ML20206T095

Forwards Responses to NRC Concerns on Emergency Operating Procedures,Per 860911 & 15 Requests.Documents Describing Generation of Procedure ECA 3.1 Also Encl

ML20206T095
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	09/16/1986
From:	Leblond P COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
2084K, NUDOCS 8609230104
Download: ML20206T095 (167)

Text

{{#Wiki_filter:. ] )on.nrumansn b . Cr :.oo. m Address Reply to: Post Omco Box 757 Chee00,lEncis 80000 0767 September 16, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comunission Washington, DC 20555

Subject:

Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Emergency Operating Procedures NRC Docket Nos. 50-454/455 and 50-456/457

Reference:

March 26, 1985 letter from D. H. Smith to H. R. Denton.

Dear Mr. Denton:

The referenced letter provided the Procedures Generation Packages (PGPs) for Byron and Braidwood Stations. These PGPs have been utilized to construct the Emergency Operating Procedures (EOPs) for each station. Representatives froin Commonwealth Edison Company met with Ms. Jan Stevens and other members of your staff on September 11, 1986, in Bethesda, MD. A follow-up teleconference was held on September 15, 1986. Commonwealth Edison was provided with a list of NRC concerns associated with the PGP. This list is enclosed as Attachment 1. Commonwealth Edison Company has reviewed these concerns and has 4 provided a response to each item individually. These responses are contained in Attachment 2. It is our understanding that these responses are 1 acceptable to the NRC staff. I contains the documents that describe the generation of ECA 3.1 for Byron Station. This level of detail is considered to be typical of the EOP development effort at both Byron and Braidwood Stations. Please direct any questions you may have regarding this issue to this office. I Very truly yours, i l P. C. LeBlond Nuclear Licensing Administrator 1 I" ( cc: Region III Inspectors B/B g ] Ms. J. Stevens - NRR k R. Gruel - PNL g 2084K B609230104 860916 j PDR ADCCK 05000454 F ppg i

p-w ATTACHMENT 1 i i 2984K

2 Our review of the B/B P-STG identified the following concerns: 1. A goed description.of the organizational aspects of preparing the E0Ps from the generic technical guidelines is provided, and Attachments A and C provide a useful plant description and detailed differences between B/B and the reference plant. However, all deviations from and additions to the generic technical guidelines should be included in the PGP, and an analysis or other technical justification supporting the deviations and additions that are of safety significance should be provided. The Step Deviation Document (Figure 1 of the P-STG) should be completed for each procedure and included in the PGP. A meeting was held between the staff and the WOG Procedures Subcomittee on March 29, 1984, to discuss the task analysis requirements of Generic Letter 82-83 (Supplement 1 to.NUREG-0737). The sumary of the meeting is contained in a NRC memorandum from H. Brent Clayton to Dennis L. Ziemann dated April 5, 1984. At the meeting the owners group made a presentation on the background of the ERG development program as it relates to the issue of task analysis. The presentation included a description of the (1) ERG background documents, (2) development of Revision 1 to the ERG, (3) interactions with NRC requirements, Supplement 1 NUREG-0737, and (4) an overview of how the WOG had responded to the requirements. Based on the presentations, the staff comented that Revision 1 of the ERG and background docments provide an adequate basis for generically identifying information and control needs. As a result of the above meeting the staff has made the following additional coments that should be acted upon by CECO and submitted as part of the PGP: a. Provide a description of the process for using the generic guidelines and background documentation to identify the characteristics of needed instrumentation and controls. For the infomation of this type that is not available from the ERG and background documentation, you should describe the process to be used to generate this information (e.g., from transient and accident analyses) to derive instrumentation and control characteristics. b. Identify existing plant instrumentation and how it differs from the reference plant in Attachment B of the P-STG. Ceco should provide justification in the PGP for potentially safety-significant plant-specific deviations from the ERG instrumentation and controls. These should be submitted in the plant-specific technical guideline portion of the PGP, along with other technical deviations, For each instrument and control used to implement the E0Ps, c. there should be an auditable record of how the needed characteristics of the instruments and controls were determined. These needed characteristics should be derived from the infomation and control needs identified in the background documentation of Revision 1 of the ERGS or from plant-specific information.

3 B. Writer's Guide Our review of the B/B writer's guide, pertaining only to the instructions for producing E0Ps, identified the following concerns: 1. E0Ps are reviewed and approved by qualified individuals to ensure their accuracy. There is no provision for approval signatures on the cover pages. Section IV.B should be revised to include a system or documentation of the review process. 2. Criteria for the various instructions within the writer's guide need to be sufficiently explicit to assure comon understanding by procedure writers. The writer's guide contains a number of statements in which several format options are available to procedure preparers. The guidance provided for formatting procedures should be revised in the following case': s a. Section IV.B.4.c states that the " order of the symptons is left to the discretion of the writer, as well as the choice to use strict ordering...or a loose ordering." The writer's guide should be revised to provide criteria for ordering of entry conditions or symptoms, and to designate the use of either numbers, letters, closed bullets or open bullets. b. Section IV.D.2.a indicates that figures and tables contained within the text of a procedure may be titled in either of two ways, depending upon the writer's choice. This section should be revised to designate a single method for titling figures and tables contained within the text of a procedure. c. Section IV.D.2.d should be supplemented with an example of how a table in a procedure should be formatted, d. Section V.F.5 states that parentheses and brackets "may be used by the writer as desired to emphasize..." This section should be revised to discourage the use of parentheses and and brackets for emphasis. J

4 Section VI.I indicates that equipment, controls and displays e. may be identified in any of several methods, depending on the discretion of the writer. This section should be revised to I designate a preferred menthod for identifying equipment, controls and displays, and to provide guidance for its consistent use throughout the E0Ps. 3. Placekeeping aids can assist the operators in keeping track of their position within a procedure. These aids are of particular importance when performing concurrent steps or procedures, and in situations where the operator's attention is diverted. Section IV.C should be expanded to include a discussion of some type of placekeeping aid. 4. As noted in Section IV.C.6, information should be presented so that interruptions in its flow are minimal. To insure that the flow of information from procedures to operators 'is uninterrupted, this section should be revised to indicate that in no case may action steps be split between two pages. 5. The manner in which the text is organized and divided should be evident through the use of headings and an alphanumeric numbering system, so that operators can keep track of where they are in the procedure and know how to move easily and quickly to other parts of the procedure. If a step continues on a subsequent page, Section IV.C.6 should be revised to provide some method of noting the step number on the subsequent page 6. Referencing of and branching to other procedures or sections of procedures can be disruptive arid cause unnecessary delays. The guidance offered on this topic should be expanded as follows: 4 a. Section IV.D.2.c.1 illustrates the use of "from" when referencing a figure. Section VI.H does not address the use of "from" when referencing, and either should be expanded to do 50 or the example in Section IV.D.2.c.1 should be rewritten, b. In order to sufficiently emphasize GO T0 statements, Section VI.H.2 should instruct that the words GO T0 be fully capitalized. 7. The correct use of punctuation can significantly increase the understandability of procedures. Section V.E discusses the use of hyphenation and gives examples of instances where words may be hyphenated to prevent confusion with other words. Certain rules given in this section, 2.d. f, and i, do not reflect standard English usage, do not appear to make these words less confusing, and should be avoided. 8. Vocabulary and syntax should be readily understood by both the procedure preparers and operators. To achieve this, the following items should be addressed:

5 a. A list of acceptable verbs and their definitions for use in the E0Ps should be included in the writer's guide, b. Section V.G. references the B/B Administrative Procedure for approved abbreviations. This is not sufficient. In order to ensure consistency in the E0Ps, the writer's guide should contain its own inclusive list of acceptable abbreviations, symbols, and acronyms for the use in the E0Ps. c. Complicated or confusing terms should not be used in the E0Ps. For this reason, the writer's guide should provide a list of words to avoid using in the E0Ps. 9.. Instructions should be written for various types of action steps that an operator may take to cope with different plant situations. The guidance provided in Sections VI.A.6 and VI.A.7 should be expanded to include more explicit definitions and content to the steps.

10. Section VI.E.1.b states that, as a general rule, diagnostic instuctions shall not appear in high-level steps. Consideration should be given to providing the same guidance regarding the use of operative instructions in high-level steps.

For example, an example given in Section VI.E.2.b has a high-level step " START AN RCP". However, this is not an instruction to start the pump per se, but a heading for the substeps to follow. The substeps may provide actions that are to be taken (e.g., start the associated lift pump) before the RCP is started. This situation would be avoided if Section VI.E.1.c stated that operative instructions shall not appear in high-level steps.

11. Notes and cautions provide operators with important supplemental information concerning specific steps or sequences of steps in the E0Ps. The information provided in Section VI.G should be revised to address the following points:

a. This section should provide an alternate emphasis technique for the distinction between cautions and notes. Cautions are currently to be distinguished from notes by the use of all capitals in the text. The use of all capitals makes text more difficult to read than mixed case and should be avoided. As an example of an alternate method notes may be enclosed with straight lines instead of asterisks. b. This section should indicate that notes should always precede the step to which they apply, even if the note pertains to the results of a step. I 12. Foldout pages are cumbersome and the folds are subject to wear that may reduce legibility or lead to tearing. Section VII.F 4 should revised to specify the manner in which such disadvantages will be overcome, or should specify that another format be used to present the information contained on the foldout page (i.e.}. placing the information on the facing page of the procedure

6

13. Status trees provide important safety information to operators.

Thus, it is critical that they be completely understandable. The guidance provided in Section VII.G for the preparation of the status trees should be expanded with regard to the following points: a. Color coding, line types, and end symbols are used in the status trees to provide distinction for the various paths. Although the examples are consistent with the construction of status trees in the ERGS, this section should specify how these items are to be properly formatted. b. Because hand-drafted flow charts are more difficult to read than produced by computer graphics or professional draftsman this section should be expanded to include guidance for the size of letters and symbols to be used and criteria for readability. c. The entire text of the sample status tree presented in Figure 8 is capitalized. If all words are so capitalized, then capitalization cannot be used for emphasis; furthermore, text written in all capitals is more revised to state that capitalization in status trees will conform to the rules established for other E0Ps.

14. To reduce confusion, delay, and errors in execution of E0P steps, the following concerns should be addressed:

a. E0Ps should be structured so that they can be executed by the minimum control room staffing required by the Technical Specifications. b. Instructions for structuring E0Ps should be consistent with the roles and responsibilities of the operators. c. Action steps should be structured so as to minimize the movements of personnel around the control room while carrying out procedural steps. d. Action steps should be structured to avoid unintentional duplication of tasks. e. E0Ps should be structured so that the control room supervisors will be able to follow staff actions and monitor plant status. See NUREG-0899, Section 5.8, for additional information.

15. Because they will be used in stressful circumstances and under time constraints, E0Ps must be easily accessible to operators and easily identifiable.

The writer's guide should address the accessibility of E0Ps and techniques to distinguish them from 4 other plant procedures.

F' 7 16. It is important that the quality of E0P copies (e.g., legibility completeness, color) approximates the quality of the original procedure to preclude operator difficulty in reading the E0Ps. The writer's guide should be expanded to address this point. See NUREG-0899, Subsection'6.2.2, for further information. 17. E0Ps must be current to be usable. The writer's guide should describe a system that will ensure the E0Ps are updated in a timely fashion when changes occur in plant design, in Technical Specifications, in the ERGS, in the control room, or in other plant procedures that affect E0Ps.

18. The following typographical errors and inconsistencies between examples and text should be corrected:

a. Section VI.F.3.d is mission a coma before THEN. b. Section VI.F.3.e shows a period, rather than a comma, before THEN. c. Section VII in several places references heading instructions provided in Section VII.C.1.2.3. No such section exists. It appears that the reference should be Sections VII.C.1, VII.C.2, and VII.C.3. d. Figure 5 includes the title " FIGURE IB(w)EP ESO.1-1." It appears that this should be " FIGURE 18(w)EP ES 0.1-1." C. Verification and Validation Pregram Our review of the 8/8 verification and validation programs identified the following concerns: 1. The types of personnel involved in the verification and validation process (i.e., engineers, procedure writers, operations persnnnel, and human factors experts), and the roles and responsibilities of these individuals, should be specified. 2. Particular attention should be paid to deviations from and additions to the generic technical guidelines that are.of safety significance during the verification and validation programs. These verification and validation steps can be accomplished separately or as a part of the E0P verification and validation programs. The PGP should discuss how the deviations from and additions to the ERGS are to be verified and validated.

