 1.20, 1.21, 1.22, 1.23, 1.24, 1.25, 1.26, 1.27, 1.28, 1.29, 1.30, 1.31, 1.32, 1.33, 1.34, 1.35, 1.36, 1.37, and 1.38 are renumbered to 1.20, 1.21, 1.22, 1.23, 1.24, 1.25, 1.26, 1.27, 1.28, 1.29, 1.30, 1.31, 1.33, 1.34, 1.35, 1.36, 1.37, 1.38, 1.39, 1.41'a'nd 1.42, respectively, to account for the three new definitions, 1.19, 1.32 and 1.40.

]

,1

4 9.

Page 2-1, in Specifications 2.1.1 and 2.1.2, Reactor Core and Reactor Coolant System Pressure, add "... and comply with the requirements of Specification 6.7" at the end of the ACTION statement.

10. Page 2-4. Sp'ecification 2.2.1. Table 2.2-1, the footnote is changed to " Design flow is 87,700 gpm per loop for Unit I and 88,500 gpm per loop for Unit 2" (Unit 2designflowadded).

~

11. Page 2-6 Specification 2.2.1, Table 2.2-1, item 22.d is changed from " Low

~

Setpoint Power Range Neutren Flux, P-10" to " Power Range Neutron Flux, P-10".

12. Page 2-7, Specification 2.2.1. Table 2.2-1, the table subtitle is modified to

" TABLE NOTATIONS", and in note 1 the defintion of T' is replaced with "T' 0

0

= less than or equal to 576.6 F for Unit I and less than or equal to 577.6 F for Unit 2 Reference T,yg at RATED THERMAL POWER" (Unit 2 T,yg added).

13. Pages 2-8 and 2-9, Specification 2.2.1. Table 2.2-1, the table substitute is changed to " TABLE NOTATIONS" and in Notes 2 and 4. " trip point" is changed to"TripSetpoint"(twiceeach).

14 Page 2-9 Specification 2.2.1, Table 2.2-1, in Note 3, the definition of T" is 0

changed to "T" = less than or equal to 576.6 for Unit I and less than 0

or equal to,577.6 F for Unit 2 Reference T,yg at RATED THERMAL POWER" (Unit 2T,yg added).

/

5

15. Page 2-9, Specification 2.2.1. Table 2.2-1, in Note 3, the definition of K 5

is changed to "... averace tenperature, and 0 for decreasing..."

I 16 The note before page B 2-1 is changed to "The PASES contained in the succeeding pages summarize the reasons for the Specifications of Section 2.0, but in accordance with 10 CFR 50.36 are not pert of these Technical Specifications."

17. Page B 2-1, Bases for Specification 2.1.1, in the second and third sentences of the second paragraph, the reference to the "W-3" correlation is replaced with one to the "R-prid" correlation.

18. Page B 2-2, Bases for Specification 2.1.2, delete "1967 Edition" from the ANSI Standard reference for the RCS piping end fittings design.

l6 t.

19. Page B 2-2, Bases for Specification 2.1.2, and Pages 3/4 9-3, 3/4 9-6, and 3/4 9-9, Technical Specification 2/4.0, Pefueling Operation, "reector pressure vessel" is replaced with " reactor vessel".

20.

Page B 2-3, Bases for Specification 2.2.1, " Reactor Prctection System" is replaced with " Reactor Trip System" (four times).

?).

Peoe B 2-3, Bases for Specification 2.2.1, in the second paragraph, replace

" Reactor S,vs' ten" with " Reactor Coolant System" and other places throughout the document.

3 m

6 22.

Page B 2-4, Bases for Specification 2.2.1 the second paragraph under the heading " Power Range, Neutron Flux, High Rates" is replaced with "The Power Range Negative Rate Trip provides protection for contrU rod drop

~

accidents. At high power, a rod drop accident could cause local flux peaking which could cause an unconservative local DNBR to exist. The Power Range Negative Rate Trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate Trip for those control rod drop accidents for which theDNBRswillbegreaterthan1.30."

l

23. Page B 2-4, Bases for Specification 2.2.1, the title of the "Intennediate and Source Range, Nuclear Flux" section, and first line of the corresponding paragraph is changed to " Intermediate and Source Range Neutron Flux". Also in the same paragraph " reactor core protection" is h

replaced with " core protection", and " Reactor Protection System" with

" Reactor Trip System".

24. Page B 2-5, Bases for Specification 2.2.1, the title of the reference in the top paragraph is corrected to "WCAP-9226, Reactor Core Response to Excessive Secondary Steam Releases".

25.

Page B 2-7, Bases for Specification 2.2.1, the seventh and eighth 1ines in the paragraph discussing the Steam /Feedwater Flow Mismatch and the Low i,

Steam Generator Water level setpoints are changed to"...when the steam 6

flowexceedsthefeedwaterflowbygreaterthanorequalto]1.45x10 0

lbs/ hour for Unit 1 and 1.49 x 10 lbs/hrforUnit2"(Unit 2valueadded).

./

7

26. Page B 2-B, Bases for Specification 2.2.1, under Reactor Coolant Punn Breaker Position Trip, " reactor core protection" is replaced with " core protection" in the second line, and " accident analyses" with'" safety r

analyses" in the fourth line.

27. Pages B 2-6, B 2-9, 3/4 4-25, 3/4 4-26, 3/4 4-27 (Table 4.4-4 title and footnote),3/44-28(theheadingofFigure 3.4-1), 3/4 7-10, B 3/4 3-2, and B 3/4 4-3 "prirary coolant" is replaced with " reactor coolant".

\\

28. Pages B 2-8 and B 2-9, Bases for Specification 2.P.1, in the paragraphs describing the P-6 end P-IO interlocks, " reactor trip" is replaced with

" trip" (five times).

P9. Pape 3/4 0-1, Specification 3/4.0, Applicability of Limiting Conditions for Operation, add a new specification:

"3.0.5 Limiting Conditions for Operation including the associated ACTION requirements as follows:

r a.

Whenever the Limiting Conditions for Operation refers to systems or components which are shared by both units, the ACTION requirerents will apply to both units simultaneously.

This will be indicated in the ACTION section; b.

Whenever the Limiting Conditions for Operatier epplies to only one unit, this will be identified in the APPLICABILITY section of the specification; and

__p 8

c.

Whenever certain portions of a specification contain operating

~

l parameters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes, or bo'dy of the requirement."

30. Page 3/4 0-3, Specification 3/4.0, Applicability of Surveillance Requirements, add a new surveillance requirement.:

"4.0.6 Surveillance Requirements shall apply to each unit individually unless otherwise i

indicated as stated in Specification 3.0.5 for individual specifications or whenever certain portions of a specification contain surveillance parameters different for each unit, which will be identified in parentheses, footnotes, or body of the requirement."

i a

31.

Page 3/41-1, in Surveillance Requirement 4.1.L1.1d, " Specification of

[

the factors of e, below", is replaced with "of the factors of Specification 4.1.1.le, below".

32. Page 3/4 1-1, the footnote to Specification 3.1.1.1 is changed from "*See Special Test Exception 3.10.6." to "*See Special Test Exception Specification 3.10.1."

33.

Page 3/41-4 Specificaton 3.1.1.3, delete "in lieu of any other report required by pecification 6.9.1" from ACTION a.3.

a i

}-

.,/

i

9 l

34.

Page 3/41-6, the footnote to Specification 3.1.1.4.is changed from "*See Special Test Exception 3.10.3." to "*See Special Test Exception Specification 3.10.3."

~

35.

Page 3/4 1-12, Specification 3.1.2.5a.2) is changed from "Between 20,000 and 22,500 ppm of boron, and" to "A boron concentration between 20,000 and 22,500 ppm, and".

36. Page 3/4 1-13, S'p~ecification 3.1.2.6a.2) is changed from "Between 20,000 and i

22,500 ppm of boron, and" to "A boron concentration between 20,000 and 22,500 ppm, and".

37.

Page 3/4 1-13, Specification 3.1.2.6b.2) is changed from "Between 2000 and 2200 ppm boron, and" to "A boron concentration between 2000 and 2200 ppm, and".

38.

Pages 3/4 1-15 and 3/4 1-16, in Specification 3.1.3.1, Movable Control Assemblies, delete ACTION item b and add new ACTION items c and d.

The previous ACTION item c is redesignated to item b.

This change allows the use of rods which are imovable but retain their trip function and are properly positioned.

39. Page 3/4 1-16, the first line in Surveillance Requirement 4.1.3.1.2,is changed from "Each full-length rod not fully inserted shall be determined to b5...

to "Each full-length rod not fully inserted in the core shall be detennined to be..."

.3 I

/

d

10

40. Page 3/4 1-18, Specification 3.1.3.2, "The shutdown and control rod position indication system..." is replaced with "The Digital Rod

~

Position Indication System..."

~

~

41. Page 3/4 1-18 Specification 3.1.3.2, in ACTION items a and b.1, " rod position indicator" is replaced with " digital rod position indicator".

42. Page 3/4 1-18, in Surveillance Requirement 4.1.3.2, replace " rod position indicator" with " digital rod position indicator", and " Rod Position Indication System" with " Digital Rod Position Indication System" (twice).

~

43. Page 3/4 1-19, Specification 3.1.3.3. " rod position indicator" is 4

K replaced with " digital rod position indicator".

44. Page 3/41-19, the "#" footnote is changed to "# See Special Test Exceptions Specification 3.10.4".

. 45. Page 3/4 1-19. Surveillance Requirement 4.1.3.3 is changed to "4.1.3.3.

Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full range of rod travel at least once per 18 months."

46.

Page 3/4 1-22 Specification 3.1.3.6 is changed to "The control banks shall i.

be linited in physical insertion as shown in Figure 3.1-la for Unit 1 and Figure 3.1-lb for Unit 2" (Unit 2 figure added).

.]

11

47. Page 3/4 1-22, delete "either" in the second line of the introductory sentence under the Specification 3.1.3.6 ACTION statement.

48. Page 3/4 1-23, the designation of Figure 3.1-1 is changed to "3.1.la" and an indicatio'n that it applies to Unit 1 is added. A new Figure 3.1-lb, which applies to Unit 2 is added in page 3/4 1-24.

49.

Pages 3/4 2-1 and 3/4 2-2, Specification 3.21, Axial Flux Difference, is replaced with a revised Specification 3.2.1, which extends the range of applicability from "above 50% RATED THERMAL POWER" to "above 15% RATED THERMAL POWER" and incorporates the LIMITING CONDITION FOR OPERATION and ACTION items that apply within the range of 15% to 50% RATED THERNML POWER.