8 3. The validation progran description states that table-top reviews, simulator exercises, control room or simulator walk-throughs, and references to the generic validation will be used, but does not state the conditions under which each will be used. The validation program should be revised to address the following: a. The validation program should state that simulator exercises are the preferred validation method. The program should be expanded to include a description of the criteria that will be used to select the scenarios to be run during the validation process. The criteria should be developed on the basis of what is needed to validate the procedures and should ensure that single, sequential, and concurrent failures are included.- A review of the capabilities and the limitations of the simulator will then identify what can be validated on the simulator, b. For the parts of the E0Ps that cannot be validated on the simulator, the criteria for selecting any additional validation that may be needed and the methods to be used, such as a control room walk-through or a mock-up walk-through, should be described. c. The reference method of validation is inappropriate and should be deleted as a validation method. 4. The E0Ps will require a certain number of operators to carry out the various activities and steps as specified. The validation program description should indicate that the E0Ps will be excercised, during simulator excercises or control room walk-throughs, with the minimum control room staff size required by the facility Technical Specifications. 5. The verification and validation program descriptions should include the criteria or methods that will be used for determining the need to reverify and revalidate any changes in the E0Ps, resulting from either the verification and validation program or from subsequent E0P revisions. 6. The verification and validation programs should describe the method by which the four B/B units will be handled in the verification and validation process to account for unit differences. D. Training Program 1 Our review of the 8/B training program for E0ps identified the following concerns: l

l 9 1. Although the PGP states that a simulator will be used for operator training, the training program description should be expanded to address the following items: a. Discuss the method to be used to train the operators in areas where the simulator does not react like the plant and in parts of the E0Ps that cannot be run on the simulator. Under these i situations, walk-throughs should be used for operator training. Classroom training is not an appropriate substitute for simulator or walk-through training. b. Address the extent that all E0Ps will be covered by all operators, particularly if walk-throughs will be used to train aspects of E0Ps not taught in the simulator. Indicate the use of a wide variety of scenarios, including c. multiple (simultaneous and sequential) failures, to fully excercise the E0Ps on the simulator and in control room walk-throughs, thus exposing the operators to a wide variety of E0P uses. d. Indicate that operators will be trained to use the E0Ps as a team and that each operator will be trained in the role that he would be expected to take in an actual energency. 2. The training program should state that the operators' knowledge and performance on the use of th,e E0Ps will be evaluated during and after training and that appropriate follow-up training will be conducted, if necessary, i i I I l t l

I ATTACleeplT 2 Cosmonwealth Edison Company's responses to the specific concerns i raised by the NRC staff in Attachment 1 are discussed below: ITEM A.1 Documentation presently exists for procedure step deviations from the ERG's. Included in this material is the technical basis for the step deviations. This material is large and bulky and it is not feasible to include in the PGP. However, Commonwealth Edison Company intends to expand the step deviation document to include justification for the bracketted, plant-specific steps. This work will be completed by six months following i the issuance of a full power license for either Braidwood 1 or Byron 2, whichever comes first. ITEMS A.I.a. b, c The Westinghouse Owners Group background information on the generic i ~ instrumentation and control was compared against the existing plant instru-mentation. This comparison is presented in Attachments A and B of the PGP. specifically, Attachment B describes the plant specific instrumentation and 3 highlights any deviations from the referenced plant. These deviations from the referenced plant are fully justified in Attachment C. The individual plant and unit setpoints were determined during a detailed setpoint review. This review is documented at commonwealth Edison Company. I ITEM B.1 I The review mechanism and format for all plant specific procedures is tightly controlled by administrative procedures at each site. These procedures control the format for the approval signatures. This is discussed within the p0P in Section II.D, Plant Specific Technical Guidelines. The existing administrative procedures will be strengthened by the addition of i } guidance on the location for the placement of the approval stamp. In addition, there will be a requirement to stamp every page of the 50ps. This additional guidance will be implemented and referenced in the PGP by January 31, 1987. t l ITEMS B.2.a._b. c. e/B.6.b/B.7/B.10/B.11.a/B.13.b. c cossmonwealth Edison Company has reviewed these issues and has concluded that they represent valid human factors concerns. However, these issues must be integrated into commonwealth Edison's ongoing Human Factors review effort. The schedule for the resolution of these procedure related human factor issues is June 1, 1987. Therefore, these issues will be j submitted to commonwealth Edison's Human Factors review team for inclusion 1 in the broader, human factors procedure review. The resolution of these items will be specifically addressed to the NRC upon completion of this segment of the bop review.

i -- i ITEMS B.2.d/B.3/B.5/B.6.a/B.8.a. c/B.9/B.11.b/B.12/B.13.a/B.15/B.16/B.18/C.1/ C.2/C.3.a. b/C.5/C.6 Commonwealth Edison Company has reviewed these concerns and has concluded that they warrant incorporation. Revisions to the PGP will be completed by January 31, 1987. However, the changes to the PGP discussed above will not be reflected in the BOPS until six months after the issuance of a full power license for either Braidwood 1 or Byron 2, whichever comes first. ITEMS B.14/C.4 Commonwealth Edison Company has reviewed these issues and has concluded that they warrant incorporation. However, the PGP revisions will include specific reference to the plant administrative procedures that reflect the actual operating practices. These PGP revisions will be completed by January 31, 1987. ITEM B.4 Commonwealth Edison Company has reviewed this specific issue and has concluded that Section IV.C.6 already addresses this issue to the maximum extent feasible. Thus while Commonwealth Edison agrees with the concern raised, no further action is contemplated. ITEM B.8.b This concern raised by the NRC staf f would require Conunonwealth Edison company to include the list of approved abbreviations in the PGP. After careful review, Commonwealth Edison Company has concluded that this proposed action would not be prudent for the following reasons; (1) The list of approved abbreviations is very large and unwieldy totaling over 35 pages (2) Leaving this large list in its present location allows for continued easy administrative control over its contents (3) This list of abbreviations is utilized in all station procedures (4) This list is utilized in applications outside of the scope of procedure usage such as the labeling of main control room components. Therefore, based upon the above discussion no further action is contemplated.

4 ITEM B.17 Comunonwealth Edison Company has concluded that the concerns raised by this issue are adequately addressed by the pre-existing plant administra-tive procedures. These procedures contain specific guidance regarding the alteration of procedures and the plant modification process. This system will be described in the PGP. Included with this description will te examples to illustrate when the 50Ps should be reviewed for potential changes. In addition, the PGP reference list will be expanded to include the appropriate plant administrative procedures. This work will be completed by January 31, 1987. ITEM C.3.c This issue was resolved during the meeting held on September 11, 1986, following a clarification of the NRC staff's concerns. ITEMS D.1.a, b, c, d/D.2 i The PGP currently complies with the guidance provided in NUREG-0899. a In addition, the training out1 Lined in this issue is conducted by n==anwealth Edison's Production Training Department. Their program has been accredited by the Institute for Nuclear Power Plant Operation (INPO). Byron Station received INPO accreditation for its Operator Training Program in December, 1985. Braidwood Station is expected to receive its accreditation by December, 1987. The INPO accreditation criteria specifically addresses these concerns. The POP will be revised to more adequately reference the training conducted'under the accredited Production Training Department's program. This revision will be completed by January 31, 1987. i f l 2084K i

ATTRCteatrF 3 CONTENTS Discussion Item 1 - IBCA 3.1, Revision 1, WOG-1 Item 2 - Initial Step Deviation Document Item 3 - Procedure Verification Item 4 - Procedure Changes Item 5 - On-Site Review Deficiencies Item 6 - Training Change Documentation Item *1 - Training Change Verification Item 8 - 1BCA 3.1, Revision lA, WOG-1 l l l l l 2084K

DISCUSSION 2084K

DISCUSSIM 4 DEVELOPMENT OF BYRON STATION IBCA 3.1 SGTR WITH LOSS OF REACTOR COOLANT - SU N E RECOVERY DESIRED - UNIT 1 Byron 1BCA 3.1, Rev. 1 WOG-1 (Item 1) was developed from the Westinghouse Owners Group Emergency Response Guideline ECA 3.1 HP Rev. 1. All background information related to the procedure was reviewed and plant specific steps were developed as required by the ERG and WOG Executive Volume. Upon completion of the draft copy of 1BCA 3.1, Rev. 1, WOG-1, an initial Step Deviation Document-(Item 2) was generated in accordance with Byron Station Procedure Generation Package (PGP). The next step in the process was to complete a verification of the procedures (Item 3) in accordance with the PGP. This program was a joint effort with two senior licensed members from the Byron Station and two certified senior operators from the Braidwood Station as members of the verification team. This effort took ten working days to complete the entire i set of emergency procedures. One month after the Verification Program was completed, a Validation Program was conducted on the Braidwood simulator. This program took five days and all procedures were validated acceptable in accordance with the Byron /Braidwood PGP Validation Program. ) Upon completion of the V&V Programs, recommended changes were incorporated into the procedures and these changes are documented in Item 4. The final draft of the Emergency Procedures was given independent On-Site Reviews by both Byron and Braidwood Stations. Deficiencies noted I during these OSR's were corrected and documented in Item 5. I Prior to final approval of the Byron Station Plant Superintendent, all Byron Station licensed operators received a five day simulator training program on the new procedures. This program brought out a few significant changes that required 1BCA 3.1, Rev. lA, WOG-1 to be developed. These changes were documented per Item 6 and verified por Item 7. l Presently 1BCA 3.1, Rev. lA, WOG-1 (Item 8) is on the books at both l' Byron and Braidwood Stations. All operators are receiving training on the procedures in accordance with established training programs. 5 2084K j i I

ITEM 1 - IBCA 3.1, REVISION 1, WOG-1 2084K

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n..

n J =- s.n n/ - x - n u z a. a, l s m , ew+ ru s>-i. o.v.j 2. D~s,s - ~a -1 ./ a ] R.vi.w.d by _ 'i m C >,, ~ SUPEftSEDED . thn;. APPROVED

1 4 '.. SGTR WIIM {WCG-1 l SUBCCOL E D RECOVERY DESIRED 1 t l N I- ~ A PURPOSE RCS to cold shutdown conditionsThis procedure pro while minimizing loss of RCSo coo inventory and volding in the RCS. B. SYMPTOMS ?_S!D D.*TRY CONDITIONS nis procedure is entered from: 1 IBEP-3, STEAM GENERATOR TUBE RUPTURE cannot be isolated from any intact SG. if a ruptured SG , Step 3, 2 be :solated by closing its isolatiIBEP-3. STEAM G Step 5, on valves. if PZR PORV cannet 3. SG pressure is less than low steamli1BEP-3 STE Step 12, if the ruptured is available for RCS cooldown.1BEP-3, STEAM G 4. . Step 13, if no intact SG 5. 1BEP 's. STEAM GENERATOR TUBE RUPTURE SG pressure continues to decrease f ll , Step 14, owing RCS cocidown.if the ruptured o 6 1BEP-3. le:s than acceptable value. STEAM GENERATOR TUBE RUPTU Step 15, if subece1ing :s 7 IBEF-3 STEAM GENERATOR TUBE RUPTURE does no,t increase after closing PZR PORV and i, Step 18 if RCS pres 8. ISEP-3, solation valve. SGTR WITHOUT PRESSURIZER PRESSURE CONSTEAM } be terminated. TROL, Step 7,.nd'E~'.-3 3 ) 'T 9, 1BEP L -3.1

c. net 1BEP ES-3.2 POST-SGTR COOLDOWN USINGPOSY-S 1BEP ES-3.3, POST _SGTR COOLDOWN USING Step 2, BLOWDOWN, Step 2, accumulators should not be isolated and STEAM DUMP, Step 2, if SI 10.

1BEP ES-3.1 POST-SGTR COOLDOWN USING B 1BEP ES-3.2 15, and 1BEP ES-3.3, Step 5, if a nonPOST-SGTR COOLDOWN USING STEAM and Step l',, cooldown. ruptured SG lt, not available for RCS t 3 l ,u,gn,g_y_ g_g_ Page 1 of 37 -1 m u. m (0110E) OCT 23 25

3. 0. S. R.

F.

O 1 REv. 1 SGTR WITH LOSS OF REACTOR COOLANT-IBCA J,1 WCG-1 SUBCOOLED RECOVERY DESIRED-UNIT 1 L l

11. 1 BEP-3, SGTR Unit 1.

Step 23. a r.d 1 BCA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, m up 7 and 10 if ECCS flow is required.

12. 1 BCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 21, if RCS pressure is less than technical specification for the maximum S: accumulator nitrogen pressure.

i l e SUPERSEDED i i APPROVED l OCT 23 G85 Page 2 of 37

e E2 12H Wii&1ilIMfI-d STEP M ACTION / EXPECTED REWOINE REWOfGE NOT OSTAINED ............e..e......................... I,,,,S, Jiani se i.ESS 46%, THE BCCS SHOULD RE ALINED FOR

• COLD LEG RECIRCUIATION USIMO 1 REP ES-1.3, TRABSFER TO COLD LES RECIItCULATIN.

= eseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen emesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene CAUTICg a IF OFFSITE Poller IS IAST AFTER SI RESET, THEN MANUAL ACTION MAY BE

• REQUIRED TO RESTART SAFwnrranna e
• EQUIPMENT.

eneseeeeeeeeeeeeeeeeeeeeee........eeeeeee neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e speg With procedure in effect, notify the

• Station Director who will evaluate for GREP condition per 35P-200A1.

eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemen 1 RESET SI:

a. Depress both SI reset

a. I_F SI reset can IIOT pushbuttons be verified, THEN reset SI per

b. Verify SI ACTUATED 190k PRI-5 CONTROL ROON permissive litptt - NDF LIT IMDWY'unaIBILITY.

c. Verify AUTO SI arm permissive light - LIT SUPERSEDED APPROVED w qa __ -

Page 3 of 37

REV. 1 SGTR WITH LOSS OF REACTOR C00VWT-IKA-3 1 WOG-1 SUK 00 LED REC 0VERY DESIRED-UNIT 1 i STEP H ACTION / EXPECTED REWONEE REWONSE NOT OSTAINED = 2 RESET CONTAllstENT ISOLATION:

a. Roset CastT Isolation Phase A

a. Roset per 1904 PRI-5 u u.su 200N IMACCESSIBILITY.

b. Roset CiEET Isciation Phase 3

b. Reset per 190A IEI-5 C NTROL 20(NE I - IBILITY.

c. Roset CBBIT Ventilation Isolation

d. Roset SI recirc sump isolation valves e ISIS 311A e 18I33118

e. Cneck SAC run lights - ANY LIT

e. Start one SAC per OBOk SBC-9 SAC STARTUP DURING AMORMAL CONDITIONS.

f. Open instrument air containment isolation valves e

IIA 065 IIA 066

g. Open service air containment isolation valves e

ISA032 e 15A033

h. Open fire protection containment isolation valve e 17pe10 APPROVED vii23 Wi Page 4 of 37

(#1185) &&&E

2" * ? E2 lE! E Wii & % T M lM t m e -i. -i - 1,0, -,S. - - .S S r rA S. r DO EXCEED D GENERATOR } f REQUIRBIENTS:

• o 5500 W CMTINDUS DUTY 4 954 AMPS
• MAXIMEE.
• o 5935W C M TIMIOUS FOR 2000 HOURS 1050 AMS nAx1MM.

k

• o 6050 W CONTINUDUS FOR 2 HOURS S b

i 1050 AMPS MAXIM 38. c 5 Y y 2 cAUTIN ?