50.

Page 3/4 2-3, in the third line of Surveillance Requirement 4.2.1.4, insert

" Specification" before "4.2.1.3".

51. Page 3/4 2-5. Specification 3.2.2, in the definition of K(Z) "is" is

,-eplaced by "=".

52. Page 3/4 2-7, in Surveillance Requirement 4.2.2e, the last line is changed from " Specification 6.9.1.14" to " Specification 6.9.1.8".

53. Page3/42-y.inthesecondlineofSpecification3.2.3."R,R"is 1

2 replaced with "R", and item a is changed to define "R".

]

f

,w

._m-

12

54. Page 3/4 2-9, in the third line of Specification 3.2.3, " Figure 3.2-3" is replaced with " Figure 3.2-3a for Unit 1 and Figure 3.2-3b for Unit 2".

55. Page 3/4 2-9, in Specification 3.2.3, item b, which defines R in terms of R 2

3 and the Rod Bow Penalty (RBP(BU)), and item e, which defines RBP(BU), are deleted, and items "c" and "d" are redesignated as items "b" and "c",

respectively.

56. Page 3/4 2-9, in 3pecification 3.2.3, the third line of new item c is changed to "..

3plues of F elta H shall be used to calculate R since Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2... "

57. Page 3/4 2-9, in Specificetion 3.2.3, the second line of the introductory a,

ACTION paragraph is changed to "... acceptable operation shown on Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2".

~

58. Pages 3/4 2-9 and 3/4 2-10, in Specification 3.2.3, ACTION items a.1, b, and c, "R, R " is replaced with "R".

3 2

59. Page 3/4 2-10, in Specification 3.2.3, in the seventh line of ACTION item c l

" Figure 3.2-3" is replaced with " Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2".

60. Page 3/4 2-10, in Surveillance Requirement 4.2.3.2 "R, R " is replaced with 3

p "R" and " Figure 3.2-3" with " Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2".

.3

./

13

61. Page 3/4 2-11, in Surveillance Requirement 4.2.3.3, " Figure 3.2-3" is replaced with " Figure 3.2-3a for Unit I and Figure 3.2-3b for Unit 2" and "R, R " is replaced with "R".

3 2

62. Page 3/4 2-12. Specification 3.2'.3, Figure 3.2-3 is redesignated Figure 3.2-3a, the DNB limit curve and the designation that the other curve represents the "LOCA LIMIT" are deleted, and an indicition that the figure applies to Unit 1 is added.

L.

L

63. Page 3/4 2-13. Specification 3.2.3 Figure 3.2-4 is replaced with a new Figure 3.2-3b, which provides RCS Total Flowrate versus R for Unit 2.

64. Page 3/4 2-18 Specification 3.2.5 Table 3.2-1 is revised to incorporate the limits for the Unit 2 DNB parameters, and thus provide the applicable DNB parameters for each unit.

65. Pages 3/4 3-2 to 3/4 3-7 Specification 3.3.1. Table 3.3-1, Table Notations, is replaced with revised Table Notations to incorporate administrative changes.

In addition, the second and third lines in ACTION 11 are changed to "... channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance..."

5

66. Page3/43-y, Specification 3.3.1, Table 3.2-2,aresponsetime"less than or equal to 0.5 second*", with a reference to the table footnote, is assigned to Functional Unit 6.

SourceRange,NeutronFlix.

__._-m__=

4 14 4

67. Page 3/4 3-13 Surveillance Requirerents 4.3.1.1, Table 4.3-1, the Table Notation "*" is revised to incorporate administrative changes, and Table Notation (6) is changed to "Incore-Excore Calibration, abovi_75% of RATED THERMAL POWER" and "The provisions of Specification 4.0.4 are not

~

applicable for entry into PCDE P er 1" is added at the end of (2), (3) and (6).

68.

Pages 3/4 3-15 to 3/4 3-??, Specification 3.3.2, Table 3.3-3 is revised to incorporate admin'istrative changes.

\\

69.

Pages 3/4 3-15 and 3/4 3-18. Specification 3.3.2, Table 3.3-3 in the Functional Units 1.c. and 4.a. the Applicable Modes are changed from

~

Modes "I, 2, 3" to "1, 2, 3, 4", and the reference to Table Notation "##"

in the Applicable Modes column for the Functional Unit 1.e entry is 4

deleted.

70. Pages 3/4 3-16 and 3/4 3-17. Table 3.3-3, the information in the CHANNELS TO TRIP COLUPN for the 2.a and 3.b.I entries is changed to "2 with 2 coincident switches", and a reference to Table Notation "*" in the ACTION column for the 3.c.1 and 3.c.2 entries added.

71. Page 3/4 3-18, Specification 3.3.2, Table 3.3-3, a reference to Table l'

Notation "##" in the Applicable Modes column is added to the 4.d ertry, the /CTIOM for the 5.a entry is changed to "25", and " ACTION 25 - With e*=

ht#AA P 61***LM M9-. ' N " T

[

_[*"

N'

"~

~ - '

7

15 the number of OPERABLE channels one less than the Minirrum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel mey be bypassed for up to P hours for surveillartee testing per Specification 4.3.2.1, provided the other channel is OPERABLF" is added in page 3/4 3-??.

Pages 3/4 3-23 to 3/4 3-27, Specification 3.3.2, Table 3.3-4 is revised to 72.

incorporate edr nistrative changes, and in pages 3/4 3-23 and 3/4 3-26 the o

~

Allowable Valu,es for entries 1.f.2) and 4.d.2) are chenced from "less than er equal to 585 psig" to "less than or eoual to 580 psig".

73. Papes 3/4 3-28 and 3/4 3-31, Specification 3.3.2, Table 3.3-5 is revised to incorporate edministrative changes, replace the entry under Initiating R

Signal 8 with " Turbine Trip", and add main feedwater bypess valves inforration to Table Notation (2) and, consequently, the requirement to verify response time on these valves.

74. Pages 3/4 3-32 to 3/4 3-36, Surveillance Requirement 4.3.2.1. Table 4.3-2 is revised to incorporate administrative changes, in the Functional Unit 1.c the Applicable Modes are changed from Modes "1, 2, 3" to "1,

?, 3, 4", ard a reference is edded to new Table Notation "(2)

For the Plant Vent Activity - High Monitor, only a CHANNEL FUNCTIONAL TEST shall be performed at least orce very 31 days" for entry 3.c.2).

a

./

16 75.

Page 3/4 3-37, in Specifiertion 3/4.3.3, replace the title with

" RADIATION MONITORING FOR PLANT OPERATION", and insert "for plant operations" after " instrument channels" in the first line of.

Specification 3.3.3.1, after " Alarm Trip Setpoint" in the first line of

~

ACTION item a., after " monitoring channels" in the first line of ACTION item b., and after " instrumentation channels" in the first line of Surveillance Requirement 4.3.3.1.

76.

Pages 3/4 3-38 arid 3/4 3-39, Specification 3.3.3.1, in Table 3.3-6, add 8

"FOR PLANT OPERATIONS" to the title, delete the headings "1.

AREA MONITORS" and "2.

PROCESS MONITORS"; change " Control Room Ventilation Isolation" to " Control Room Ventilation Mode Change"; and change the number of " MINIMUM CHANNELS OPERABLE" for the same line from "1" to "2" r

with a reference to footnote "***", which is added as: "*** One channel for each normal intake to the Control Room Ventilation System (connon to both units)", and change ACTION 30 to "With less than the minimum Channels Operable requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint or an individual qualified in Radiation Protection Procedures with a radiation does rate monitoring device is provided in the Fuel Storage Pool Area. Restore the Inoperable monitors to OPERABLE status l

within 30 days or suspend all operations involving fuel movement in the l~

i fuel storage pool area."

1 I~

s

.)

17

77. Page 3/4 3-40, Specification 3.3.3.1, Table 4.3-3, is revised to be consistentwithandincorporatetheap@icablechangesmadeto Table 3.3-6(seeitem76above).

78. Page. 3/4 3-42, in Specification 3.3.3.3, a reference to footnote "# The Seismic Monitoring instrumentation is common to both units but located in Unit I or comon areas" is added.

'~

79. Page 3/4 3-42, Surveillance Requirement 4.3.3.3.2, which applies to seismic monitoring instrumentation follow (ng a seismic event, the time allowed for CHANNEL CALIBRATION in the third line is extended from "5" to "10" days, and the time allowed for submittal of a Special Report in the seventh line is extended for "10" to "14" days.

80. Page 3/4 3-45, in Specification 3.3.3.4, a reference to footnote "# The m

meteorological monitoring instrumentation channels are common to both units", is added.

81. Page 3/4 3-48, in Specification 3.3.3.5, ACTION item a is changed from

"... channels less than required by Table 3.3-9..." to "... channels less than the minimum channels OPERABLE requirement by Table 3.3-9,..."

82. Page 3/4 3-49, Specification 3.3.3.5, Table 3.3-9, delete the

" MEASUREMENT RANGE" column, change Instrument 5 to " Steam Generator Wide Range Water Level", and change Instrument 6 to " Condensate Storage Tank Water Level".

5 e

.r

18

83. Page 3/4 3-50, Surveillance Requirement 4.3.3.5, Table 4.3-6 is revised to incorporate administrative changes that parallel those in Table 3.3-9 (see Item 82 above).

~

84. Page 3/4 3-51, ACTION items a and b of Specification 3.3.36 are changed to indicate that the Reactor Vessel Level Indication System is exempted from their provisions. ACTION item e is redesignated as item g, and ACTION item e, which stipulates the provisions that apply to the Reactor VesselLevelIqdi5ationSystem,andACTIONitemf,statingthatACTION item e applies onig to the first cycle, are added, and replace

" containment sump" with " containment recirculation sump" in ACTION

~

items b and c.

-4

. h.85. Page 3/4 3-52, Specification 3.3.3.6, Table 3.3-10 entries 9 and 10 are, changed to "9.

Containment Reactor Cavity Sump Level (3) - Wide Range" and "10 Containment Recirculation Sump Level (1) - Narrow Range", respectively, and a new entry added "20.

Reactor Vessel Level Indication System" with the REQUIRED NUMBER OF CHANNELS as 2 and the MINIMUM NUMBER OF CHANNELS OPERABLE as 1.