• PER HEATERS SHOULD BE IAADED W ONLY *
• OIII E SF BU S.

i

• OTHER NW-ESF LOADS SHOULD BE IDADED
• 5

......O.PPO.S..ITE ESF BEM.

• W 3

VERI:Y Ali AC RfttFR FMFilGI7FD BY 0 :FSITE PfEK 2: I

a. ESF 4KV Susses:

a. Try to restore power to

[ ESF busses with offsite t power.

• SAT 142-1 Bus Alive

[- Ligitt - LIT IF offsite power can NOT l e ECS 1412 n - Se restored, i e SAT 142-2 Bus Alive notify System Li$t - MT Dispatcher of ( e ACB 1422 - Ct4 SED esisting co'MI~1009 so art (, program can be ing:lemented. emergency em. i.e ratica i ?; necessary, verify the following equ t loaded on the k ESF as applicable: t-h Step continued on next page SOPERSED b s APPROVED UUI'33 W Page 5 of 37 =

f 1 D Y ETEP ACTIODUEXPECTED REWODNE REWOINE WT WTAspdED = o CENT CHG pusps o SI pumps con Room cailler Ohit i o cs pumps o CC pumps o SE pumps o AF pump 1A o 480 volt ESF buses

b. N005-ESF 4KV Busses:

b. IF offsite power can MDT E promptly restored, e SAT 142-1 Bus Alive Light -

establish necessary LIT ESF loads to maintain e ACB 1432 - m e n plant conditions. SAT 142-2 Bus Alive Light - e LIT e ACB 1442 - CIASED

1) Verify locally all breakers open on Bus 143 and 144.

2) Pull-to-lock all non-running MS pumps.

3) Energise Bus 143 and 144 from ESF cross-tie breakers.

4

4) Open all da9 volt 5

transfe---- tr. u b:. breakers a.. %Aated with Bus 14.'J and 144. Step continued on t,wnt page v SUPERSEDED APPROVED OCT 23 W5 Page 6 of 37 (81185) B. & & R.

I REV. 1 SGTR WITH LOSS 0F REACTOR C00. ANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UN1T 1 STEP H ACTION / EXPECTED RENONOE,' RESOfGE ICT OSTAINED h

5) Re-energize PER heaters:

a) Close 4160 volt PER heater transformer's HIGI side breakers at electrical distritation panel. b) Close 480 volt PER heater transformer's IAN side breakers at IPN05J. c) Operate PER heater controls as needed to control system pressure.

6) Start a station air compressor por 030k SBC 9, SAC STARTUP DURIES mannarar.

M DITI M if necessary.

7) Energise other EM-ESF loads as necessary.

c. 6.9 KV Busses:

c. Try to restore power to busses with offsite power.

light - LIT ,I,,E offsite power can M e ACB 1572 - De rest red-e ACB 1592 - M notif,- ?_7te. Lead e SAT 142-2 Bus a vs Di tcher of wasting light LLT itions so an emergency e ACB 1562 - AC restoration program can e ACB 1582 - be laplemented. II outside air temperature Tees than it_'E. M start SR make-up p SS APPROVED WI'M J Page 7 of 37 (elles) gggg

E-i 1 D Y d SN H ACTION / EXPECTED RAWOISE REWONEE NOT OSTAINED = I eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee** cAUTIm

• NaOH ADDITIM TO THE CMTA!WINT i_

SPRAY SYSTEN IWST BE TEEN! MATED IStEN

• SPRAY ADDITIVE TANK ID-2 LEVEL LISTS ARE LII.

......eeeeeeeeeeeeeeeeeeeeeeeeeemse 4 CHFN IF CONTAIMcFMT SPRAY SHni D IE STUi+E n j

a. CS pumps run lights - LIT

a. Go to Step 5 E

g ~

b. Containment spray termination

b. Continue with Step 5 requirements - ACHIEVED:

M containment pressure is less than Containannt pressure Lggt e THAN IS PSIG 18 PSIG, and containment spray has run at least two hours e Spray operating time - A_I g do Steps 4c = E-LEAST TWO HOURS tarougth 4e.

c. Roset containment spray signal f

d. Stop CS pumps and place in standby:

N e CS pump 1A g e CS pump 13

e. Close CS eductor spray additive g

isol valves: I e ICS019A [ e IC80193 E E i sure m b APPROVED F G Mi isa m w e e av (mq,., c g g, g,,

REV. 1 SGTR WITH LOSS OF REACTOR C00UuiT-18CA-3.1 WO6-1 SU8C00 LED REC 0VERY DESIRED-UNIT 1 d STEP l l ACTION /EXPSCTED RENCBGE M ICT WTANGED l eesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen RCS PRESSURE MONITORED, IF

• RCS PRESSURE necewaama TO LESS THAN
• 300 PSIG (400 PSIG FOR ADVERSE W ),*

RH PWEPS NDST BE MANUALLY RESTARTED T ... e e n... e..O SUPPLY HATER M THE RCS. * ...e e .........es.. 5 CHECK IF RH PtM Mi SHOULD BE STOPPED:

a. Check RCS pressure:

a. Go to Step 6.

1) Pressure - GREATER THAN 300 PSIG (600 PSIG FOR ADVERSE CWIT)

2) Pressure - STABLE OR INCREASING

b. Stop RH pumps and place in atandby e RH pump 1A e RH pump 13 6

IN "IATE EVAL _UATION OF PLANT STn"US:

a. Check Auxiliary Building

a. Yry to identify and radiation:

isolate leakage.

1) Auxiliary Building vent stack effluent nooitors e Grid 2 Beta IPA 228 e Grid 2 Gas Low 195128 e Grid 2 Iodine 193328 l

e Grid 2 Gas High 1P3428 Step continued on next page APPROVED Page 9 of 37

REV. 1 SGTR WITH LOSS 0F REACTOR C00UWT-IBCA-3 1 WO6-1 SUSC00 LED RfC0VfRY DESIRED-UNlT 1 STEP H ACTION / EXPECTED REWONEE l REWOGGE NOT OSTANdED

2) ECCS pusy cubicles - LESS THAN ALERT ALAIDE SETPO!Irf e RH/CS pusp 1A Cubicle (IPR 13J):

e Grid 2 Beta IPA 213 e Grid 2 Gas IPS113 e RH/CS pump 15 Cubicle (IPR 14J): e Grid 2 Beta IPA 214 e Grid 2 Gas IPB114

• CENT OiG pump 1A Cubicle (IPR 17J):

e Grid 2 Beta IPA 217 e Grid 2 Gas IPA 117

• CENT CHG pusp 18 Cubicle (IPR 18J):

e Grid 2 Beta IPA 218 e Grid 2 Gas IPB118

b. Obtain samples e aCS activity e acs boron concentration e RCs hydrogen concentration e Ruptured SG(s) activity

c. Evaluate plant equipment:

o oc system o RH Systen o other equipment as necessary

d. Start additional plant

$ % Q Q(Q equipment to assist in recovery. APPROVED OCT 23 g Page 10 of 37 EME je1185)

M L E2 IEEE EMilIE6TI-2"^*2 d STEP H ACTION / EXPECTED MWOINE l m RDT WTAHOW 7 CMfr IF trA ARE IMTACT:

a. Check pressures in all 80s -

a. Verify all faulted SS(s) e isolated unless needed 5

ISOLATIW, Step 1. p e =-

• ALTERNATE MATER FCE AF PtSIPS *
• WILL BE MBCESSARY IF CST LEVEL n-

. mr'swames TO LES ...................S THAN 3%. g 8 CHEfr INTACT SS LEVFIR: 5-E

a. Barrow range level

* " rEn

a. Maintain total feed flow THAN 44 (34% FOR ADV"*** '***)

greater than See GBH tati: m =- E narrow range level greater than 44 (34% FOR ADVERSS W M :,a at least one 80. h

b. Control feed flow to maintain

b. I_g narrow range level in narrow range level between 4_)

.any intact 80 continues 3 (34% FOR ADVERSE QBET) and 50% to increase in an E uncontrolled manner, E go to 1 MP-3, STERN TU M EDFTURE, Step ?- E E E9 m I; E Y E { APPROVED = Page 11 of 37 =_

N 4 i E2 EME EMilIETM-2* 2 Fr .., s. i = As time permits ing RCS cooldown, check SSP 100-5 PLAIFF SHUfDOIN AIID a e b ennrnneer to insure appropriate steps *

• for RCS cooldown ar eeeeeeeeeeeeeeeeee....e me.t i-

.....eeeeeeeeeeen i Shutdown margin Id be monitored during R

• ...........CS cooldoun.

.eae........................ ir e...........eeeeeeeeeeeeeeeeeeee........ k If sufficient coo rate cannot be obtained with steam dungs only, consideration should be given to e using SS PCRV(s) on intact SS(s) as an additional steen release path. r c eseeeeeeeeeeeeeeeeeeeeeeeeeeeeee......... L. eeeeeeeeeeeeeeeeeeeeeeeeeeen............. e ggg If steam dusps are opened rapidly 1 with PSR pressure greater than 1930 PSIG, Main Steamline Isolation will E occur from Low Steamline Pressure SI.* C ISten PER pressure decreases to less a f than 1930 PSIS, Low Steamline E p Pressure SI abould be blocked. y seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.....t E 9 IMITIATE RCS C00LDEAl TO 200*F: b

a. Maintain cooldoun rate in RCS E-cold lege - IEEE THAN 100*F/NR Ey

b. Use RH System if in service

,i Step continued on next page, SUPERStDED a E r APPROVED = E Pese la of a, OCT 23 g r . (su.. ) ss M E_

= L REV. 1 SGTR WITH REACTOR C00UWT-IBCA-3.1 WO6-1 SUSC00 LED RY Dti3 IRED-UN :T 1 V A ut e { ACTION / EXPECTED RAWOIM l NEWOISE 807 OSTAlffEO } 1;.. STEP = 3 L; ~ E

c. Dump steam to condenser from

c. Manually or locally dump hc, g

intact SG(s): steam from antact SG(s): .[:j E

1) Check condenser available e Use SG PORV(s).

fh c e I [

2) Place steam dump modo selector g intact SG available, f' 5

!!ntitch in STEAM Po***U!E mede - perfor= the following I-

3) Manually adjust demand o Use faulted SG.

to initiate cooldown [Y I E -CR-J E -J

4) Momenter11y bypass cooldown y

i R interlock upon reaching P-12 o R RH System IIDT in g (550*F)

service,

= THEN use ruptured SG. i l 10 CHECK RCS SUBC00 LIM: i? E { g

a. RCS subcooling - ACCEPTABLE

a. Go to Step 24.

E using: g h 3 o ICONIC DISPIAY E -OR-o ATTAOBIENT A, STEP A AND l FIGURE IBCA 3.1-1 = m ~ E 11 CHFCE IF Qine YM FD RECOVERY g IS APPINFRIAT E: = ? I I 5

a. Check RINT level - MTER

a. Refer to FI C.s asCA-3.1-3 lE THRN 67%

to determine expected cust? = g sump level. y E-g CMt? sump level less than espected, 7 go to 1BCA-3.2. SGTR IASS W REACTOR Il! COOLANT-SATURATED RECOVERY DESIRED, Step 1. I Step continued on neat page m ,,,. E w APPROVED .v j OCT 33 35 B" Page 13 of 37

r 1 Y d STW H ACTION /EMPECTED REWONOE l N NOT WTAINED h

b. Check ruptured 80 narrow

b. Comeult TSC to determine if range level - LESS THAN recovery ahcold be leted using 13CA-3.2, 96% (66% PM ADVERSE QOff)

E v1TN ImSS or Reactor CODEJWT-SATURATED R300VERY DESIRED, Step 1. 12 CHECK IF ECCS IS IN SERVICE: Go to Step 20. o Any SI pump run light - LLT -OR-o CENT CHG pump discharge to cold leg injection isolation valves - OPEN: o ISISSSIA o ISISSSIS 13 PLarF A I P2R 'FATER SWITCHFS IM MF MITIG I : eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen VOIDING MAY RCS DURING

• RCS DEPRESSURIEATIW.

yetis WILL

• RESULT IN A RAPIDLY INCREASING PER
• LEVEL.

eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeecee 14 DEPRESS 1RIZE RCS TO REFILL PZR:

a. Use normal PER spray

a. Use one PER F...

I ND PORT available, use PER auxiliary spray valve.

b. PER level -

b. Continue with Step 15.

21% (50% FCS M level greater than E TA(set PCR ADVERSE QWET), I e-do Step 14c.

c. Stop RCS depressurisation APPROVED i

e6T 2356 Page 14 et 37

~ E' lEidiskiliLE/lilI&$lHi-2" 2 w..P H A ,A ....e....eeen.e..ee.e..e..e.e.ee.e.....se

.IP.CP.m Co a,Ee%. a, e

to.T. T,. A = De WDT BE STARTED PRIOR TO A STAM 1

• EVALUATI N.

i eseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen meeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeesseesses

• W MATURAL CI

, RTD BYPASS e m PEmATvaEs AmD Assoc 1ATsD e INTwernrwa gny 33 IMRCCURATE. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e. ECP ID or IC shou be run, if possible, to provide normal PER spray. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee 15 CHFCr IF Ai RCP SHninD BE STARTED:

a. All RCPs - STQPPED

a. Stop all but one RCP.

Go to Step 16.

b. RCS subcooling - ACCEPTABLE

b. Go to Step 24.

using: o ICWIC DISPIAY -W-o ATT N A, STEP A AND PIGURE 13Ch 3.1-1

c. PER level - M EkfER THAN 21%

c. Return to Step 14.

(Set POR Awv M N ) Step continued on nest page,. SUPERSEDED APPROVED ~ wi as es Page 15 of 37

?. ,.~ 1 Y f. %.? q., Y d STW H ACTIOBWEMPECTED M l M ICT S TAdBIED [. i; 'l:

d. Try to start an RCP.

. ;] ~ ~ti

1) Metablish conditions for 1

starting a ECF per 30F RC-2 d STARTUP OF A ESACTOR t COOLANT PUNP {1>

2) Start one ECP g,7 g':r

+ fr. .,y

g. 4 seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e

-, L r ;;: e q 7; k.Pf

• After at ing any SCCS pump, RCS 7

..t. h.ft' pressure 1d he allowed to ' g. J 4 stabilise before stopping another ECCS pump.

r.p f,:-

seeeeeeeeeeeeeeeeeeeeeemesessseeeeeeeeeen 3.: n..: <. NN N eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee Y $.l -- e e _. e t

+- r.g.a,

If ADVERSS WEE conditions esist and * .5 % subcooling requirements cannot be a

• C.! - i ;;

<Mi attained for SI flow reemetion, 15 }7 contact TSC for possible relaxation of subcooling requirements. ~.;-t 4

g. n.J.I, eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeaeeeeeeeee

-. e q. 7 ig;, =. 1 . -E 4, eeeeaeeeeeeaeeeeeaeeeeeaeaeeeeeeeaeaeeaee f() 4 g e e

• The CENT CHS and SI pumps

+x . %;c..) should be at on alternate 30CS k{' trains when possible. ? '.4- ..4 m e$', eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ( Mji.? 16 rHFff IF rFMT CHR PtEW(S) SprumD 7'g..i 7 E sFatT - n: }s...li. 4..;cj. ld,;;

a. CM CNS pump (s) - INJECTING 10

a. Go to Ptep 17.

.:, ;4;1.f, 3C5 COLD LESS .g Mn .gggr Step continued on next page '.= % w.r.,) kz. c Q.Y APPROVE _ c. n, g,g g ..~

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IBCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REN REMNSE NOT OBTAINED

b. Determine required subcooling from Table:

RCS SUBCOOLING (*F) 2 CENT CHG PUMP _(S) ON 1 CENT CHG I'WP N RCPs ANY ON ALL OFF ANY ON ALL OFF R[lAL ) RMAL ) RMAL V) ) o 2 RUNNING 39' (240*) 40' (240*) 35* (234*) 35' (234*) 1 1 RUNNING 40* (241*) 41' (241*) 35* (234*) 35' (234*) 1 0 RUNNING 44' (248*) 48' (248*) 35' (234*) 35' (234*) t

c. Check RCS subcooling - GREATER

c. DO NOT RE-ALIGN PUMP (S).

THAN REQUIRED VALUE using: Go to Step 24. c o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP B

d. PZR level - GREATER,fHAN 21%

d. Do not RE-ALIGN PUMP (S).

(50% FOR ADVERSE C3 NIT) Return to Step 14.

e. Realign CENT CHG pump (s) through normal charging:

1) Verify open CENT CHG pump (s)

1) Manually open valves.

miniflow isolation valves: ICV 8110 e ICV 8111

2) Manually close ICV-121 to M Step continued on next page SUPERSEDED A P P R O V E D OCT 23 95 Page 17 of 37 (01105)

3. O. S. R.

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REWONSE REWONSE NOT OSTAINED

3) Open charging line contain-ment isolation valves:

e 1CV8105 e ICV 8106 a cu..c.,,.cun... ~ ' cE55' leg inj~ectio7 ~ ' isolation valves: e ISI8801A l e ISI8801B

5) Open ICV-182 - GRDTER THAN 75%

6) Throttle CV flow using ICV-121 to maintain PZR level - between 4% (38% FOR ADVERSE CNMT) and 60%

17 04ECK I: MdE CENT CHG PUMP SHOULD 3E STOP 4 );

a. CEbrF CHG pumps - TWO RUNNING

a. Go to Step 18.

Step continued on next page i SUPERSEDED l APPROVED i

r REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REM REMNSE NOT OBTAINED

b. Determine required subcooling from table:

RCS SUBCOOLING (*F) ANY RCP ON A)1 RCpg OM SI PUMP STATUS ISORMAL (ADVERSE NORMAL (ADVERSE CNMT CNMT) CNMT CNMT) 2 SI RUNNING 45' (251*) 49' (251*) 1 SI RUNNING 48' (253*) 51' (253*) 0 SI RUNNING 70* (280*) 80* (280*)

c. Check RCS subcooling GREATER

c. DO NOT STOP CENT CHG THAN REQUIRED VALUE using:

pump. GO to Step 24. o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP B

d. PZR level - GREATER THAN 21%

d. DO NOT STOP CENT CHG pump.

(50% FOR ADVERSE CNMT) Return 'o Ste-14.

e. Stop one CENT CHG pump 18 CHECC IF ONE SI PUMP SHOULD BE STOP4D:

a. SI pumps - TWO RUNNING

a. Go to Step 19.

b. Normal charging - IN SERVICE

b. Go to Step 24.

Step continued on next page 9dft,nOC.V APPROVED Page 19 of 37

l REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

c. Determine required subcooling from table:

RCS SUBCOOLING (*F) ANY RCP ON Al1 RCPS OFF SI PUMP STATUS NORMAL (ADVERSE NORMAL (ADVERSE CNMT CNMT) CNMT CNMT) i 2 SI RUNNING 61* (267*) 69* (267*)

d. Check RCS subcooling GREATER

d. DO NOT STOP SI PUMP.

THAN REQUIRED VALUE using: Go to Step 24. o ICONIC DISPLAY l -OR-o ATTACHMENT A, STEP B

e. PZR level - GREATER THAN 21%

e. DO NOT STOP SI PUMP.

(50% FOR ADVERSE CNMT) Return to Step 14.

f. Stop one SI pump 19 CHECK IF REMAINING SI PUMP SHOULD BE STOPPE ):

a. SI pump - ONE RUNNING

a. Go to Step av.

b. Normal charging - IN SERVICE

b. Go to Step 24.

Step continued on next page c""5RSEDED APPROVED Page 20 of 37 NE (0110E) 3, o, g, g

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REN REWONSE NOT OSTAINED 'l

c. Determine required subcooling from table:

RCS SUBCOOLINO ('F) ANY RCP ON All RCPS OFF = SI PUMP STATUS NORMAL (ADVERSE NORMAL (ADVERSE CNMT CNMT) CNMT CNMT) 1 SI RUNNING 67* (268*) 73* (267*)

d. Check RCS subcooling GREATER

d. DO NOT STOP SI PUMP.

THAN REQUIRED VALUE using: Go to Step 24. o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP B

e. PZR level - GREATER THAN

e. DO NOT STOP SI PUMP.

21% (50% FOR ADVERSE CNMT) Return to Step 14.

f. Stop remaining SI pump 20 CONTROL CHAtG NG FLOW TO MALNTAIN P2R LEVEL GtEnTER THAN 41 GRE FOR ADVERSF CMMI)

I i SUPERSEDED APPROVED Page 21 of 37 NE j (01105) & gag

5 REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IBCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 1' e i j STEP ACTION / EXPECTED REWONSE REMNSE NOT OSTAINED ..e............ ....eeen.te. CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, AFFECTED RCP(S) SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION. eeeeeeeeeeeeeeeeeeeeeeeeeeeeman........._. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee CAUTION ON NATURAL CIRCULATION, RTD BYPASS TDtPERATURE AND ASSOCIATED INTERLOCKS MAY BE INACCURATE. ene...................................... emeteesee94eeettetenesteestateettettetet. NOTE RCP ID or 1C should be run, if possible to provide normal PZR spray. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeman 21 CHECK RCP STATUS:

a. RCPs - AT LEAST ONE RUNNING

a. Try to start one RCP:

1) Establish conditions per BOP RC-2, STARTUP OF A REACTOR COOLANT PUMP.

2) Start one RCP.

IF an RCP cn [9,e i I

started, THEN refer to Attachment B to verify natural circulation.

IF natural circulation can NOT be verified, THEN increase dumping steam.

b. Stop all but one RCP

• d?ERSEDED APPROVED Page 22 of 37 ONE (0110E) gggg a.

REV. 1 SGIR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 d STEP ACTION / EXPECTED RESPONSE REWONSE NOT OSTAINED .................$.......e. 48......e.ne. CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PZR LEVEL. 222222aaseA&&&&&&&sssssss46ssisimmassumes ...$.e........e.e.......e..e.e..e........ CAUTION SI ACCUMULATORS SHOULD BE ISOLATED FROM THE RCS, BEFORE PRESSURE DECREASES TO LESS THAN 800 PSIG, TO PREVENT DISCHARGING ACCUMULATORS. e......................................e. 22 DEPRESSURIZE RCS TO MINIMIZE RCS SUBC00 LING:

a. Use normal PZR spray

a. Use one PZR PORV.

IF NO PORV available,

b. Cycle PZR heaters as necessary THEN use PZR auxiliary spray valve.

c. Depressurize RCS until either of the following conditions satisfied:

o PZR level - GREATER THA41 ?6% (62% FOR ADVERSE CNMT) -OR-o RCS subcooling NOT ACCEPTABLE FROM ICONIC DISPLAY OR ATTACHMENT A, STEP A AND FIGURE IBCA 3.1-1 23 VERIFY ADEOllATE SHUTDOWN MARGIN:

a. Sample ruptured SG(s)

b. Sample RCS

c. Shutdown margin - ADEQUATE

e. Borate as necessary.

MPERSEDED APPROVED OCT 231!B5 Page 23 of 37 (0110E) B. O. S. R.

REY. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.2 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REM 3NSE REM)NSE NOT OSTAINED 24 VERIFY ECCS FLOW NOT REQUIRED:

a. RCS subcooling - ACCEPTABLE

a. Manually operate ECCS using:

pumps as necessary. Go to Step 25. o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP A AND FIGURE IBCA 3.1-1

b. PZR level - GPE.ATER THAN 4%

b. Manually operate ECCS (38% FOR ADVERSE CNMT) pumps as necessary.

Return to Step 14. l 25 C4ECK IF SI ACCUMULATORS SHOULD BE ISOLATED:

a. RCS subcooling - ACCEPTABLE VALUE FROM ATTACHMENT A,

a. R RCS hot leg temperatur greater than 400*F, STEP A AND FIGURE IBCA 3.1-2 THEN go to Step 26.

l g NOT, THEN do Steps 25b and 25c. I l

b. Check power to SI accumulator

b. Restore power to isolation discharge isolation valves -

AVAILABLE valves by closing the following breakers: o MCC 131X2A A3 (ISI8808A f o MCC 132X2A A3 (ISI88088 o MCL 13 M '. A2 (ISI8808C o MCC 1.n. (aSI8808D

c. Close all SI accumulator

c. Vent any ur. isolated discharge isolation valves and place out-of-service:

accusr.tlator by per Mrming the following: Step continued on next page l SUPERSEDED A P P R O V E D OCT 23 885 Page 24 of 37 (01105) 4

3. 0. S. E

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED RESPONSE REMNSE NOT OSTAINED 1SI8808A

1) Close the following ISI88088 nitrogen supply 1SI8808C isolation valves:

e ISI8808D e 18I8880 l ,m,..,. wn u en e IRY0268

2) Open the following accumulator vent isolation valves as necessary I

o ISI8875A (Accumulator A) o ISI8875B (Accumulator B) i o ISI8875C l (Accumulator C) o 1SI8875D (Accumulator D)

3) Open Accumulator vent j

header control valve l e ICV 943 26 CHECK IF DIESEL GENERATORS SHOULD Y STOPPE ):

a. Verify ESF 4KV busses energized

a. Try to restore offsite by offsite power:

power to ESF ous:7,- SAT 142-1 Bus Alive IF offsite power c w NOT Light - LIT be restored, e ACB 1412 - CI46ED THEN notify System Load

• SAT 142-2 Bus Alive Dispatcher of existing Light - LIT conditions so an emergency
• ACB 1422 - CLOSED AC restoration program can be implemented..

b. Stop any unloaded Diesel Generator and place in standby PUPERSEDED APPROVED WI3Jum (01105)

& O.& E

REV. 1 SGTR WITH LOSS OF REACTOR C0OLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION /EXP2CTED REM REMINSE NOT OSTAINED eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee CAUTION NOTIFY RAD CHEM Pansmurr. TO MONITOR RADIATION LEVELS IN CONDENSATE POLIS MRS AREL. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen 27 MIN MIZE SECONDARY SYSIEH CON" AMINATION:

a. Inspect Auxiliary Building and Turbine Building for leakage

b. Isolate or minimize leakage where possible.

DO NOT l isolate SI or charging path l

c. Ensure condensate polishers in service 28 CHECK RCP COOLING:

a. RCP seal injection flow -

a. Adjust ICV-182 as necessary '

GREATER THAN 8 GPM: to establish seal injection flow e RCP 1A e RCP IB e RCP 1C e RCI ID

b. RCP CC system flow - NORMAL

b. Establish normal CC WITH THE FOLLONING cooling t-RCos-AIMUNCIATORS NOT LIT:

1) Roset OttT l

e RCP THERM BARR CC Isolation Phase B, NTR FI4tf LON e RCP BRNG CC NTR FLOtt

2) Open appropriate CC I4tf System isolation e RCP PUMP THERM BARRIER CC valves as necessary WTR TEMP HIGH e RCP PUMP THERM BARRIER CC NATER FLott HIGH LOtt e RCP =No wrR T=MP HIoH SUPERSEDED APPROVED WI'23 553 Page 26 of 37 gggg

i REV. 1 SGTR WITH LOSS OF REACTOR C0OLANT-IKA-3.1 WOG-1 SUK00 LED REC 0VERY DESIRED-UNIT 1 STEP ACTION / EXPECTED N REMNSE NOT OSTAINED 29 C FCK IF RCP 9F LL RETURN FLOW 0ULD RE ESTAR IS4ED: S -

a. Both of the following Go to Step 30.