86. Pace 3/4 3-53, in Table 4.3-7 entries 9 and 10 are changed to "9.

Containment Reactor Cavity Sump Level - Wide Range", respectively, and a new entry "20.

Reactor Vessel Level Indication S.ystem" with "M" (monthly) channel chegk and "R" (every 18 months) channel calibration is added.

.3

.i

19

87. Page 3/4 3-54, in Specification 3.3.3.7, add a reference to footnote "#

The Chlorine Detection System is common to both units installed in the norral intakes to the Control Room Ventilation Systen".

=

~

88. Papp 3/4 3-55, in Specification 3.3.3.8 delete ACTION item a.?, ACTION item a.1 becomes part of the introductory statement to ACTION a, and ACTION iten a.3 is redesignated as ACTION item c.

89. Page 3/4 3-57 and 3/4 3-58, Table 3.3-11, Fire Detection Instruments.

Panel B. Zone 6 date is changed to "6.

Fire Pump Area (5) 1 N.A.

Unit ? Auxiliary Puilding Supply Fan Room 1

N.A.

Control Room Ventilation Equipment Room 1

N.A.";

the first item in Zone 16(1) is changed to " Unit 1 Auxiliary Buildirg

..., and note "(5) The Fire Pumps and Diesel Generator No. 3 are common to both units. Located on the Unit I side and on the Unit 1 Fire Detection Instrunent Penel only" is added.

90. Pages 3/4 3-65 and 3/4 3-66, Specification 3.3.3.10, in Table 3.3-13, the reference under the APPLICABILITY colunn fer the Noble Gas Activity Monitor in entry 5 is charged to "*** Modes 1-4, also Mode 6 during CORE ALTERATIONS or movement of irradiated fuel tritbin containment," and the Instrunent designation "(RM-1dA and 14B)" is changed to "(RM-14A or 148)."

't

20 91.

Page 3/4 3-67 and 3/4 3-68, Surveillance Requirement 4.3.3.10, in

~

Table 4.3-9, the reference under the MODES FOR WHICH SURVEILLANCE REQUIRED column for the Noble Gas Activity Monitor in entry 5'is changed r

to "*** Modes 1-4, also Mode 6 during CORE ALTERATIONS or movement of

~

irradiated f'uel within containment", and the Instrument designation

"(RM-14Aand14B)"ischangedto"(RM-14Aor14B)".

92. Page 3/4 3-69, in Specification 3.3.4.1, lines 3 through 7 under ACTION a

~~

are changed 'to "... steam line inoperable, restore the inoperable

~

valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or isolate the turbine from

~;

the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ".

J

93. Page 3/4 3-69, in Specification 3.3.4.1, changes lines 2 and 3 of ACTION b to "... within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply".

94. Page 3/4 4-1, in Specification 3.4.1., delete the reference to the footnote in the APPLICABILITY section and the footnote, and change the ACTION statement to "With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ".

95. Page 3/4 4-2, in Specification 3.4.1.2 delete the reference to footnote

"**" in the APPLICABILITY section and the footnote.

[

./

a s---1---

21

96. Page 3/4 4-3, in Specification 3.4.1.3, modify the introductory

~

statement a to "At least two of the loops / trains listed below shall be OPERABLE and at least one of these loops / trains shall be in operation *",

delete item b, reverse the order of the footnotes, and in ACTION items a and b, rep a~ce "RC loops and/or RHR trains" by " loops / trains".

97. Page 3/4 4-4, change the first two lines of Surveillance Requirements 4.4.1.3.1 to "... pump (s) and/or RHR pumps, if not in operation, shall'he determined OPERABLE once..."

\\

98. Page 3/4 4-4, the second line of Surveillance Requirement 4.4.1.3.2 is changed to "... secondary side water level to be..."

99. Page 3/4 4-5, in Specification 3.4.1.4.1., ACTION a is changed to "With one of the RHR trains inoperable and with less than the required steam generator water level, immediately initiate corrective action to return the inoperable RHR train to OPERABLE status or restore the required steam generator water level as soon as possible."

100. Page 3/4 4-5, delete Surveillance Requirements 4.4.1.4.1.1 and renumber the following two Surveillance Requirements.

101. Page 3/4 4-6, delete Surveillance Requirement 4.4.1.4.2.1 and renumber the remainingSgrve111anceRequirement.

.5 l

22 102. Page 3/4 4-7, in Specification 3.4.2.1, change the last two lines of the ACTION statement from "... and place an OPERABLE residual heat removal train into operation in the shutdown cooling mode." to "... and place a residual heat removal train into operation".

103. Page 3/4 4-10, in Specification 3.4.4, delete "and remove power from the block valve (s);" in the third line of ACTION a.

104. Page 3/4 4-10, the last two lines of Surveillance Requirement 4.4.4.2 are i

changed to "... the block valve is closed in order to meet the requirement of ACTION a, of Specification 3.4.4.".

105. Page 3/4 4-13, in Surveillance Requirement 4.4.5.3c.1) replace " Primary" L

with " Reactor".

[

106. Page 3/4 4-15, change lines 2, 3, and 4 of Surveillance i

Requirement 4.4.5.5c. to "... Category C-3 shall be reported in a Special

,.r Report pursuant to Specification 6.9.2 within 30 days prior to resumption of operation. This report shall provide...".

A 107. Page 3/4 4-17, Surveillance Requirement 4.4.5, Table 4.4-2, the reporting requirements when the results of a first and second sample steam generator tube inspection fall in Category C-3, are changed to

" Notification to NRC pursuant to 50.72(b)(2) to 10 CFR Part 50."

i,

23 108. Page 3/4 4-18, in Specification 3.4.6.lb, replace " containment sump

~

level" with " Containment Structure Sumps and the Reactor Cavity Sump Level".

~

109. Page 3/4 4-18, in Surveillance Requirement 4.4.6.lb, replace " containment sump level" with " Containment Structure Sumps and the Reactor Cavity Sump Level".

110. Page 3/4 4-19, cKange the second line of Specification 3.4.6.2e to

\\

"2235

20 psig, and ".

111. Page 3/4 4-20, in the third line in Surveillance Requirement 4.4.6.2.lc change the RCS pressure to "2235

20 psig".

a 112. Page 3/4 4-25, in Specification 3.4.8b, ACTION, Modes 1, 2, and 3 item c.,

2:

and third line of ACTION, : lodes 1, 2, 3, 4, 5, item a., insert "of gross radioactivity" after "microcuries/ gram".

s 113. Page 3/4 4-25, in Specification 3.4.8, ACTION a. that applies only during MODES 1, 2, and 3 is divided into two ACTION items, a. and b., with no change in their provisions, and ACTION items b. and c. are redesignated

c. and d., respectively.

4 F

.3 l

.f i

I 7

-,,-_-.,e--.

24 114. Pages 3/4 4-25 and 3/4 4-26, the second sentence in the introductory statement to the ACTION item a., which applies during MODES 1, 2, 3, 4,

~

and 5, is replaced with "For this ACTION statement, prepare 4-Special Report to the Commission pursuant to Specification 6.9.2 with n 30 days with a copy to the Director, Nuclear Reactor Regulation, Attention:

Chief, Core Performance Branch, and Chief, Accident Analysis Branch, U.S.

Nuclear Regulatory Commission, Washington, D.C.,

20555.". The word

~

"first" is deleted from item 1 under the same ACTION item a, and item 2 is replaced with "2.-+ Results of a) the last isotopic analysis for radionuclides performed prior to A

exceeding the limit.

b) analysis while limit was exceeded, and

~*

c) one analysis after the radiofodine activity was reduced to less than the limit including each isotopic analysis, and the date-and time of sampling, and the radiciodine concentrations;"

115. Page 3/4 4-27, Specification 4.4.8, Table 4.4-4, add reference to footnote

"**" in entry 1. and add footnote "**" which provides detailed guidance on accepted methodology to determine " gross radioactivity"; and add i

reference to footnote "***" in entry 3. and add footnote "**" which provides detailed guidance on methodology to determine the " average disintegration energy".

I e

i 9

I Pe M

+

25 116. Pages 3/4 4-29, 3/4 4-30 and 3/4 4-31, add "and the setpoint of Technical Specification 3.4.9.3a" at the end of' Surveillance Requirement 4.4.9.1.2, and change the period for the material curves in Figures 3.4-2 and 3.4-3, Specification 3.4.9.1, to "6 EFPY."

117. Page 3/4 4-?2, Table 4.4-5, insert " Unit 1" under the title, and add tha Unit 2 reactor vessel material surveillance withdrawal schedule to make the table applicable to both units.

-n i

118. Page 3/4 4-34, in Specification 3.4.9.3, delete existing item 1, and combine the existing items b and c to create a new item a.

To correspond to the above change, delete ACTION item a and redesignate the letters of the following ACTION items. These changes are made to conform with NRC requirements as described in Diablo Canyon SSER-21.

119. Page 3/4 4-35, delete items d and e in Surveillance Requirement 4.4.9.3.1.

120. Page 3/4 5-1, in Specification 3.5.1 change items a and c to "The isolation valve open, and power removed," and "A boron concentration of between 1900 and 2200 ppm, and", respectively; and change the last two lines of ACTION item b to "... or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ."

121. Page 3/4 5-2, in Surveillance Requirement 4.5.1.1c replace the RCS pressure with "1000 psig", and delete Surveillance Requirement 4.5.1.1d.

=

/

26 122. Page 3/4 5-8, in Surveillance Requirement 4.5.3.1 insert " Surveillance" between " applicable" and " requirements".

123. Page 3/4 5-8 in the second line of Surveillance Requirement 4'.5.3.2 replace " required" with " allowed," and delete "per Specifica' tion 4.0.5" in the footnote.

124. Page 3/4 5-9, change item b of Specification 3.5.4.1 to "A boron concentration of between 20,000 and 22,500 ppm, and".

i 125. Page 3/4 5-11, in Specification 3.5.5, the OPERABILITY requirements on I

the RWST, and the ACTION statement are editorially modified without u

changing the applicable provisions.

y p.

126. Pages 3/4 6-1, 3/4 6-7, and 3/4 6-8, in Technical Specification 3/4.6.1.1 replace " primary containment" with " containment".

r, I?.

127. Page 3/4 6-1, change Surveillance Requirement 4.6.1.lb to "By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and".

i 128. Page 3/4 6-2, in Specification 3.6.1.2, add "as applicable " at the end of itema.1)anddelete"(a)"and"(b)with"inACTIONstatement.

t 4

t i

1 i

... ~.