SATISFIED: e CC flow to seal water !f= (1FI-642 AIDC BLDG 383' I ELEV XX AISLE) e VCT pressure BETWEEN 5 PSIG AND 70 PSIG

b. Open RCP seal water return containment isolation valves to establish seal return flow:

e ICV 8112 l e 1CV8100

c. Verify seal return flow

1) Verify No. I seal leakoff

1) Manually open valves.

isolation valves - OPEN: e ICV 8141A e ICV 81418 e ICV 8141C e ICV 8141D h APPROVED Page 27 of 37 (01105)

3. O. S. R.

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IBCA-3.1 WOG-1 $U8C00 LED RECOVERY DESIRED-UNIT 1 STEP ACTNHi/ EXPECTED REWONSE REWONSE NOT OSTAINED l 30 CHECK IF Si't

RA F# DETECTORS SHOULD BE E D tl117F ):

a. Check intermediate range

a. Continue with Step 31.

current - LESS THAN 10-10 AMPS WHEN current less than 10-40 Anyg, TH!2! de Staps 30b and 3Gc.

b. Verify source range

b. Manually energize source detectors - ENERGIZED range detectors.

c. Transfer NR-45 recorder to one source range channel and one intermediate range channel J

SUPERSEDED APPROVED OCT 23 885 Page 24 of 37 (0110E)

5. O. S. R.

l u REV. 1 SGfR WITH LOSS OF REACTOR COOLANT-1EA-3.1 WOG-1 SUK00 LED REC 0VERY DESIRED-UNIT 1 STEP ACTION / EXPECTED REMJ8E REMNSE NOT OSTAINED 31 SHU"YWM UNNECESSARY PLAq ' EQu MENT:

a. Shutdown all main feedwater pumps

b. Shutdown all heater drain pumps

c. Shutdown all but ONE condensate /

condensate booster pump

d. Defeat NDCT Turbine Trip Interlock:

1) Place all NDCT valve control switches in BYPASS OPEN position:

e ICWOO4 1CW005

2) Place interlock fuses 6 and 7 in OFF position -

(0PM01J)

3) Reposition valves as necessary for temperature control and circulating water pump shutdown

e. Shutd7wn all but ONE circulating water pump and associated NDCT valves s

s 4t SUPERSEDED l APPROVED Page 29 of 37 E 23 $ (0110E)

i l REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IKA-3.1 WOG-1 SUK00 LED RECOVERY DESIRCD-UNIT 1 STEP ACTION / EXPECTED REWONSE REMNSE NOT OSTAINED eeaee.........eene.......eeeneaeen.e..... CAUTION e I FEED FIAN SHOULD NOT BE ESTABLISHED 1 TO ANY RUPTURED 8G WHICH IS ALSO FAULTED UNLE88 NEEDED FOR RCS COOLDONN. seeeeeeeeeeeeeeeeeeeeeeeeeeeeeee 32 CHEC C RJPTURFD SG(S) N_aDR0W RANG: LIVEL:

a. Ruptured SG(s) narrow

a. Refill ruptured SG to 82%

range level - GREATER THAN (50% FOR ADVERSE CNMT) 4% (34% FOR ADVERSE CNMT) using feed flow. IF either of the following conditions occurs, THEN stop feed flow to the ruptured SG unless needed for RC8 cooldown: o Ruptured SG pressure decreases in an uncontrolled inanner -OR-o Ruptured SG pressure increases to 1090 PSIG. e

REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IKA-3.1 WOG-1 SijK00 LED RECOVERY DESIRED-UNIT 1 STEP ACTION / EXPECTED N ngMNSE NOT OSTAINED 33 CHECif IF RCPS MUST BE STOPPED:

a. Check the following:

o Number 1 seal differential pressure - LESS THAN 200 P8ID e RCP 1A e RCP IB e RCP 1C

• RCP 1D

-OR-o Number 1 seal leakoff flow - LESS THAN 0.2 GPM e RCP 1A e RCP IB e RCP IC e RCP ID

b. Stop affected RCP(s)

c. IF all RCPs stopped, THEN, verify steam dump mode selector sw:,tch in STEAM PRESSURE mode.

34 CHECC

F RCS CO

) OVER)2ERSURE PROT lEC" ION CAN ti PLAC: ) IN SERVICE:

a. RC8 temperature - LESS THAN 380*F

a. Return to Sce,

m.

b. Place RCS Cold Overpressure Protection in service per BGP 100-5 PLANT SHUTDONW AND COOLDONN SUPERSEDEDAPPROVED Page 31 of 37 E'23 $

g,33,,3

IM I REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IBCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 I STEP ACTION /E?.PECTED REN REMNSE NOT OSTAINED 35 CHEC C IF RH EYST EM CAN BE PLAC ED IN SEE VIC E:

a. Check the following:

a. Go to Step 36.

RCS temperatures - LESS 'IHAN 350

• F e

RCS pressure - LESS THAN 360 PSIG

b. Consult TSC to determine if RH System should be placed in service.

36 CHECK RCS TEMPERATURES:

a. RCS temperatures - LESS THAN

a. Return to Step 8.

200*F 37 EVALUATE LONG TERM PLANT STATUS:

a. Maintain cold shutdown conditions

b. Consult TSC

-END-APPROVED OCT 23 985 Page 32 of 37 (01105)

5. O. S. R.

= [ l l REV. 1 SGTR WITH 0F REACTOR C00ULNT-1BCA-3.1 ,WO6-1 SUBC004.ED RE RY DESIRED UNIT 1 2500 I llll.; 2400 Igi. 2500 2200 j.. :. j 2l00 g gg :. 2000 1900 j ie00 J = s '1400 // /i 3 ,f 7.- p 7.. S iS00 f f.j r=.. 1400 3 3j j ;f 3.- is00 r l .- j

. l iam j

f;f f; E'""" i i/ /:/; i ACCEPTAALE j / ff j E '" i / //: /! / / 700 e

)

f .} g -.// i i i f . pgyy m -;.5. "- 500 ADWEftSE 400 C80ET -y IIDIth8AL ~. 300 . C8 e, f_T -

. 9 g ::.

N 7 1 I00 4:

.-i-SATU, RATIC, II 100 200 300 400 800 000 700 TEarERATUIE PF)

SUPERSEDED R,a.flGuec l'.~. A 3.1-1.waC00 LING MARGIN APPROVED DUT 23 gl$ Page 33 of 37 B. O. 8. R. g,,,

REV. 1 SGTR WITH LOSS OF REACTOR C0OLANT-1BCA-3.1 WOG-1 $UBC00 LED REC 0VERY DESIRED-UNIT 1 88 " i il 1: 2400 lit f-3300 11 l-an00 L,[ I' # ((;:. j am0 i q g '"o 3 ij pi / _. i ie00 3 7f : f; 1700 f;f f. ie0c m // f e is00 -) h 1 i a S '400 i i f f! if i i300 /) f iam ff ,f

• 1100

/ / / i I '0" i / /

/

1 I i 0" ACCEPTMLE [ r f fj E 0" i i/ / / i i

/.

} / \\ 400 - k NoT M. E! "aegy nonisas. . :/ I i

gegy 500 g

t =. 300 . p -- r loo :. satu, nario, n..c. . =.i i i-100 300 300 400 500 e00 700 TEldPEnATURE (*F) SUPERSEDED FIGURF ".T., 3.1-2 RCS SUix.Out.iNG MARGIN +50*F APPROVED l OCT 23 885 Page 34 of 37 g g, g g a (elles) 1

REV. 1 SGTR WITH LOSS OF REACTOR C00UWT-IKA-3.1 WOG-1 SUK00 LED REC 0VERY DESIRED-UNIT 1 4 - ;=: _ 1.. = w _q 'h EE: r~ - - ' - ~ .. i.. ~.~. : ~ g - -. _..... _ - T_T - .= = - - -.=r: r ~-- g l> Q---: -- '1:.sil:iT:]~ f"-ii f.:i.i: !==~= - - - ~ ~ ~ ~ ~ ~ --- ' ~ 8 "" : T - -3. ---- i.!I-*="Y_% 585: r -Gr~- r'~E'N -b

• :i.i}"'I 5

= 2...:: 2=r ' Q, F:i.:n.. - -";-- i.2. 2_.g p -- _d-h. g gggg ic h _ _ _ - d__ - -P. -t _._ _ _. g

; : ----- - w

- : :. __w..u :

==c.

i....

.... g:. 1 .-_.t.-- E - - - j:-_ i:.f:% i;h::i j; ';--.". :i.. -~-%[-i:~.1 r -

f :ii M--

~~--' =. = :- - =- - -r.-- - %=_:.. i _. :. c.: =e:3.. --- u... _ s : =

::.. : a

. :: -Ei-i - g-----p- ,. T -+ g ggg. 5.1 _... .-...-.i..i:-_- g ........_-__-__-:-==._.__.

3' +

p s18CA-3.2

-T fSUSC00 LEO Me..

...._ :r " = ~ ~ - - - - 32 SATUllATED - -r HECOVERY g' : .+-i--- -- r o =E RECOWERY APPROPRIATE - -. k

- :ti:!= _

~ g -1 appguyngayg - --..tx. V. :._ -

E=

= _a =

i. s-SO

= - m u. __.i =N=.=. _ _=... =_ = =.: = =_ =2 =_-a -%_s: -._ _ -._.m_-_ = = - -m_. --.,. :

_-- - r --.- :- - - a s

10 et 80 at INelCATED COIITA10000ENT SUIIP LEVEL ( IIICHES ) SUPERSEDED FIGURE M l. 3.1-3 CONTAINMENT w i? LEVEL VS RWST LEVEL APPROVED OCT 23 915 Page 35 of 37 (01105) S. O. S. R. '

F REV. 1 SGTR WITH LOSS OF REACTOR C0OLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ATTAQ9ENT A A. Determination of Post-Accident RC8 Subcooling:

1. Check Containment for ADVERSE conditions:

o Containment pressure greater than 5 PSIG -OR-o Containment radiation greater than 10 R/hr 5

2. Check RCS pressure on wide range pressure instruments (1PI-403A/405)

3. Determine temperature for RC8 pressure using NORMAL or ADVERSE CNMT curves from Figure referenced in procedure step.

4. Check average of ten highest core exit TCs from MCB indicators (ITI-001/002).

5. IF average of ten highest core exit TCs less than temperature for RCS pressure, THEN acceptable subcooling exists.

B. Determination of RC8 Subcooling for SI Flow Reduction:

1. Check RCS pressure on wide range pressure instruments (1PI-403A/405).

2. Determine saturation temperature for RC8 pressure using SATURATION curve from Figure 1BCA 3.1-1.

3. Check average of ten highest core exit TCs from KC

'-di atsrs (1TI-001/002).

4. Calculate RCS subcooling by subtracting average of ten highest core exit TCs temper,ature from saturation temperature.

5. Compare actual RC8 subcooling (Step 4) to required RCS l

subcooling. SUPERSEDED APPROVED OCT 23 895 Page 36 of 37 B. O. S. R. I

REY. 1 OPERATOR ACTION

SUMMARY

1EA-3.1 WO6-1 FOR IKA-3.1 SI REttrITIAT!cer: CENT CHG MW_MINIFLOW VALVES: Manually operate ECCS pumps as Close ICV 8110, ICV 8111 necessary H either: e RCS pressure i 1370 PSIG o RCS subcooling - LIE ACCEPTAALE (< 1670 PSIG ADVERSE QBtT) VEUR FRON ICENIC DESPLAY OR -AND-A' 7AO51ENT A. STEP h AND SI actuated F ;GutE isCA 3.1-1 Onse ICV 8110, 1CVS111 -OR-e *:S pressure > 2000 PSIG o PER level - CAIRIDT BE MAINTAINED >4% (38% FOR RED PATH SWWIARY: ADVERSE CWIT)

1. Suberiticality - NUCLEAR CST LEVEL < 201:

2. Core cooling - CORE EXIT i

o Crosstie unit CSTs TCs > 1200*F o Makeup from lEIDS or l radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate (344 FOR ADVERSE m) ABID o Prepare to isolate secondary wmL r--- FAlti <S00 of 3 SG GRE AVAIIABLE

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN LAST 60 MINUTES AIED RCS COLD LES T""""*TURE < 24 6

• F 1.

Verify secondary side of 3 SGs isolated

5. Containment - QBIT FR38803t3 > 50 PSIG 2.

Switch AF suction to SX M) To ' RF 3-2 IF f *" mIr.ru mu SG: o Uncontrolled pressure decrease -CR-o Caspletely depressurised M needed for cooldown GO 10 15EF E8-1 3 IF: APPROVED e musT level i_iG OCT 23 885

s. o. s. R.

Q (0110s)

T REV. 1 SGTR WITH LOSS OF REACTOR COOLANT-IKA-3.1 WOG-1 SUK00 LED REC 0VERY DESIRED-UNIT 1 ATTAOOUDif B The following conditions support or indicate natural circulation flow: RCS subcooling - ACCEPTABLE VALUE FROM EITHER ICONIC DISPLAY OR ATTACHMENT A, STEP A AND FIGURE IBCA 3.1-1. e SG pressure - STA5t2 OR DECREASING e RCS hot leg temperatures - STABLE OR DECREASING e Average of ten highest core exit TCs - STABLE OR DECREASING e RCS cold leg temperature - AT SATURATION TEMPERATURE FOR SG PRESSURE i $Nh - APPROVED

ruwwu, OCT 23 885 Page 37 of 37 (01105)

5. O. S. R.

6 ITEM 2 - INITIAL STEP DEVIATION DOCUMIDIT i i 2084K l l

p T-o BYRON EOP STEP DEVIATION DOCUMENT Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired Writer: E. Cope Date: 4-23-85 Page 1 of 5 Byron ERG Step No..' Step No. ' CHANGE DESCRIPTION REASON FOR CHANGE A A Changed " guideline" to Document 1BCA 3.1-is a B B " procedure" procedure, not a guideline 1st Note Added GSEP information Remind operator to before coordinate his efforts Step 1 with overall station actions 1 1 Added SI reset verification Plant specific detail criteria and procedure to reset SI 2 2 Containment isolation Phase A & Steps combined affords 3 B and Instrument Air Step a more logical flow of combined, along with containment actions. ventilation isolation reset. Included service air SI recirc These systems are sump isolation valves and fire required to be reset protection to be reset. in order to provide complete unisolation of containment. 3 4 Added method for restoring power Byron method more to AC bypass (ESF 4ky, Non-ESF comprehensive than ERG, 4ky, 6.9 kv) using off-site addresses needs and power. requirements of Byron equipment and , electrical' systems. l i Caution 5 Added caution on NaOH addition Commitment per FSAR i Step 4 termination requirement 0022-25 2-l $ (AER) Sb (AER) Changed to read - Containment Plant specific spray securing requirements requirement achieved. Added spray operating time at least two hours. 5 6 Changed " Low Head SI" to "RH" Plant specific terminology 6a, b, c 7a, b, c Added method to check auxiliary Plant specific method 1 (AZR) (AER) building radiation, sample l points and equipment to evaluate ___ 0110E)_. _ _. _ _, _ _ _ _ _.. _. _ _ (

_s. BYRON EOP STEP DEVIATION DOCUMENT Procedure No IBCA-3.1 Rev: 1 WOG1

Title:

SGTR With Loss of - /. Reactor Coolant-Subcooled j Recovery Desired Writer: E. Cope Date: 4-23-85 Page 2 of 5 Byron ERG Sten No. ' Step No. ' CHANGE DESCRIPTION REASON FOR CHANGE 7 (AER) 8 (AER) Changed from " Check If SGs Are Preferred plant Not Faulted" to " Check If SGs terminology Are Intact" 2nd Note Added step to consider use of Provide addition 1 before both steam dumps and SG PORV cooldown if necessary Step 9 on intact SG 3rd Note ERG Step 36 states plant This is a more logical before specific steps related to place to remind the Step 9 cooldown should be placed after operator to observe step 35. Byron will use a Note other cooldown instead before Step 9. requirements before commencing an RCS. .cooldown. 9 10 Changed " Cold shutdown" to 200'F Plant specific t "RHR" to "RH" terminology Added method for dumping steam Plant specific method 10a (AER) lla (AER) Changed to read - RCS subcooling Byron plant specific ACCEPTABLE VALUE FROM ICONIC - method DISPLAY 10a (RNO) 10a (RNO) Change to include contingency Plant specific method step to allow for backup means of determining RCS subcooling. 12 13 Changed "High-Head SI" to "SI" Plant Specific i terminology " BIT-NOT ISOLATED" to " CENT Ng)( BIT at Byron, this ^ CHG" pump discharge to cold isolation is for same leg injection isolation valves path and purpose OPEN lst 1st Added seal and bearing Pump safety caution caution inspection recosmondation before before Step 15 Step 16 t 15b (AER) 16b (AER) Same as Step 10a (AER) Same as Step 10a (AER) 15b (RNO) 16b (RNO) Same as Step 10a (RNO) Same as Step 10b (RNO) 15d (AER) 16c (AER) Added Byron procedure for Plant specific method starting RCP (0110E)

BYRON EOP STEP DEVIATION DOCUMElff Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired Writer: E. Cope Date: 4-23-85 Page 3. of _5 Byron ERG Step No. ' Step No.

• CHANGE DESCRIPTION REASON FOR CHANGE lst Note 1st Note Changed "SI" to "ECCS" Plant. specific before before terminology i

Step'16 Step 16 2nd Note 2nd Note Added note allowing relaxation Background document before before of subcooling requirements by states that subcooling Step 16 Step 16 Shift Engineer if, during restrictions are very adverse containment conditions, conservative and that subcooling requirements cannot after evaluation by be met. cognizent individual (s) they may be relaxed if f they cannot be met. This statement confirmed by y NTD.

l 3rd Note 3rd Note Changed " Charging /SI" to " CENT Plant specific i

before before CHG" and "High-Head SI" to "SI" terminology Step 16 Step 16 Step 16 Step 17 Byron step seipience on SI reduce Byron evaluation of ERG Step 17 Step 18 flow is different from ERG SI reduced flow gave too Step 18 Step 19 reference plant. high a subcooling Step 19 Step 20 requirement. See Byron Step 20 Step 22 optimized SI reduced j flow program. 21a (RNO) 23a (RNO) Added plant procedure for Plant specific method i starting RCP i i 2nd Added Caution on SI accumulators To prevent inadvertent j Caution to be isolated before RCS discharge of accumulator before pressure decrease to less than N2 gas into RCS Step 800 psig g. 22b (AER) 22b (AER) Changed " Turn on" to " Cycle" Allow for better pressure control 22c (AER) 22c (AER) Changed "RCS subcooling to NOT Plant specific method ACCEPTABLE VALUE FROM ICONIC of monitoring RCS l DISPLAY" subcooling 24 26 Change "SI" to "ECCS" Plant specific i terminology 24a (AER) 26a (AER) Same as Step 10a (AER) Same as Step 10a (AER) 244 (RNO) 26a (RNO) Same as Step 10a (RNO) Same as Step 10a (RNO) i (0110E)

= - t = BYRON EOP STEP DEVIATION DOCUMENT Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired Writer: E. Cope Date: 4-23-85 Page 4 of 5 Byron ERG Step No. ' Step No. ' CHANGE DESCRIPTION REASON FOR CHANGE j-25 27 Added valves and valve circuit Plant specific detail breaker numbers and valve needed for veni:ing accumulator. 26 28 Change "AC Emergency" to "ESF Plant specific 4kv" terminology I Added instruction for load Plant specific method dispatcher to implement AC for restoring AC j restoration program emergency power 27 (AER) 29 (AER) Added methods used to minimize Plant specific method Secondary System contamination l 28 30 Added requirenents needed to . Plant specific detail verify proper RCP CC System and seal injection flow: Included methods to restore flow 29 (AER) 31 (AER) Added criteria to be met before Plant specific detail 4 establishing RCP seal return flow, and method for establishing l flow 30a (AER) 32a (AER) Changed " flux" to " current" Match MCB labeling 30c (AER) 32a (AER) Change to select one IR and one To obtain record of SR channel on recorder power decrease 31 (AER) 33 (AER) Added equipment to be shutdown Plant specific detail l as necessary j 33d (AER) 33 Added new step to verify Steam To ensute steam dumps dump in STEAM PRES 8URE mode if do not op'en ) all RCPs stopped. inadvertently i 34 Added step to place RC5 cold Plant specific overpressure protection in requirement service if below 380'F, also i added procedure to be used in place of system in service. 3 t I (0110E)

s i BYRON EOP STEP DEVIATION DOCUMENT Procedure No: 1BCA-3.1 Rev: 1. WOG1

Title:

SGTR With Loss of Reactor Coolant-Subcooled Recovery Desired Writer: E. Cope Date: 4-23-85 Page 5 of 5 Byron ERG Step No.

• Step No. '

CHANGE DESCRIPTION REASON FOR CHANGE 35 36 Change "RHR" to "RH" Plant specific terminology Figure Added: Necessary for use in 1BCA 3.1-1 RCS subcooling margin curve determining RCS subcooling Figure Added: Plant specific 1BCA 3.1-2 RCS subcooling margin + 50*F requirement for curve monitoring RCS subcooling Figure Added: Required by ERG 1BCA 3.1-3 Containment Sump .VS RWST Level Curve Attachment Attachment Steps for determining Natural ERG Request B A Circulation Flow . e. De o C.- (0110E)

\\ i e BYRON EOP STEP DEVIATION DOCUMENT Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

Foldout For 1BCA-3.1 Writer: E. Cope Date: 4-23-85 Page l_ of 1 Byron ERG Stop No. ' 5 top No. ' CHANGE DESCRIPTION REASON FOR CHANGE SI Changed "SI" to "ECCS" Plant specific REINITIATION terminology CRITERIA Changed RCS Subcooling to read Plant specific methods "NOT ACCEPTABLE FROM ICONIC for determining RCS DISPLAY OR ATTAC,19ENT A. STEP A" subcooling. 4 RR RED Deleted reference to TC(s) Byron has a CE RVLIS PATH P_ATH >700*F and RVLIS full range less System which cannot SUpeRRY SUleRRY, than 3 1/2 ft with not RCP's meet the criteria established. running. 3 CST AFW Change to reflect Byron format Plant specific j M SUPPLY and include additional steps preference and detail <20% SWITCH-to take in providing AF water i OVER supply. CST M j <3% I CENT CHG Instruction for closure of To ensure operator takes PUMP siniflow valves. necessary action to MINIFLON isolate miniflow until vnLVES auto closure of valves is installed. 00 TO IBEP-2 IF Change to read: l ANY UNISOLATED SG: o Uncontrolled pressure decrease Plant specific-format -CR-l GO TO IBEP ES-1.3 IF: o Completely depressurized Plant specific format UNLESS needed for cooldown Change to read:

• RWST level <45%

li. - 1 ,k*k (0110E)

4 ITEM 3 - PROCEDURE VERIFICATION i i l i t 2084K

h.t)..:. ':7 . ;.t,-c ~ s. - 2 s t. ATTACHNENT A WRITTEN CORRECTNESS EVALUATION CRITERIA CHECXLIST ECP TITLE % TR Wira Lnns OG RrACTr.2 ('rrt nur-Mpernen Reccgy Oc araea - E0P NUM8ER / /?cA - 3. / REVISION /. u g g,. / PERFORME0 BY A 2.-wwa__, DATE 5 7-g APPROVED BY OATE.f-/d'fj' (/ I. Procedure - General A. Format and Style 8 1. Printed borders are visible on all procedure pages. 4/92. The text, tables, figures and graphs are legible. ffd6f3. The general format of the procedure is consistent with the Byron Emergency Procedure Writers Guide (i.e., dual column format, page layout and required sections are present per Writers Guide). j d 4. Procedure contains all its pages in the correct order with correct procedure number, titles and page numbers on each page. 85. " Step continued on next page", typed at the bottom of each page where required. & 6. The last page clearly identified by the word ~END. <#h5'r 7. Each page contains the correct revision number.

1. d 8.

Attachments are labeled with number and title. c46f( 9. The title is descriptive of the purpose of the procedure. II Steo - Specific I A. Format and Style i d 1. Steps are numbered correctly. M 2. Nonsequential substeps are designated with bullets. d3. Steps deal with only one idea. g4 Steps are short with ambiguous words and phrases avoided. \\s [ d 5. The tests stipulates precisely what actions or decirions are required. Page 5 of 10 (0654M)

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.. s _..... ? !? ATTACHMENT A (Continued) h6. If there are more than two actions or objects in a step. they are listed separately. (8 7. Punctuation conforms with standard American English usage, d!i 8. Capitalization conforms with standard American English or with specifications for emphasis in Writers Guide. M 9. Only abbreviations, acronyms and symbols appearing in the Writers Guide and Byron Administrative Procedure, Conventions. Definitions and Approved Station Abbreviations (BAP 1310-T2) should be used. h10. Instruction steps make proper use of logic structure, dd 11. CAUTION statements are emphasized to standout from the text and precede NOTE statements for the same step. fd12. CAUTION and NOTE statements avoid action steps. AI4f13. ~ CAUTION and NOTE statements (where required) reecede the applicable step (s). d 14. Formulas and calculations are minimized. Where calculations s';. are necessary, space is provided. 1 ' dd15. Referenced procedures are identified by both title and number. 8 16. The use of referencing other procedures is minimized and is used only to eliminate excessive detail. <f@$r17. The instructions " refer to" and "go to" other procedures are used correctly and avoid routing user past important information such as cautions proceding steps. / M 18. Exit conditions are compatible with the entry conditions of the referenced procedure. M19. When an action instruction is based on receipt of an annunciator alarm, the alarm setpoint is identified. B. Control'8 card Compatibility gdd 1. Equipment or instrumentation referenced is available and located where specified. [8 2. Equipment or instrumentation nomenclature either matches control room or local labeling or is consistent with normal operator terminology. /dd3. Unit of measure used in the procedure are the same as those used on control board indicators. M 4. Where sequence of order is not specified or required, equipment is listed in a lef t to right, top to bottom order. Page 6 of 10 (@6530)

,4~,Eq. J' .., p. l 5,p. g.,,,,.,, f. ..l s ,f ?;.;7... ATTACHMENT B i TECHNICAL ACCURACY EVALUATION CRITERIA CHECKLIST E0P TITLE T.:2 w,rA less e G 2am e 8wlad-Sul.culect ecceed Pe'str'd REVISION h ee,/ \\ E0P NUMBER /78CA 5./ tdc 6 ' PERFORMED BY d [hnc DATE f/7 l' I APPROVED BY OATE S -/d-G P V A. Entry Conditions and Symptoms 1. The entry conditions of the E0P are listed correctly. (( [f# 2. The list of symptoms for entry into the E0P is correct. 3. The list of symptoms is not excessive. B. Steos. Cautions and Notes 1. E0P/ ERG discrepancies are documented and exp,lained. 2. The E0P step / cautions / note is technically correct. 3. The ERG technical foundation (strategy) is not changed by the following changes in the development of the E0P. a), elimination b), addition 4. Correct Byron plant-specific information is incorporated into the E0P's (per the ERGS) for: a). systems b). instrumentation c).

limits, 4~

d). controls e). indications 5. Licensing commitments applicable to E0Ps are addressed. 6. Differences between licensing commitments and the E0Ps or ERGS are documented. l Page 7 of 10 .(0654M) l

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. ?.. *. .w,, ATTACHMENT B (Continued) r.. E' C. Quantitative Information 1. The quantitative values, including tolerance bands, used in the EOPs are consistent with the ERGS and licensing commitments. 2. Where ERG values are not used in the E0Ps, the E0P values are computed correctly. 3. When calculations are required by the E0Ps, the equations used ~ supply sufficient information for operator use. D. Plant Hardware 1. The following plant hardware specified in the E0P is available for use: a). equipment b). instrumentation c). controls d). indicators This requirement will be met by performing a plant / control room walk-through as appropriate. 6. P Page 8 of 10 (06$4M)