27 129. Page 3/4 6-3, in Surveillance Requirement 4.6.1.2, insert "as applicable,"

after "0.75L " in lines 1, 4 and 7 of item b, and replace the second and t

third lines of item c.1) of Surveillance Requirement 4.6.1.2.with

... supplemental test results L, minus the sum of the Type k and the c

superimposed leak, L, is equal to or less than 0.25 L,, or 0.25 L. as o

t applicable."; and change item c.3) to " Requires that the rate at which gas is injected into the containment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L,, or 0.75 Lt and 1.25 L

as applicable."

t

\\

130. Page 3/4 6-4, replace "per" with "by the requirements of" in item e to Surveillance Requirement 4.6.1.2, 131. Page 3/4 6-6, the second footnote in Surveillance Requirement 4.6.1.3 is changed to "** This represents an exemption to Appendix J. Paragraph III.D.2 of 10 CFR Part 50."

.p 132. Page 3/4 6-7 Specification 3.6.1.4, replace the statement " Primary containment internal pressure shall be maintained between -3.5 and +0.3 psig." with " Containment internal pressure shall be maintained between

-1.0 and +0.3 psig."

133. Page 3/4 6-9, the third line in Surveillance Requirement 4.6.1.6.2 is changed to "... Commission in a Special Report pursuant to Specification 6.9.2withid'15 days. This report shall include a..."

./

28 134. Page 3/4 6-11, in Items C.1) and C.2) of Surveillance Requirement 4.6.2.1,

" Containment isolation phase "B" is replaced with " Phase "B"_ Isolation".

~

135. Page 3/4 6-15, delete " containment" from the first line in i ems a and b

~

of Surveillance Req'uirement 4.6.3.2, and insert "its isolation" between "to" and " position" in the second line of item b.

136. Pages 3/4 6-19, 3/4 6-20, and 3/4 6-21, Specification 3.6.3, in Table 3.6-1, delete the'"1" for all manual valves showing a Unit I designation,

\\

to make the table applicable to both units. On page 3/4 6-20, delete the e-D from Valve RCS-512 and change the Function to Isolating Valve FI-927 OC.

~

137. Page 3/4 6-24 Specification 3.6.3, Table 3.6-1, replace the last 16 entries with Diablo Canyon plant specific valve designations, add " Unit I

^

only" to valve FP-180, and add valve "VAC-252 FP-867 Containment Fire Water IC-Unit 2 only."

138. Page 3/4 6-26, delete " containment" from the first line of Specification 3.6.4.2.

139. Page 3/4 7-1, the last line of ACTION item a in Specifications 3.7.1.1 is changed to "and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ."

t 140. Page 3/4 7-2, Specification 3.7.1.1, for each entry in Table 3.7-1 add a i.

reference to a new footnote "* Unless the Reactor Trip system breakers are in the open position."

._3

29 141. Page 3/4 7-6, Specificatirn 3.7.1.3, footnote "*", which applies to PODE 3 in the APPLICABILITY section is deleted.

142. Page 3/d 7-P, Surveillance Requirement 4.7.1.4 Table 4.7-1 5s revised to incorporate administrative changes.

143. Page 3/4 7-9 in the ACTION for Specification 3.7.1.5, the end of the statement for PODE 1 is changed to "... within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHt!TDOWN within the

~

following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ."; and the ACTION statement for MODES 2 and 3 is changed M

editorially and elminates the exemption from the requirements of Specification 3.0.4, when the plant is in MODE 2 or 3 and the MSIV becomes L

d' inoperable.

144. Page 3/4 7 8, insert "The provisions of Specification 4.0.4 are not applicable for entry into MODE 3." at the end of Surveillance Pequirement 4.7.1.5.

145. Pace 3/4 7-11, replace " containment isolation phase "B" with " Phase "P" Isolation" in item b of Surveillance Requinnent 4.7.3.1.

146. Page 3/4 7-13, in Specification 3.7.5.1 add a reference to footnote ""he control Room Ventilation System is conron to both units" after "Syster" in the first line, and in the existing footnote replace "on the plant site"atthe'endoftheparagraphwith"withintheSITEBOUNDAP.Y."

s b

30 4

147. Pages 3/4 7-14 and 3/4 7-15, in Surveillance Requirements 4.7.5.lc.3, 4.7.5.le.4, 4.7.5.lf, and 4.7.5.lg, which apply to the Control Room Ventilation System; page 3/4 7-17, in Surveillance Requirements 4.7.5.Ib.4, 4.7.6.1d.3, 4.7.6.le, 4.7.6.lf, which apply to th~s Auxiliary Building Safeguards ~ Air Filtration System; pages 3/4 9-14 and 3/5 9-15, in Surveillance Requirements 4.9.12b.4, 4.9.12e and 4.9.12f which apply to the Fuel Handling Ventilation System; on pages B 3/4 7-13, which provides the basis to support Specifications 3.4.7.5 and 3.4.7.6; and B 3/4 9-3, which provides the basis for Specification 3/4.9.12 change the applicable standardsfrom"AN{IStandardN510-1975" to " ANSI Standard N510-1980."

148. Page 3/4 7-26, ACTION items a and b in Specification 3.7.9.1 are changed to remove the requirements to submit Special Reports pursuant to

~~

Specification 6.9.2 when portions of the Fire Suppression Water System are e

inoperable.

149. Page 3/4 7-27 Surveillance Requirement 4.7.9.1, add reference in item c t.

to footnote: *Except valves which are located inside the containment and I

are locked, sealed, or otherwise secured in position. These valves shall be verified in the correct position during each COLD SHUTDOWN except such l

verification need not be performed more often than once per 92 days.",

1 l

after " valve" in the first line, and item d is changed to "At least once l

l per 6 months by performance of a system flush of the outside distribution -

l loop to verify no flow blockage."

\\

i, i

J 7

t

c--

m,m--..m,_..

. ~,. -._..-

m..

v.

___-y,

-.v

-m--,

.-yw v.

-.~,w.,

31 150. Page 3/4 7-78, in Specification 3.7.9.2, delete reference to pumps "2 and 3" in item e, and insert the f611owing two editional Spray and/or Sprick'er systen:

"f.

Centrifugal Charging Pump Area, and" "h.

Contaiorent Penetration Area."

~

1,51. Pages 3/4 7-28, 3/4 7-30, 3/4 7-32, 3/4 7-33 and 3/4 7-36, in ACTION a to Specifications 3.7.9.2, 3.7.9.3, 3.7.9.4, 3.7.9.5 and 3.7.10, all of which refer to fire pi6tection, delete the requirement for a Special Report

\\

pursuant to Specification 6.9.2 in case diverse portions of the system cannot be restored to OPERABLE status within 14 days.

f 152. Page 3/4 7-31 Table 3.7-3 is replaced by a revised Table 3.7-3 which incorporates the CO systen Unit 2 data.

2 153. Pages 3/4 7-34 and 3/4 7-35, Table 3.7-14 is replaced with a revised Table 3.7-4 which incorporates infonnation on the fire hose stations for

~ ;

Unit 2.

p 154. Page 3/4 7-36, the APPLICABILITY statement in Specification 3.7.10 is changed to "Whenever the equipment protected by the fire barrier penetrations is recuired to be OPERABLE.", to conform to the current NRC position as presented in the April 5, 1984 Regional Appendix R Workshop.

..r

./

32 155. Page 3/4 7-37, Specification 3.7.11 is changed to "3.7.11 the temperature of each area shown in Table 3.7-5 shall not be exceeded for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or by more than 30'F".

~

156. Page 3/4 7-37, in Specification 3.7.11, the format of ACTION' items a and b is changed, and ACTION item a is revised to exempt the licensee from the provisions of Specifications 3.0.3 and 3.0.4 when the temperature limits of Table 3.7-5 are exceeded in one or more areas for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

\\

157. Page 3/4 7-38, revise entry 15 in Table 3.7-5 to indicate that the Diesel Generator No. 3 Room is common to both units.

158. Page 3/4 7-39, in Specification 3.7.12 add a reference to footnote "*The L

UHS is common to both units" after (UHS) in the first line.

159. Page 3/4 7-40, in Specification 3.7.13 add a reference to footnote "*Both breakwaters are common to both units" after "(east and west)" in the first line.

160. Page 3/4 8-1, Specification 3.8.1.1, the footnote is changed to

"*0PERABILITY of the third (common) diesel generator shall include the capability of functioning as a power source for the required Unit upon automatic demand from that Unit" to make it unit nonspecific.

i

.9

.n.

33 161. Page 3/4 8-2, Specification 3.8.1.1, ACTION C, add "If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

=

~

162. Page 3/4 8-3, in footnote "*" to Surveillance Requirement 4.8.1.1.2, replace "for Unit 1" in the second line with "for one Unit" and "for Unit 2" in the fourth line with "for the other Unit" to make it unit nonspecific, and change footnote "***" to Surveillance Requirement 4.8.1.1.2 to "May'be the associated bus in the other Unit if that Unit is i

in Mode 1, 2, 3 or 4".

n 163. Page 3/4 8-7, the second line in Surveillance Requirement 4.8.1.1.4 is changed to "be reported as a Special Report within 30 days to the

(

Commission pursuant to Specification 6.9.2" L

I 164. Page 3/4 8-8, the last sentence in the footnote to the Table 4.8-1 is I

changed to "For the purpose of this schedule, only valid tests conducted after the completion of the preoperational test requirements of 1,,

Regulatory Guide 1.108. Revision 1, August 1977, shall be included in the computation of the "last 100 valid tests".

165. Page 3/4 8-11, in Specification 3.8.1.2, item b.3) is deleted, and item b.2) is changed to "One supply train of the Diesel Fuel Oil Storage and Transfer System with 8000 gallons of fuel in addition to the fuel i

required for the other Unit" to make it unit nonspecific.

/

34 166. Page 3/4 8-11, in Surveillance Requirement 4.8.1.2 the last line is changed to "... for ESF timers, b.6), b.7), b.10) and b.11)."

1

)

=

167. Page 3/4 8-12, Specification 3.8.2.1d, e, f, g, h, i, j, k, 1, m, n, o, which, in reference'to onsite po'wer distribution, describe the electric S

busses that must be energized, delete the "1" imediately following the words " Bank" and " Bus", to make the statements applicable to both units.

168. Page 3/4 8-12, S'pecification 3.8.2.1, at the end of items m, n and o, add "and its associated full capacity charger".