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f.;<. c' - s ATTACHMENT 0 VERIFICATION STEP CHECXSHEET E0P VERIFICATION Verifier (Written Correctness): b-E0P Y. REV l (WO G I) Verifier (Technical Accuracy): b.- Page 3 of 7 STEP, CAUTION, NOTE-SPECIFIC VERIFICATION WRITTEN CORRECTNESS TECHNICAL ACCURACY STEP NUMBER, DISCREPANCY DISCREPANCY CAUTION OR NOTE ACCEPT 4BLE SHEET # A P BLE SHEET # T9 YA YAA 9h }@h '(MM/. 9c. Mh% TM# to W9 W M/ toa. W Ws 11 k7,b RBL s l{o N // ,t L 'YM ' WA 1:a 'lGWI -KtM is Kaf)A /fI c& T&L M4. 14 'LHL WA s l4a lh> Nb oQb k $/? kc. Wb Wh G-kt W/ LLPs' rL /& 7/M1/ ~ M,- VM MW 15~ Mrs LW/ l(4 N/ N l<b hka bh Q,A(W /M'/ F lWi t\\ n /t 4#'t An w Page 10 of 10 (0654M)

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~ lEY ~.. s. ' i -:... ;. s '- ; ATTACHMENT 0 s; 1 . s. ' VERIFICATION STEP CHEcKSHEET E0P VERIFICATION .s, Verifier (Written Correctness): b-E0P / M'3.l REVdujoC27) Verifier (Technical Accuracy): b-Page ~/ of 7 STEP, CAUTION, NOTE-SPECIFIC VERIFICATION l WRTTTEN CORRECTNESS TECHNICALAbCURACY STEP NUMBER, DISCREPANCY DISCREPANCY CAUTION OR NOTE ACC N A8LE SHEET # ACCE T B E SHEET # u id% la% m 1ss 'ws n is "M/ W4P/ nc 'EGA /MA w WA %L471 94s W/ AAiVA { ([- 34b N 'N7 A 35 hl/ MXA 'U3 /f/X// 2n, YaMG PM. 3L FAtil D!7V/. c m '9&J 'M 23 'La4' HWL? w 2n XML MV/ nk W//// WAG 1 GL 3.u-t 'KM/- MV// F L 3.1-2 WAfi Ed dif fM 3.1-3 h(( N i k+r D A iMA AA9 afsJLee ffdAI TR A faAk %W /e49 a( r Page 10 cf 10 (0654M) i.

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• 2084K

t-9 t ,\\. BYRON EOp STEP DEVIATION DOCUMENT - BY/BW V&V PROG Procedure No: IBCA-3.1 R'ev: 1. WOG1

Title:

SGTR with LOCA i _ - - _ _ Subcooled Recove v Desired Writer: E. Cope Date: 6/24/85 Page 1 of 2 Byron ERG-Step No. ' Step No. ' CHANGE DESCRIPTION REASON FOR CHANGE

1. 1 Caution #1 Caution Changed RWST setpoint frc:a "45V See BEP-1 Step 14a Step 1 Step 1 to "46%"

deviation

1. 2 Note Note Deleted Note on Foldout Page See BEP-0 Step 1 Step 1 Step 1 deviation 1 AER RNO 1 Revised Steps on " RESET SI" See BEP-0 Step 36 deviation 3b-(2) 3b RNO Added - Non-running See BEP ES-0.1 Step 9b RNO (2) deviation Notes 10 Revised sequence of notes Standardize with other Step 9 Notes 1, 2, 3 & 4 procedures become 3, 2, 4, 1 New Note 3 10 Reworded note to. state - If Revised step is more Step 9 Steam Dumps are opened rapidly, meaningful and old note with PZR pressure greater than will.be covered in 1930 psig. Main Steamline training Isolation will occur from Low Steamline Pressure SI New Note 3 10 Added "As Time Permits" See BEP ES-1.2 Step 6 Step 9 deviation 10a AER 11 Reworded substep to include See BEP-0 Step 29a RNO both means of checking RCS deviation L

subcooling in AER column 11b (RNO) 12b (RNO) Changed " Plant Engineering Plant Specific Staff" to "TSC" Terminology

1. 1 Caution Caution Deleted - RCP seal and bearing Statement is not part Step 15 Step 15 disassembly may be necessary of ERG caution prior to restart 15b (AER) 16b (AER) Reworded - See Step 10a (AER)

See Step 10a (AER) (RNO) (RNO)

1. 2 Note l'1 Changed wording "SE" to "TSC" Plant Specific Step 16 Terminology 16c (AER) f7 See Step 10a (AER)

See Step 10a (AER) 4 (0110E)

-) BYRON EOP STEP DEVIATION DOCUMENT - BY/BW VEV PROG Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

SGTR with LOCA Subcooled Recovery Desired-Writer: E. Cope Date: 6/24/85 Page 2 of 2 Byron ERG Step No.

• Step No. '

CHANGE DESCRIPTION REASON FOR CHANGE 16e (1) - Changed wording " Check" to Verify implies for (AER) " Verify" operator to open valves (RNO) if necessary 17c (AER) l7 See Step 10a (AER) See Step 10a (AER) 18d (AER) l1 See Step 10a (AER) See Step 10a (AER) 19d (AER) gg See Step 10a (AER) See Step 10a (AER) 20 22 Added - GREATER THAN 4% (38% Provide operator with a FOR ADVERSE Claff) PZR level to maintain 220 (AER) 24c (AER) See Step 10a (AER) See Step 10a (AER) 24a (AER) 26a (AER) See Step 10a (AER) Sep Step 10a (AER). (RNO) (RNO) 28 30 Reversed sequence of substep See BEP ES-1.1 Step 19 a&b deviation 28a (RNO) 30 Reworded step - Adjust ICV-lC2 Plant Specific as necessary to establish seal Terminology injection ficar 35b (AER) 35b (AER) Changed " Plant Engineering Plant Specific Staff" to "TSC" Terminology 37b (AER) 37b (AER) Same as Substep 35b (AER) See Substep 35b (AER)

i-(0110E)

G .i: BYRON EOP STEP DEVIATION DOCUMENT - BY/BW V&V PROG Procedure No: IBCA-3.1 Rev: 1. WOG1

Title:

Operator Action Sununary SGTR with LOCA Subcooled Recovery Desired Writer: E. Cope Date: 6/24/85 Page 1,of 1 Syron ERG Step No. ' Step No. ' CHANGE DESCRIPTION REASON FOR CHANGE CST LEVEL Changed to read - Prepare to Better meaning of action <20%: isolate secondary side of 3 SGs sununary RED PATH Changed to read - Heat Sink - See BST-3 Heat Sink SUIORRY All SGs NR <4% (34% ADVERSE deviation CIGff) and total AF <500 GPM AVAILABLE Go to Change RWST setpoint from "4%" See BEP-1 Step 14a IBEP ES-1.3 IF: to "46%" deviation t l l

6. -

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ar* - G ITiet 5 - ON-SITE REVIEW DEFICIIDICIES 2084K

~. BYRON E0P STEP DEVIATION DOCUMENT - BY/BW OSR Procedure No: IBCA-3.1 Rev: 1, WOG1

Title:

SGTR with LOCA Subcooled Recovery Desired Writer: E. Cope Date: 8/5/85 Page 1 of 2 Byron ERG Step No. ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE 2 2&3 Revised substeps to allow check Instrument air system of SAC before opening instrument presure must be air containment isolation valves adequate before supplying conponents inside containment.

1. 2 Caution Changed note to caution statement on PZR Step 3 heaters'more applicable to a caution.

7a (RNO) 8a (RNO) added - "per 18EP-2 FAULTED kickout to 18EP-2 is STEAM GENERATOR ISOLATION. appropriate since this STEP 1 procedure more aptly describes how to iddntify and isolate faulted SG(s). ~

1. 3 Note added --When PZR pressure statement is included Step 9 decreases to less than 1930 to be consist'ent with PSIG, Low Steamline Pressure ERG.

SI should be blocked. 16a (AER) Changed to read - "INIECTING TO changed allows for RCS COLD LEGS lineup during both injection and recire phase 16c (AER) deleted figure 1BCA 3.1-1 not required due to Attachment A revision 17c (AER) deleted figure 1BCA 3.1-1 same as 16c (AER) 18d (AER) deleted figure 1BCA 3.1-1 same as 16c(AER) 19d (AER) deleted figure 1BCA 3.1-1 same as 16c (AER) 28b (AER) 30 (AER) Revised listing of RCP CC procedure consistency System Flow annunciators 29a (AER) 31a (AER) added additional requirement insure adequate back-of proper VCT pressure before pressure on #1 seal establishing RCP seal return flow. Figure 1BCA 3.1-3 added " EXPECTED REGION" to graph clarification of figure (0110E)

BYRON E0P STEP DEVI'ATION DOCUMENT - BY/BW OSR Procedure No: IBCA-3.1 Rev: 1, WOG1~

Title:

~SGTR with LOCA ~ Su'bcooled Recovery Desired Writer: E. Cope Date: 8/5/85 Page 2 of 2 Step No.. ERG Byron ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE Attachment A Step B.2 --added figure adding figure provides 1BCA 3.1-1 more pertinent information ong checking required RCS subcooling. Operator Action Summary SI REINITIATION:

1) added to PZR level - "CANNOT to be consistent with BE MAINTAINED ERG RED PATH

SUMMARY

1) Heat sink - changed to read to be consistent with "all SGs NR <4% (34% FOR ERG ADVERSE CNMT) AND TOTAL FEEDWATER FLOW <500 GPM AVAILABLE

2) Integrity - change to read to be consistent with DECREASE >100*F IN LAST ERG 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F S

2. -

l (0110E)

U* 4 4 ITIDI 6 - TRAINIW CHAME DOCUfENTATION 2084K

i &b BYRONEOPSTEPDEVIATIONDOCUMENT(OPERATORTRAININGREV.1WOG T ,g Procedure Nc: IBCA-3.1 Rev: 1A WOG1

Title:

SGTR with LOCA - A Subcooled Recovery Desired rf y Writcc: E. Cope Date: 3/24/86 Page 1 of 2 eta'II p Byron ERG gr.p P J ep No. ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE 44' p,f gp-v 'M9, 2d (AER) 2 (AER) Deleted step To allow for auto switchover of RWST 34, b% during a LOCA condition. New 2d 3 (AER) Change same as 1BEP-0 b/A *>*6 i (AER) Step 37d (RNO) 3b 1) & 4 (RNO) Change same as IBEP ESO.1 E4,-/A M 8 3b 5) & Step 9b 1), 9b 5), & 9b 6) (RNO) 3b 6)(RNO)

1. 2 Caution Change same as IBEP-1 ht A Wod-l Step 4 Step 5
2. 2 Caution Step 8 4b (AER)

Sb (AER) Change same as 1BEP-1 Ak'd Wod "# 4b (RNO) 5b (RNO) Step 4b (AER) (RNO) 8b (AER) 9b (AER) Change same as IBEP-0 ft -/A W86*/ Step 32b (AER) Note 4 & 5 Split out note 4 of Rev. Itvo6-1 See change on Step 9 Step 9 into two separate notes 1BEP ESI.2 Step 6 6-/A a'ed-/ 9c 2)(AER) 9c (AER) Change same as IBEP-0 SW/A wad-/ Step 23a (RNO) lla (RNO) 12a (RNO) Change from "CNMT sump level" R6 quired indication to "CNMT floor water level" 15d 1) 16d (AER) Change same as IBEP ESO.1 As,-/A Wod-/ (AER) Step lla (RNO)

1. 3 Note Change "TSC" to "SE" Byron operating staff Step 16 Step 17 perference 16b (AER)

Change same as 1BEP ESl.2 S,-/A wa4-/ Step 12b (AER) 16e 5(AER) Change same as 1BEP ESl.2 /24,-/4 &#6-/ 16e 6(AER) Step 12e 5) (AER) Step 12e 6) (AER) 17b (AER) Change same as IBEP ESI.2 &/4 W/'/ Step 13b (AER) (01'10E/0011E)

\\ N BYRON EOP STEP DEVIATION DOCUMENI OPERATOR TRAINING REV. 1 WOG-1 Procedure No: 1BCA-3.1 Rev: 1A WOG1

Title:

SGTR with LOCA Subcooled Recovery Desired Writer: __ E. Cope Date: 3/24/86 Page 2 of 2 Byron ERG Step No. ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE 18c (AER) Change same as 1BEP ES1.2 priA W Step 15c (AER) 19c (AER). Change same as 1BEP ESI.2 fr/A M6"/ Step 15c (AER) 21a (RNO) 23a (RNO) Changed to the following

1) Subcooling and PZR

1) Check RCS subcooling level required by ACCEPTABLE using:

ERG's o ICONIC DISPLAY

2) Change procedure

-OR-kickout to BOP RC-1, o ATTACHMENT A, STEP A AND STARTUP OF AN RCP. FIGURE IBCA 3.1-1 Caution Change same as 1BEP ESO.2 Sc/A 8W-/ Step 22 Step 17 Caution 28 (RNO) 30 (RNO) Change same as IBEP ESO.2 fu-/4 @4-/ Step 19a (AER) 30a (AER) 32 (AER) Change same as IBEP ESO.1 M /A M '/ s (RNO) (RNO) Step 12a (AER) 31c (AER) 33 (AER) Change same as IBEP ESO.1 er-M #/ 31e (AER) Step 14 c (AER) 33a (RNO) 35a (AER) Change same as IBEP ESO.1 /* /A W# U b (RNO) Step 14c.2 (RNO) Figure Change same as 1BEP-0 M 'A W##-/ 1BCA 3.1-1 Figure 1BEP 0-1 RL'S Subcooling Margin C. - (0110E/0011E)

i BYRON EOP STEP DEVIATION DOCUMENT (OPERATOR 'ERAINING REV. A WO procedure No: IBEP-0 Rev: 1A WOG 1

Title:

RX Trip or Safety Injection Writer: E. Cope _ Date: 3/24/86 Page 1 of 3 Byron ERG Step No. ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE 2 (RNO) 2 (RNO) Changed entire step to read the Operator request for same as IBFR S.1 Step 2 (RNO) procedure consistency 3b (RNO) 3b (RNO) Added..." while continuing with Procedure step this procedure clarification 4 (RNO) 4 (RNO) Revised step to include -OR-Procedure usage 0 logics consistency 4 (AER) 4 (AER) Deleted the work "ALL" from Not all Group 2 monitor second statement on Group 2 lights are associated Cold Leg Injection Monitor with Cold Leg Injection lights 8a (AER) 12 (AER) Changed from " Dampers" to Byron /Braidwood plant " Valves" specific tereinology 14a (AER) 14 (AER) Added pressure instruments and Provide instrumentation recorders for CS for operator use Caution Changed wording from..." of Statement clarification Step 20 SG Narrow Range Indication to..." For Any SG Narrow Range l Indication". 23a (RNO) 19 (RNO) Added to second contingency a This step added to ne'w substep 2) to state place insure when steam dumps steam dump pressure controller are placed in the STEAM in manual and reduce demand PRESSURE mode, the dump signal to zero valves will not inadvertently open causing repid decrease in steam pressure which could lead to possible closure of main steam isolation valves. 23a (RNO) 19 (RNO) Added to substep 4 of second Provide operator with contingency step the following maximum allowable ... rate /less than 50*F/He cooldown rate for the condition. (0130E/0013E) .o# l _8 : n ,9 w,.