F 169. Page 3/4 8-12a, after " associated Battery Bank" in the first and second

[

lines of ACTION item c of Specification 3.8.2.1 add "and full-capacity a:

charger".

170. Page 3/4 8-13, add "and full-capacity charger" at the end of item c of Specification 3.8.2.2.

171. Page 3/4 8-15, in Surveillance Requirement 4.8.3.1, items b.2) and c.3),

replace "250 micro-ohms" with "150 x 10-6 ohm *" and add the footnote "*

The resistance of cell-to-cell connecting cables does not have to be included."

s 172. Page 3/4 8-Surveillance Requirement 4.8.3.1, Table 4.8-3, in footnote (b) replace "5 amps" with "2 amps".

.I

35 173. Page 3/4 8-15 Surveillance Requirement 4.8.3.1 iten e, which addresses the 60 month surveillance test to verify battery capacity, insert

" required by Specification 4.8.3.1;" after " service test". ~

174. Page 3/4 8.15 Surveillance Requirement 4.8.3.1 iten f, the~first and second lines are changed to "At least once per IP nonths during shutdown by giving performance discherge tests of battery capacity to any battery tha t shows...".

175. PePe 3/4 8-18,I in Surveillance Requirement 4.8.4.1, item 1 replace

" CHANNEL FUNCTIONAL" with " TRIP ACTUATION DEVICE OPERATIONAL".

176. Pages 3/A P-19, 3/4 8-20 and 3/4 8-21 Specification 3.8.4.1 Table 3.8-1, Y

for all components identified by a two-digit designation (e.g. SI purp 11 e

and Accumulator 14), delete the first "1", to make the data in the table ro applicable to both units. Add a footnote

indicating that FCV-601 is

~

corren to both units.

t

[/

177. Pages 3/4 8-22 through 3/4 8-26, a new Specification 3.8.4.2, and corresponding Surveillance Requirement 4.8.4.2, which apply to Containment Penetration Conductor Overcurrent Protective Devices is added.

178. Page 3/4 9-1, Specificetion 3.9.1, delete "With the reactor vessel head closure bolts less than fully tensioned or rith the head removed," in the introductory statement.

a J

--,----,.-_....-c..---

r.--m.,,-

36 179. Page 3/4 P-P, Surveillance Requirements 4.9.2 items b and c are changed to "An ANALOG CHANNEL OPERATIONAL TEST...".

~

180. Page 3/4 9-6, Surveillance Requirements 4.9.6.1 and 4.9.6.2, which apply to the manipul,ator' crane and au'xiliary hoist durirg refueling operations, respectively, in the third line of each replace "to the start of such operations" with "to removal of the reactor vessel head".

'181. Page 3/4 9-7, Specification 3.9.7, delete the reference to footnote "**"

\\

and the footnote.3, 182. Page 3/4 9-7, Specification 3.9.7, the existing ACTION becomes ACTION

.g item "a", and a new ACTION item b is added as "b".

The provisions of m.

Specification 3.0.3 and 3.0.4 are not applicable.

[

183. Page 3/4 9-8, delete Surveillance Pequirement 4.9.8.1.1 "The required RHR g

trains shall be demonstrated OPERABLE pursuant to Specification 4.0.5" a

h and renumber the next surveillance requirement to "4.9.8.1".

184. Page 3/4 9-9 Specification 3.9.8.7, add a reference to footnote "*" at the end of the statement, add a nev footnote "*" Prior to initial criticality, the RHR train may be reroved from operation for up to I hour per 8-hour period during performerce of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs".

i

.)

l 9

l-

_, _. - - _. ~...

37 185. Page 3/4 9-9, change Surveillance Requirement 4.9.8.2 to "At least one RHR loop shall be verified in oper6 tion and circulating reactor coolant at a flow rate greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ."

186. Page 3/4 9-10, Specification 3.9'.9, the existing ACTION becomes ACTION item a and "The provisions of Specification 3.0.4 are not applicable" in the last sentence is deleted, and a new ACTION item b, "b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable" is added.

187. Page 3/4 9-11, in Specification 3.9.10, change the APPLICABILITY statement to "During movement of fuel assemblies or control rods within

~

the containment when either the fuel assemblies being moved or the fuel assemblies seated within the reactor vessel are irradiated while in MODE 6."

eI 188. Page 3/4 9-11, in Surveillance Requiremenmt 4.9.10 delete "within the reactor vessel" at the end of the requirement.

T 189. Page 3/4 9-12, in Specification 3.9.11, the existing ACTION becomes ACTION item a and "above" is inserted before " specification" in the first line, and a new ACTION ftem b "b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable." is added.

't i,

e

.1 4

,,w,--o

~

,w-~

,. an n, -,, ee re v-e. e s-e., + <

.2.sw ev, _ -,

38 l

190. Page 3/4 9-13. Specification 3.9.1?, ACTION item c is charged te "The provisions of Specifications 3.0.3 and 3.0.4 are not applicable."

3 191. Page 3/4 9-16 Specification 3.9.13 is changed to "No spent fuel shipping cask bandling operation near the spent fuel pool (i.e. any movement of a cask located north of column line 12.9 for Unit 1 or snuth of column line 23.1 for Unit 2) shall be performed unless spent fuel in all locations in Racks 5 and 6 has decayed for at least 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months since shutdown."

i 192. Page 3/4 10-1, in Surveillance Requirernents 4.10.1.1 and 4.10.1.2, add

" control" between " full-length" and " rod".

g I

193. Page 3/4 10-2, editorial chenges in Surveillance Requirements 4.10.2.1 and 4.10.2.2 are made.

C 194. Page 3/410-3, in Surveillance Requirement 4.10.3.2 replace "a CHAFFEL r

FUNCTIONALTEST"with"enANALOGCHANNELOPERATIONALTEST".

195. Page 3/4 10-4, Technical Specification 3/4.10.4, which addresses Special Test Exceptions for RCS loops during natural circulation tests is deleted.

196. Page 3/4 10-5, Specification 3.10.5, item a is incorporated into the introductory etetenent, item b and the applicable footnote are deleted; add "and during surveillance of digital position indication for as

39 OPERABILITY" to the APPLICABILITY, and, to account for the deletion of Technical Specification 3/4.10.4 (see 195 above), redesignate this Specification to 3.10.4, and the corresponding Surveillance Requirements to 4.10.4.

197. Page B 3/4 0-1, add to the introductory paragraph "In the event of a disagreement between the requirements in these Technical Specifications and those stated in the applicable FEDERAL REGULATION or ACT, the requirements stayed in the applicable FEDERAL REGULATION or ACT shall take precedence and shall be met except where a specific exemption to the Regulation has been granted in the Technical Specifications or Facility License."

y.

198. Page B 3/4 0-1, in Bases for Specification 3.0.3, information is added to

_ provide additional guidance to understand how to consider the time alloted in ACTION statements to initiate and complete a reduction in Operational Modes, particularly for those circumstances not specifically provided for in ACTIONS.

c 199. Page B 3/4 0-1, a new Bases to support the addition of Specification 3.0.5, "3.0.5 This specification delineated the applicability of each specification to Unit 1 and Unit 2 operation." is added.

200. Page B 3/4 0-2, in Bases for Surveillance Requirement 4.0.3, a e

clarification of how inoperability can be determined, and the timing of surveillancerequirements,andthecorrespondingACTIONstathments,is a,dded.

.I

do Pol. Page B 3/4 0-3, a new Bases to support the addition 'f Specification 4.0.6:

"4.0.6 This specification delineates the applicability of the surveillance activities to Unit I and Unit 2 operations." is added.

~

702. Page B 3/4 1-?, in the Bases for Specification 3/4.1.1.4, delete iter (3)

"the P-12 interlock is above its setpoint", and renumber subsequent items.

203. Page B 3/41-2, in the Bases for Specification 3/4.1.2, irsert " Boron" ahead of In,iectron System" in the first line of the third paragraph.

\\

204, Page P 3/4 1-3, in Bases for Specification 3/4.1.3, add to the first I

oaragraph, " Group Demand position can be detemined from 1) the group step counters, 2') the plant computer, or 3) for control rods, ard P to A Converter at the rod control cabinet."

2 205. Page B 3/4 2-4, correct a typographical error in the Bases for i.

y Specifications 3/4.2.2 and 3/4.2.3, Item 1., and by changing " 113 steps" A!

h to read " 112 steps."

n.

206. Pace B 3/4 P-4, in Bases for Specifications 3/4.2.2 and 3/4.2.3, which support hot channel factor limits, in the bottom paragraph:

replace "R "

y by "R" in the first line, and delete "R as defined, allows for the 2

inclusion of a penalty for Rod Bow on DNBR Only." in liver 5 and 6.

1, l

~

me=mF

.]

41 207. Page B 3/4 2-5, in the Bases for Specifications 3/4.2.2 and 3/4.2.3, change the existing paragraph to " Fuel rod bowing reduces the value of DNB l

ratio. Credit is available to offset this reduction in the generic margin. The generic margin totaling 9.1% DNBR is derived from the l

l difference between the design and required values on the following items; (a) design DNBR limit, (b) grid spacing multiplier, (c) themal diffusion l

coefficient, (d) DNBR spacer factor multiplier and (e) pitch reduction.

l l

The rod bow penalty is calculated with the method described in WCAP-8691, Revision 1, and Ts completely compensated by the available margin of 9.1%", and replace " Specification 6.9.1.14" in the bottom paragraph with

" Specification 6.9.1.8."

208. Page B 3/4 2-6, in the Bases for Specification 3/4.2.4 delete "A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F is g

depleted." in the second paragraph.

209. Page B 3/4 3-1, in the Bases for Specification 3/4.3.1 and 3/4.3.2 delete item (12) at the end of the third paragraph.

210. Page B 3/4 3-3, in the Bases for Specification 3/4.3.3.3 change the last two lines to ".... pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent with the recomendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes," April 1974."

i.

./

T M selslnTM M M' M M' M 'A

42 211. Page B 3/4 3-3, in the Pases for Specification 3/4.3.3.6, replace the last two lines with "...is consistent with the recomendations of

~

Regulatory Guide 1.97, Revision 3 " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983, and NUPEG-0737, " Clarification of TMI Action Plan," November 19P0."

212. Page B 3/4 4-2, in the Bases for Specification 3/4.4.2, add "In addition, the Overpressure Protection System (relief valves) provides a diverse a

means of protectien against RCS overpressurization at low temperatures."

at the end of the top paragraph.

M

.,213. Page B 3/4 4-3, in the Pases for Specification 3/4.4.5, in the bottom paragraph, change the reporting requirements to "... these results will f,

be reported to the Commission as a Special Report pursuant to Specification 6.9.2 prior to..."

f; 214. Page B 3/4 4-4, the Bases for Specification 3/4.4.6.2, Operational Leakage, are modified adrninstratively and two paragraphs at the end are inserted addressing the importance of leakage through the RCS pressure isolation valves, as part of IDENTIFIED LEAKAGE.

215. Page P 2/4 4-5 and B 3/4 4-6, the Bases for Specification 3/4.4.8 are modified administratively, and two new paragraphs are inserted before the last paragraph to explain the reasons for excluding radiofodines from the

.J I

l j

43 determination of gross specific activity and the average disintegration energy, and the allowable time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months between sample and comp,leting the initial analysis.

216. Pages B 3/4'4-6 to B 3/4 4-11, the Bases for Specification 3/4.4.9 is revised administrative 1y; " Unit 1" is added to the Title of Table B 3/4 4-la to accomodate introducing Table B 3/4 4-Ib, which is the equivalent table for Unit 2; deleting Tables B 3/4.4-Ic, B 3/4.4-Id and B 3/4.4-2, which are not referred to in the text; and adding a new Figure B 3/4.4-2.

i 217. Page B 3/4 4-12, in the Bases for Specification 3/4.4.9, replace the second paragraph with "The fracture toughness testing of the ferritic materials in the reactor vessel were perfonned in accordance with the 1966 Edition for Unit 1, and 1968 Edition for Unit 2, of the ASME Boiler and Pressure Vessel Code,Section III. These properties are then

.~

evaluated in accordance with the NRC Standard Review Plan,".

In the third paragraph, change the third line to ".. 6 effective full power years of service life. The 6 EFPY service...". In the fourth paragraph,

[',

change the second line to "... are shown in Table B 3/4.4-la for Unit 1 and Table B 3/4.4-1b for Unit 2 Reactor..." In line 5, replace "and copper content" with " copper and phosphorous content," and in lines 6, 7 and 8. replace the reference with "The largest value of Delta RT computed NDT by either the Regulatory Guide 1.99 Trend Curves from the Regulatory Guide 1.99, Revision 1, " Effects of Residual Elements on 4

I e

e 1

44 Predicted Radiation Damage to Reactor Vessel Materials: or the Westinghouse Copper Trend Curves shown by Figure B 3/4.4.2.", In the last line of this paragraph also change "4.5 EFPY" to "6 EFPY" as the limiting service life for Delta RT determination.

In the last paragraph, insert NDT a sentence defining the " lead factor" as it applies to the reactor vessel material surveillance program.

218. Page B 3/4 4-13 and B 3/4 4-16, in the Bases for Specification 3/4.4.9, delete the refer'e'nce to "WCAP-7924A" in the top paragraph of page B 3/4

\\

4-13, and delete the top paragraph, and insert a new section to support the provisions used for " low temperature overpressure protection" on page B 3/4 4-16.

d'. '

[

219. Page B 3/4 5-2, in the Bases for Specifications 3/4.5.2 and 3/4.5.3, the top and next two paragraphs are reversed.

220. Page B 3/4 6-1, editiorial changes are made in the Bases for Specification 3/4.6.1, and the Bases for Specification 3/4.6.1.4 is changed to "The maximum peak pressure expected to be obtained from a LOCA event is 46.91 psig. This includes the limit of 0.3 psig for initial positive containment pressure. The total pressure is less than design pressure and is consistent with the safety analysis."

f

~

..- t

.f

45 4

221. Page B 3/4 6-7, chance the containment maximum pressure in the Bases for Specification 3/4.6.1.6 to "46.91 psig."

222. Page B 3/4 6-3, update the reference to Reculatory Guide 1.7 to " control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant-Accident". Revision 7, November 1978."

223. Page B 3/4 7-2, perform the following administrative changes: Bases for Specification 3/4.7.1.2, in the second paragraph, line 1, insert " motor" after " electric"; Bases for Specification 3/4.7.1.4, in line 1, insert

" coolant" after " secondary", replace " limits" in line 3 by " dose guideline values," " primary" by " reactor" in line 4, and " accident" by

" safety" in the last line.

224. Page B 3/4 7-3, in the Bases for Specification 3/4.7.4 replace " accident conditions within acceptable Ifmits." with " safety analysis."

i.

225. Page B 3/4 7-6, in the Peses for Specification 3/4.7.8, replace the reference to "10 CFR 70.39(c)" in the second line with "10 CFR 3

j 70.39(a)(3)."

226. Page B 3/4 7-7, Bases for Specification 3/4.7.9, which addresses OPERABILITY requirements for fire suppression systen.!, delete the last i

sentence, "The requirement for a twenty-four hour report to.the s

e m

46 l

Comission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire protection capability for the continued operation of the nuclear plant."

~

227. Page B 3/4 8-1, under Bases 3/4.8.1, 3/4.8.2, and 3/4.8.3, reword the information on Third Diesel Generator testing to make it unit nonspecific by changing from "... from Unit 2 is maintained during surveillance testing on Unit 1, then the third (comon) Diesel Generator Unit shall be

~

considered to be DPERABLE for Unit 2." to "... from one Unit is V

\\

maintained during surveillance testing on the other Unit, then the third (comon) Diesel Generator Unit shall be considered to be OPERABLE for v.

that Unit."

e

}.

228. Page B 3/4 8-2, in the Bases for 3/4 8.4, additional infonnation is provided to support the provisions added to protect containment electrical penetrations and penetration conductors, and the Surveillance 2

Requirements applicable to lower voltage circuit breakers.

229. Page B 3/4 9-1, at the end of the Bases for Specification 3/4.9.1.,

(

replace " accident analysis" with " safety analysis".

230. Page B 3/5 9-2, in the Bases for Specification 3/4.9.7, replace " SPENT l

FUEL STORAGE" in the title by " FUEL HANDLING".

l 1

231. Page b 3/4 9-3, at the end of the Bases for Specification 3/4.9.13 add l

"the location of Racks 5 and 6 is shown in Figure 9.1-2 of..the FSAR."

'e e

47 232. Page B 3/4 10-1, the Bases for Specification 3/4.10.4 is deleted.

233. Page 5-1, delete "The Reactor" and " building" from the first,*line in Specification 5.2.2.

234. Page 5-5, replace Specification 5.4.2 with "The total water and steam volume of the reactor coolant system is "12,811 1 100 cubic feet at a 0

nominal T,yg of 576 F for Unit I and 12,903 i 100 cubic feet at a nominal 0

~

T,yg of 577 F or" Unit 2."

235. Pages 6-1 through 6-25, replace " unit" with " plant" throughout

~

Specification 6.0, Administrative Controls, and on pages 6-6 and 6-8

^

delete the heading " AUTHORITY".

O 236. Pages 6-2. Specification 6.2.1, Figure 6.2-1, Offsite Organization, replace "on site" by " plant," delete the position of " Manager, Nuclear Plant Operations"; " Technical Assistant to Vice President, Nuclear Power Generation", and " Quality Assurance Engineer," become " Manager, Nuclear Operations Support" and " Director. Quality Support," respectively.

Figure 6.2.2 Plant Organization, replace " Technical Assistant to Vice President" and " Quality Assurance Engineers" with " Manager, Nuclear Operations Support" and " Director, Quality Support", respectively.

237. Page 6-5, in Specification 6.2.3.1, insert the statemer)t in Specific.ation 6.2.3.4: "The OSRG shall make detailed recon endations for n

revisedprocedures,equipmentmodifications,maintenanceactkvities.

./

r H

-w m

e w w eews-,

r+-e

+

--*e--ave-a2 m hers er*" * " "

-e

'=

- - * = ^r*

u'""""m'-*"RW'a+-+C wa.-

1 48 l

operations activities or other means of improving plant safety to the Manager, Nuclear Operations Support.", which is deleted from its original location as Section 6.2.3.4 on page 6-6.

=

238. Page 6-6, Specification 6.3.1 is' redesignated "6.3", revised editorially, and the minimum qualifications for licensed operator and senior operators are introduced.

239. Page 6-6, delete"* identified by the OSRG" at the end of Specification

\\

6.4.1.

jg 240. Page 6-7, Specification 6.5.1.6, replace " Manager of Nuclear Plant

-4 Operations" with "Vice-President, Nuclear Power Generation" in item c,

. a.

and item f with " Review of all REPORTABLE EVENTS".

t 241. Page 6-8 in Specification 6.5.1.8, replace " Manager of Nuclear Plant Operations" with "Vice-President Nuclear Power Generation", and delete o

" Chairman of".

242. Page 6-9, add to Specification 6.5.2.1, "The GONPRAC shall report to and advise the Executive Vice President, Facilities and Electric Resources Development, on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8." at the end, and delete it from its original location as entry 6.5.2.9.

4 243.Page6-9,inSpecification6.5.2.2,whichliststhecompositkonof GONPRAC, replace"ProjectManager,DiabloCanyon"with" Manager, Nuclear Engineering and Construction Services," replace " Technical I

49 Assistant to the Vice President, Nuclear Power Generation" with

" Director, fiuclear Adminsitration and Support Services," replace "Planager, fluclear Plant Operations" with " Assistant to the Vice President, Nuclear Powcr Generation," add " Manager, Nuclear Operations Support," and " Director, Nuclear Regulatory Affairs," as niembers of GONPRAC to reflect organizational changes and delete the footnote.

~

244. Page 6-10 in Specifir,ation 6.5.2.7, change item g. to "All REPORTABLE EVENTS", and replace item 1. with " Reports end meeting minutes of the Plant Staff Review Comittee and the Onsite Safety Review Group."

q 245. Page 6-12. Specification 6.6, in the title "0CCURREllCE" is replaced with

" EVENT" and the specification is revised to incorprate the REPORTABLE s

EVENT requirements and clarify the role of the PSRC and GONPRAC, and f

reflect organization charges.

g k-g 246. Page 6-12. Specification 6.7, is modified to reflect organization changes and administrative changes to be taken when safety limits are violated.

[

247. Page 6-13, chu.se iten,s b through g in Specification 6.8.1 to l.

"b.

The mergency operating procedures inuired to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as sttted in Generic Letter No. 82-33, I

c.

Security plan implementation, d.

Emergency Plan implementation, 4

,/

50 e.

PROCESS CONTROL PROGRAM implementation, f.

ODCP and ERMP implementation, and g.

Quality Assurance Program for eff,1uent and environmental _ monitoring."

248. Page 6-15, in Specification 6.9.1, "AND REPORTABLE OCCURRENCES" is deleted from the title, " Director" is replaced with " Regional Administrator" and " Inspection and Enforcement" with "the NRC."; and the date for submittal of the Annual Reports is changed to March 31 in Specification 6.9.1.4.

1 249. Pages 6-19, 6-20 and 6-21, to reflect new reporting requirements and the r

LER system Specifications 6.9.1.11, 6.9.1.12 and 6.9.1.13 are deleted, and

)'

Specification 6.9.1.14 which is revised administratively, is redesignated as "6.9.1.8."

250. Page 6-22, change item c to "ALL REPORTABLE EVENTS" in Specification 6.10.1.

251. All Technical Specifications are revised to correct typographical errors (e.g., replacing "1" by "1", KV by kv and "GPM" by "gpm" throughout), and conform to updated nomenclature (e.g., replacing " percent" by "%,"

2

" secs" by "s," " square feet" by "ft." use of scientific notation, and spelled out numbers by digits when referring to surveillance time intervals), and notation changes (e.g., replacing i), ii), iii)... by 1),2),3)...inpage3/43-19;a,b,c,d,andeby1,2,3,4,5on I,

page 3/4 7-3 Table 3.7-3; (a), (b) and (c) by (4), (5), and (6) on page

.E

.f

51 b, c,... by 1, 2, 3,

... and 1, 2, 3,... by a, b, c,... on page 3/4 11-2 Table 4.11-1 and page 3/411-9. Table 4.11-2; e, b, c, d, by 1, 2, 3, 4 on page B 3/4 2-4, Cases.for Specifications 3/4.2.2,3/4.2$3, and' floating notationbydecinalnotationonpage3/412-5,Tabit3.12-2hEdpage3/4 12-6 Table 4.12-1).

252. Pages 3-1 through 3-13 and page B 3/4 3-1, revise Section 3/4.3.1, Reactor Trip System Instrumentation, which specifies the surveil-lance test requirements for the Reactor Trip System Instrumentation channels and interlocks and the autonatic trip logic. The changcs incorporate new surveillance requirements as recommended by WCAP-10271.

Specifically, the proposed changes increase the surveillance intervals of the Reactor Trip System and time thet an inoperable Reactor Trip System analog channel may be naintained or bypassed to allow the i

testing of another channel.

253. Page 3/4 3-44 Surveillance Requirement 4.3.3.3.1. Table 4.3-4, L

Seismic Monitoring Instrumentation Surveillance Requirements, add i

the requirement to perform a channel calibration in accordance with Ah51/Aks-2.2-1978 each refueling outage for tbc triaxial peak accel-ographs and the triaxiel response-spectrum recorders.

254. Fase 3/4 3-52, Specification 3.3.3.6, Table 3.3-10. Accident honitor-ing Instrumentation, for the PORV Position Indicator, changc the i.

O ne

S'i l

required number of channels fron 1/ valve to 2/ valve as a requirci.,u.t for backup instrumentation. Add foctnotes to identify indication as one direct, stem-mounted indict. tor per valve and one comon te,nper-ature eler.:ent.

255. Page 3/4 7-1, Sxcification 3.7.1.1, Turbine Cycle Safety Valves, celete Action b., which allows a maximum of 19 main steam line safety valves to be made inoperable in Mode 3 to pemit insitu testing of the OPERABLE's'afety valve.

256. Page 3/4 7-18, Surveillance Requirement 4.7.7.1, Snubber Surveil-lance, change "in lieu of" to "and" in the introductory statement.

thus, requiring each snubber to be demonstrated OPERABLE by perfom-

[

ance of both the augmented inservice program (described subsequently in Surveillance Requirement 4.7.7.1) and the requirements of Speci-fication 4.0.5.

s i

Other changes are ained at obtaining uniformity of fomat throughcut, such as: replacing "see 1..." with "See iten 1,..."

in entries 3a.20, 3c.3) and 6e of Tables 3.3-3, 3.3-4 and 4.3-2; replacing " REPORTABLE OCCUfiREl;CE" with " REPORTABLE EVEhT"; ct.pitalizing the first letter in systerr designations or technical terns (e.g., Reactor Trip Systen, Interlock Setpoints Trip Setpcint, Safety Limits, Low Setpoint, Pressurizer High and Low Water Level, Steum Generator Water Level i.

Low-Low, Auxiliary Feeowater System. Stean/Feedwater Flow Mismatch, Low Flow Trip Setpoint, Underfrequency Trip Setpoint, Seismic, Safet/

Injection, Itoderator Temperature Coefficient, Refueling Water Stcrag

53 Tank, Boric Acid Storage System, Control Rod Drive System, Control Banks, Interlock Trip Setpoint, Engineered Safety Features, High-High Sefpoint.

Alann/ Trip Setpoint, Movable Incore Detection System, Excore Neutfon Flux Detection System, Control Room Ventilation System, Turbine Overspeed Protection System, Containment Atmosphere, Particulate Radioactivity Monitoring System, Containment Fan Cooler Collection Monitoring System, Leakage Detection Systems, Containment Structure Sump Level, Reactor Cavity Sump Level, Residual Heat Removal, Centrifugal Charging, Safety

~

'~

Injection, Containqnt Spray System, Hydrogen Recombiner, Main Steam Line Isolation Valve, Secondary Coolant System, Heat Flux Hot Channel Factor.

Flowrate, Nuclear Enthalpy Rise Hot Channel Factor, Land Use Census, Steam Dump System and Low-Low T,yg); and capitalizing defined tenns K

(e.g.,STARTUP,SITEBOUNDARYandOPERABLE).

1 Additional fonnat modifications include a greater use of abbreviations (e.g., Effective Full Power Days (EFPD) in page 3/41-2, Power Operated Relief Yalve (PORV), Reactor Coolant System (RCS), Moderator Temperature Coefficient (MTC), Refueling Water Storage Tank (RWST), and Axial Flux Difference (AFD); breaking up Table 4.8-2, page 3/4 8-9 and 3/4 8-10, into one table listing ESF Timers (Table 4.8-2a) and one for Auto Transfer Timers (Table 4.8-26) for clarity; modifying table headings (e.g., Tables 3.3-3, 3.3-4, 3.3-5, 3.3-7, 4.3-4, 3.3-8, 4.3-5, 3.3-12, 4.3-8, 3.3-13, 4.3-9, 3.7-1, 3.12-1, 3.12-2 and 4.12-1) for consistency of fonnat, to renumber footnotes to agree with their order in the text (e.g., Table 4.8-3, page 3/4 8-16), and deleting "0" after a decimal point to avoid giving the impression of greater accuracy than is needed (e.g., '1IO

54 changesto1and2.0to1). f.inor editorial changes to make the Technical

~ Specifications applicable to both units (e.g., charging the footnote in all pages to "Diablo Canyon-Units 1 ano 2") are also incorporated Before issuance df the proposed license amendraerit, the Conrission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Cow.ission's regulations.

~

The Connission has uddE a proposed determination that the amendment

\\

request involves no siggificant hazards consideration. Under the Connission's regulations in 10 CFR 50.92, this means that operation of a

the facility in accordance with the proposed amendments would not

-4 (1) involve a significant increase in the probability or consequences of 4

anaccidentpreviouslyevaluated;or(2)createthepossibilityofanew

y..

or different kind of 4ccident from any accident previously evaluated; or (3) involve e significant reduction in a margin of safety.

C 7

As stated above, the Connission proposes to detemine that the proposeo changes do not involve a significant hazards consideration.

In this regard, the v

Comission has provided guidance concerning the applicaticr. of standards for deterrdning whether or not a significant hazards consideration exists by providing certain exac.ples (4C FP. 14870) of amendments considered not likely to involve significant hazards considerations. The exar.1ples include:

(1)Apurelyadministrativechangetotechnicalspecificatict.s; i,

for example, a change to achieve consistency throughout the technical L

specifications, correction of 6n error, or a change in nomenclature;

55 (ii) A chat.ge that constitutes an accittenti limitation,-restrictico, cr control not presently included in the technical specifications; for example, a more stringent surveillance requirement; (iv) A relief granted upon demonstration of acceptabic operation frou an operating rcstriction that 'was imposed bectuse acceptable operation was not ytt der.onstrated. This assumes that the operating restriction and thc 1

critereia to be applied to a request for relief have been establisebd ir.

a prior review and that it is justified in a satisfactory way that the I

criteria have bee ~n me't'i (vi) A change which either may result in sone

\\

incretse to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptabic criteria with respect to the system or component specified in the Standard Review Plan; for exenple, a

((

change resulting from the application of a small refinement of a previously used calculational model or design niethod; (vii) A change to make a license conform to changes in the regulations, where the license change results in very mir.cr changes to facility operations clearly in keeping with the regulations.

The proposed changes to the Technical Specifications are similar to these i

exanples in that they are either adnit.istrative (1), are more restrictive (ii), grant relief upon demonstration of. acceptable operation (iv), are within theStandardReviewPlanacceptancecriteria(vi),orrespondtochangesin regulations (vii). On this basis, Connission proposes that these changes ao not involve significant hazards considerations. The follevirs is c description of how the proposed change items are similer to the exan:ples of 48 h 14070.

(hote:

iteus,areenumeratedthesameasabcvc).

.f

I 56 The proposed changes in the Technical Specifications for the items listed below i

i are for eliminating typographical errors, correcting punctuation., adjusting l

l nomenclature, additional clarification, improving consistency, mi$or changes, and including Unit 2 Specifications as necessary to reflect operation of l

Units 1 and 2.

They are encompassed by the Consission's example (1) of actions not likely to involve significant hazards considerations. The proposed changes are in Items 1, 2, 3, 4, 5, 6, 8, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22, 23, 24, 25, 26, 27, 28, 29, 30, 31, 32, 33, 34,35,36,37,39,)40$41,42,43,44,46,47,48,50,51,52,54,56,57,59,

~

60, 61, 62, 63, 64, 65, 66, 67, 68, 70, 71, 72, 73, 74, 75, 76, 77, 78, 80, 81, 82, 83, 84, 85, 86, 87, 89, 92, 95, 96, 97, 98, 99, 100, 101, 102, 103, 104, f

105, 108, 109, 110, Ill, 112, 113, 115, 117, 120, 122, 123, 124, 125, 126, 127,

[

130, 131, 134, 135, 136, 137, 138, 139, 140, 142, 143, 144, 145, 146, 147, 149, 150, 152, 153, 155, 156, 157, 158, 159, 160, 162, 164, 165, 166, 167, 171, 173, 175, 176, 178, 179, 180, 181, 182, 183, 186, 187, 188, 189, 190, 3

191, 192, 193. 194, 196, 197, 190, 199, 200, 201, 202, 203, 204, 205, 207, 209, 212, 214, 215, 216, 217, 218, 219, 220, 221, 222, 223, 224, 227, 229, 230, 231, V

232, 233, 234, 235, 236, 237, 238, 239, 241, 242, 243, 244, 245, 246, 247, 248, 249, and 251.

Proposed changes 45, 49, 65, 69, 73, 74, 76, 93, 116, 120, 121, 132, 139, 141, 143, 161, 164, 168, 169, 170, 172, 177, 185, 195, 208, 228, 238, 253, 254, 255, and 256 introduce additional operational controls and restrictions, surveillance testing and verification requirements, and more restrictive ACTION items than those presently included in the Technical Specifications. These proposed changes are thus similar to example (ii) of 48 FR 14870 in that they provide $dditional t

---..,._._.,....,__,,-,__.._._~-,,____,_,,.,.-.~,,-_...._._,_,,-,-..__,-_...~...___.___.a-_

-. _ = -

F7

estrictions and controls not presently included in the Technical Specifications. On this basis, the Commission proposes to determine thet the changesdonotinvclveasignificanthazardsconsiderationsince[thechanges incorporate addition of restrictions.and controls that ere not currently included in the Technical Specifications.

Proposed chances 53, 55, 56, 58, 59, 60, 61, 62, 63, 70, 71, 77, 94, 206, 207, 217, and 252 represent a reouest for relief from an operating restriction.

-n

(

control or limitation on the basis that acceptable operation under the proposed conditions has been demonstrated. The proposed changes are similar to example fiv) of 48 FR 14870, in that the original restrictions had l'een imposed because acceptable operation had not been yet demonstrated, and are thus not likely to involve a significant hazards consideration.

The proposed changes presented in Items 38, 67, 79, 90, 91, 121, 128, 129, 154, 174, 184, 196 and 217 constitute changes to previously analyzed occurrences,

t. -

but the results of the charges are clearly within all acceptable criteria with 5

respect to the system or the component as specified in the Standard Review Plan. The proposed changes are thus similar to example (vi) of M FR 14870 of actions not likely to involve a significant hazards consideration.

The proposed changes presented in Items 7, 8, 9, 88, 106, 107, 114, 118, 119, 133, 148, 151, 154, 163, 210, 211, 213, 223, ??5, ??6, 240, 244, 245,

?49 end 250 constitute changes rade to conform to changes in the. regulations and are thus similar to example (vii) of 48 FR 18870 of actions not,likely to involve e signi'icant hazards consideration.

.9

58 Of the above proposed changes, most have already been incorporated by the Comission into the current Unit 2 Technical Specifications issued with the low-power license DPR-81.

Incorporation of these same changes in.'to Unit 1 Technical Specifications will upgrade the specifications for Unit I and make the Unit 1 Technical Specifications essentially equivalent in tenns of content, style and fonnat. Several additional changes have been proposed for both the Unit I and the Unit 2 Technical Specifications to incorporate infonnation into each necessary to achieve a comon Technical Specifications document, clarify certain requirements, and correct minor errors. These additional changes are addressed in whole or in part for Unit 1 by the following items enumerated as p

above:

Items 1, 6, 10, 12, 14, 25, 29, 30, 38, 46, 48, 54, 56, 57, 59, 60, 61, 62, 63, 64, 68, 72, 89, 90, 91, 103, 104, 117, 128, 129,, 137, 152, 153, 160, 161, 162, 165, 171, 176, 177, 191, 199, 201, 216, 217, 227, 234, and 251. Of these items, all but Items 38, 90, 91, and 177 are adminstrative changes previously noted to be encompassed by the Comission's example (1) of actions not likely to invel.y,e significant hazards considerations. The following is a description of each of the four nonadminstrative changes and how each is similar to one of the examples in 48 FR 14870.

The proposed changes noted in Item 38 to revise the movable control assemblies specification still meet the basis that ensure that (1) acceptable power distribution limits are maintained. (2) the minimum shutdown margin is maintained, and (3) the potential effects of rod misalignment on associated accident analysis are limited. The reworded action statements pennit the same variations from the basic requirements, with the only difference being the addition of a relaxation for electrically imovable rods that afe still trippable an,d within alignment.

This relaxation is justifiable in that the

59 previously mentioned basis is not violated. The benefits of these reworded specifications are increased clarity and additional operational flexibility by allowing of repair without curtailment to operation of an iden(i.fiable electrical failure to multiple movable control assemblies that does not affect trip ability or alignment. The proposed change is similar to example (vi) of 48 FR 14870 in that the results of the change are clearly within all acceptance criteria with respect to the system or component safety function. On this basis, the Connission proposes to detemine that the change does not involve a

~

significanthazardsco$ sideration.

~

The proposed changes in Items 90 and 91 involve changing the applicability statement for the Noble Gas Activity Monitor (RM-14A or 14B) in Tables 3.3-13 and 4.3-9 associated with the Containment Purge System from "*At all times" to

"*** MODES 1-4; also MODE 6 during CORE ALTERATIONS or movement of irradiated fuel within containment." The new applicability statement is added to the Table Notations for Tables 3.3-13 and 4.3-9.

The proposed changes only affect the " automatic termination" feature of the monitor (RM-14A or 14B), since the e

same monitor, with alann, is required to be available for the Plant Vent System in Tables 3.3-13 and 4.3-9.

When containment integrity is not required, in MODE 5 and a limited time in MODE 6 there is no need to provide automatic termination of release for the Containment Purge System. The proposed change is similar to example (vi) of 48 FR 14870 in that the results of the change are clearly within all acceptance criteria with respect to the system or component specified in the Standard Review Plan.

Furthennore, this change is more conservative than the example, in that the probability and consequences of previously-analyzed accidents are not increased afid safety

60 margins are not reduced. On this basis, the Commission proposes to determine that the change does not involve a significant hazards consideration.,

The proposed change presented in Item 177 involves adding containment penetration ennductor overcurrent protective devices for four additional penetrations in the Unit 2 containment. By adding these penetrations to those covered by Specification 3/4.8.4.2, all penetrations of the Unit 2 containment protected by circuit breakers are now included in Table 3.8-2.

The proposed changeissimilartoexample(ii)of48FR14870inthatitprovides i

additional restrictions 3and controls not presently included in the Technical Specifica1 tons. On this basis, the Commission proposes to determine that the change does not involve a significant hazards consideration since the changes

~9 incorporate addition of restrictions and controls that are not currently

... m.

included in the Technical Specifications.

a The Commission is seeking public connents on this proposed determination. Any comments received within 30 days after the date of publication of this notice i

will be considered in making any final determination. The Commission will not normally make a final determination unless it receives a request for a hearing.

Comments should be addressed to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.

t, I

...?

b

61 By July 18, 1985, the licensee may file a request for a hearing with

~

respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an 5'tomic Safety and Licensing Board, designated by the

~

\\

Commission or by the Chaiman of the Atomic Safety and Licensing Board Panel, h

will rule on the request and/or petition and the Secretary or the designated Atomic Safety and licensing Board will issue a notice of hearing or an appropriate order.

4 As required by 10 CFR 2.714, a petition for leave to intervene shall set forth

[

with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition L

should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:

(1) the nature of the I

petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding; and (3) the possible effect of any order which may be entered in th{ proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the

.3

62 proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up t,0, fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described bove.

Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the

\\

petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfied these requirements with respect to at least one contention will not be permitted to participate as a party.

I Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.

If a hearing is requested, the Connission will make a final detennination on the issue of no significant hazards ennsideration. The final determination will serve to decide when the hearing is held, t

e e

e 4

. - - - - - -, - - - - -, -., - - ~ - - -... ~ - - - -

63 If the final detemination is that the amendment request involves no significant hazards consideration, the Comission may issue the amerdment and make it effective, notwithstanding the request for a hearing. Any_hearino held would take place after issuance of the amendment.

If the final determination is that the amendment involves a significant hazards consideration, any hearing would take place before the issuance of any amendment.

Nomally, the Comission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Comission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.

A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention: Docketing and Service Branch, or may be delivered to the,Comission's Public Document Room,1717 H Street, N.W.,

Washington, D. C., by the above.date. Where petitions are filed during the 1

I

_m.. _, -..,, _

,,._.-,,,,.7,,

,.,.m-,

,,,r.,ce

64 last ten (10) days of the notice period

.c is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Unionat(800)325-6000(inMissouri(800)342-6700). The Western.11nion operator should be given Datagram Identification Number 3737 and the following message addressed to G. Knighton: petitioner's na.ne and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER Notice. A copy of the petition should also be sent to the Executive Legal Director, U.S. Nuclear Regulatory Commission Washington, D.C., 20555, and to Philip A. Crane, Esq., Richard F. Locke, Esq., Pacific Gas and Electric Company, P.O. Box 7442, San Francisco, Califoniis 94120 and to

^

Bruce Norton, Esq., Norton, Burke, Berry and French, P.O. Box 10569, Phoenix, Arizona 85064.

Montimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determinaton by the Connission, the presiding officer or the Atornic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request. The determination will be based upon a balancing of the factors specified in 10 CFR 2.71 (a)(1)(1)-(v) and 2.714(d).

I r

./

66 For further details with respect to this action, see the application for amendment which is available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the California Polytechnic State University Library, Documents and Maps Department, San Luis Obispo, California 93407.

Dated at Bethesda, Maryland, this 12th day of June

, 1985.

FOR THE NUCLEAR REGULATORY COMMISSION A

George W. Knighton, Chief Licensing Branch #3 Division of Licensing f

hk hCb g

DL:LB#B7)

LB

)

3 T M DL:LB#3 HR HSchierl[ng C

n GKnighton 85 06

_/85 06/g/85

_/ /85 06/@85 g

f OELD DL D:fR, LChandler TN HTh n

i g

b 06///85 05 QS 0

b+b p

,/

ML20128H550

Text

Navigation menu

Search