- ~ \\ ) BYRON EOP STEP DEVIATION DOCUMENT OPERATOR TRAINING REV. 1 WOG-1 ^ Procedde No: IBEP-0 Rev: 1A WOG 1

Title:

RX Trip or Safety Iniection Writer: E. Cope Date: 3/24/86 Page 2 of 3 Byron ERG Step No. ' Step No. CHANGE DESCRIPTION REASON FOR CHANGE 24a (RNO) 20a (RNO) Changed from 2335 PSIG to 2315 PSIG is the reset 2315 PSIG setpoint fo* the PZR 1 PORV's and is the proper pressure requirement to insure PORV's are closed. Note NotoO Change from a " Note" to Caution statement are Step 25 Step 21 " Caution" required when equipment damage may occur. In this case, RCP's may'be ~ damage due to possible over heating 29b (RNO) 25d (RNO) Deleted..." try to stabilize Byron /Braidwood air RCS pressure with normal PZR system may not be spray adequate to allow fcr use of spray valves j without reseting Phase A which cannot be done at this time 1 32b (AER) 28b (AER) Changed from "between 4% and Byron /Braidwood Unit 1 50%" to "between 4% and 66%" SG program level is 66%. This is a more reasonable level to attempt to maintain and coincides with the WOG reference plant program level of 50%. 1st Changed from " RESET" to " CYCLED" Rx trip breakers must be Caution cycled closed then open Step 36 Step 32 vice reset. 37d (RNO) 34 (RNO) Changed from..." start one SAC The SAC should be per 0B04 SEC-9 to... start one capable of starting SAC per BOP SA-1. under normal conditions. OBOA SEC-9 address starting during abnormal condition for SAC. (0130E/0013E) .m ~. ..e g ..N M 'l ' f f O J ', ' _ i-. 1- - n ""~-~ ~ ~ ~ ~ '

\\ BYRON EOP STEP DEVIATION DOCUMENT OPERATOR TRAINING REV. 1 WOG-1 t Procsdure No: IBEP~-0 Rev: lA,WOG 1

Title:

RX Trip or Safety Iniection Writer:, E. Cope Date: 3/24/86 Page 3 of 3 Byron ERG _ Step No.__' Step No. CHANGE DESCRIPTION REASON FOR CHANGE Figure 1BEP 0-1 Changed curves to reflect new Westinghouse revised RCS data on core eixt TCs accuracy of cors exit Subcooling TC's from i 23.8'F for Margin both normal and adverse CNMT to il4.5'F for normal OttT and 145.2*F for adverse CNMT + 1 4 e t l 9 ' (0130E/0013E) l l l l l "P. ~ ' t. ' 'l ? $ .[. ,._e . = - ,-,- 3 . " '

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• O 6

ITM 7 - TRAINING OUufGE VERIPIGTIN l l l 2084K

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• 1..1 '..x, h ^ a::

ATTACHMENT A WRITTEN CORRECTNESS EVALUATION CRITERIA CHECKLIST E0P TITLE SCTR k*ilu t wc / ~kscic,2 cw s., x t - nacec.sm g eto,we g pc,,,e c- 0 EOP NUMBER /[lCA '3-REVISION I A 1:a / PERFORMED BY Ndde DATE ~7 - / 7-T6 APPROVED BY hd DATE M2 *M I. Procedure - General A. Format and Style M7 1. Printed borders are visible on all procedure pages. /'N 2. The text, tables, figures and graphs are legible. $8 3. The general format of the procedure is censistent with the Byron Emergency Procedure Writers Guide (i.e., dual column fo'rmat, page layout ard required sections are present per Writers Guide). b 8 4. Procedure contains all its pages in the correct order with correct procedure number, titles and page numbers on each page. hd 5. " Step continued on next page", typed at the bottom of each page where required. / 'I 6. The last page clearly identified by the word -END. [#T 7. Each page contains the correct revision number. N 8. Attachments are labeled with number and title. s / 4 9. The title is descriptive of the purpose of the procedure. II Step - Specific A. Format and Style t l M8 1. Steps are numbered correctly. M O 2. Nonsequential substeps are designated with bullets. /b'?/ 3. Steps deal with only one idea. 68 4. Steps are short with ambiguous words and phrases avoided. Sfi 5. The tests stipulates precisely what actions or decisions are required. I Page 5 of 10 (0654M)

. x.Q.' ' '.3 :.;

• .c :l'. ' :J:

J C .c ,,r ATTACHMENT A (Continued)- h 6. If there are more than two actions or objects in a step, they are listed separately. N 7. Punctuation conforms with standard American English usage. [ N 8. Capitalization conforms with standard American English or with specifications for emphasis in Writers Guide. 9. Only abbreviations, acronyms and symbols appearing in the Writers Guide and Byron Administrative Procedure, Conventions, Definitions and Approved Station' Abbreviations (BAP 1310-T2) should be used. h 6 10. Instruction steps make proper use of logic structure, h 8 11. CAUTION statements are emphasized to standout from the text and precede NOTE statements for the same step. 'h N 12. CAUTION and NOTE statements avoid action steps. N'8 13. CAUTION and NOTE statements (where required) precede the applicable step (s). / 14. Formulas and calculations are minimized. Where calculations are necessary, space is provided. 15. Referenced procedures are identified by both title and number. h616. The use of referencing other procedures is minimized and is used only to eliminate excessive detail. [/d 17. The instructions " refer to" and "go to" other procedures are used correctly and avoid routing user past important information such as cautions preceding steps. h 18. Exit conditions are compatible with the entry conditions of l the referenced procedure.

19. When an action instruction is based on receipt of an annunciator alarm, the alarm setpoint is identified.

+. B. Control Board Compatibility ~ [M6 1. Equipment or instrumentation referenced is available and j located where specified. [/[ 2. Equipment or instrumentation nomenclature either matches control room or local labeling or is consistent with normal operator terminology, f d 3. Unit of measure used in the procedure are the same as those used on control board indicators. 4. Where sequence of order is not specified or required, equipment is listed in a lef t to right, top to bottom order. Page 6 of 10 (0654M)

.~ .,3 t ,,;V. . hj:.. ,- ; f. .) ATTACHMENT B TECHNICAL ACCURACY EVALUATION CRITERIA CHECKLIST E0P TITLE S*G 7/t 0:rru L6s> ci tctiscron cost.t.c r -J'udCcetG~O llc'Cc In Y W > M c'O E0P NUMBER / /K / - 7 / REVISION I.4 h.<-1 PERFORMED BY /

1. d,c DATE 7-/b T4 APPROVED BY O

DATE ?/ 2"/A A. Entry Conditions and Symptoms 1. The entry conditions of the E0P are listed correctly. /$9 2. The list of symptoms for entry into the E0P is correct. [M 3. The list of symptoms is not excessive. B. Steps, Cautions and Notes /')L7 1. E0P/ ERG discrepancies are documented and explained. hl[ 2. The E0P step / cautions / note is technically correct. /hdf3. The ERG technical foundation (strategy) is not' changed by the following changes in the development of the E0P. a). elimination b). addition /I64. Correct Byron plant-specific information is incorporated into the E0P's (per the ERGS) for: a). systems b). instrumentation c). limits d). controls N' e). indications /'If 5. Licensing commitments applicable to E0Ps are addressed. /WI 6. Differences between licensing commitments and the EOPs or ERGS are documented. Page 7 of 10 (0654M)

. v. c, s .j ATTACHMENT B (Continued) C. Quantitative Information /$57 1. The quantitative values, including tolerance bands, used in the [# EOPs are consistent with the ERGS and licensing commitments. $94 2. Where ERG values are not used in the E0Ps, the E0P values are computed correctly. 21/d2 3. When calculations are required by the E0Ps, the equations used supply sufficient information for operator use. D. Plant Hardware [NGS1. The following plant hardware specified in the E0P is available for use: a). equipment b). instrumentation c). controls d). indicators This requirement will be met by performing a plant / control room walk-through as appropriate. Oi-I Page 8 of 10 (0654M)

~ ^ ' ' %'l +,' - : N ~,' ..;s ' %)L.,, 0.y. * * ' ', -) ATTACHMENT D VERIFICATION STEP CHECKSHEET IOP VERIFICATION (v c 6 -I Verifier (Written Correctness): [N Olb ECP / 06'# 3 I 'REV /-i Verifier (Technical Accursey): C Page / of 1 STEP. CAUTION. NOTE-SPECIFIC VERIFICATION WRITTEN CORRECTNESS TECHNICAL ACCURACY I STEP NUMBER, DISCREPANCY DISCREPANCY CAUTION OR NOTE ACCEPTABLE SHEET # ACCEPTABLE SHEET # ,.2 / / 3 / / c... u. v u s.,- / / e c. nu 4 V V l 7 +f~3.% / M + 3.I-I ee, v r*it ee c r e. o 9 t/ t, 9 V / ll If t/ ,e a.-v rit t..e re

1. l&

V / c. rf V /7 f. / I7 / / (9 ./ / 2I / t/ c 4. r,s y r, o ,6 [ To a 2 :2 l l f ,f 3o r/ t/ 3I ff V 32 t/ t/ 33 V V f / G 15O 3. ) - I f. / f/l-15(.L 3.1 - L ./ ,/ i:tf-th'i 31-3 V / l1<l (/ t/ Page 10 of 10 0137E(0305S5) I A i

,, w., A s., ':l : s,;, ' - a:.- ATTACHMENT D VERIFICATION STEP CHECKSHEET EOP VERIFICATION Verifier (Written Correctness): (( (('L'd E0P //7(I 3 I ~ /./ RE N[b Verifier (Technical Accuracy): P858 2 of 2 STEF. CAUTION. NOTE-SPECIFIC VERIFICATION WRITTEN CORRECTNESS TECHNICAL ACCURACY STEP NUMBER, DISCREPANCY DISCREPANCY CAUTION OR NOTE ACCEPTABLE SHEET # ACCEPTABLE SHEET # 2? ,/ / s' ~.,. u., taar y t rr B / %.,,. 1,, <2 (1 / O CA,. 3 e-4 l d. l 0137E(030585) A

ITEM 8 - IBcA 3.1, REVISION 1A, WOG-1 2084K

Q REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 A. PURPOSE This procedure provides actions to cooldown and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory and voiding in the RCS. B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from:

1. 1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 3, if a ruptured SG cannot be isolated from any intact SG.

2. 1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 5, if PZR PORV cannot be isolated by closing its isolation valves. IBEP-3, STEAM GElr"RATOR TUBE RUPTURE, Step 12, if the ruptured

3. SG pressure is less than low steamline pressure SI setpoint.

l

4. 1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 13, if no intact SG is available for RCS cooldown.

IBEP-3, STEAM GENERATOR TUBE RUPTURE, Step 14, if the ruptured f

5. SG pressure continues to decrease following RCS cooldown.

6. 1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 15, if subcooling is less than acceptable value. 1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 18 if RCS pressure

7. does not increase after closing PER PORV and isolation valve.

1BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 19, and 1BCA-3.3, S. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 7, if SI can not be terminated.

9. 1BEP ES-3.1, POST-SGTR COOLDOWN USING BACKFII.L, Step 2, 1BEP ES-3.2, POST-SGTR COOLDOWN USING BLONDOWN, Step 2, and 1BEP ES-3.3, POST SGTR COOLDOWN USING STEAM DUMP, Step 2, if SI accumulators should not be isolated.

10. 1BEP ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 5, 1BEP ES-3.2, POST-SGTR COOLDOWN USING BLONDOWN, Step 5, and Step and 1BIP ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 5 15, and Step 15, if a non-ruptured SG is not available for RCS cooldown.

APPROVED MAR 241986 B. O. S. R. (0110E/0011E)

t REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1

11. 1 BEP-3, SGTR Unit 1, Step 23, and 1 BCA-3.3 SGTR WITHOUT PRES 8URIZER PRESSURE CONTROL, Step 7 and 10 if ECCS flow is required.

12. 1 BCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 21, if RCS pressure is less than technical specification for the maximum SI accumulator nitrogen pressure.

l APPROVED MAR 24 586 B. O. S. R. (0110E/0011E)

b REV. lA OPERATOR ACTION

SUMMARY

WOG-1 FOR 1BCA-3.1 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECC8 pumps as-Close ICV 8110, ICV 8111 necessary J.E either: o RCS subcooling - NOT AX:EPTAR" RCS pressure < 1370 PSIG (<-1670 PSIG ADV'**E CNMT) VALFJE FROM IMIC DISPJLY OR -AND-ATTICrmas 1 A, arar A AlfD SI actuated FIw aB IBCA 3.1-1 Open ICV 8110, ICV 8111 -OR-o PER level - CANNOT BE RCS pressure > 2000 PSIG MAINTAINED >44 (38% FOR ADVERSE CNMT) RED PATH

SUMMARY

1. suberiticality - NUCLEAR CST LEVEL < 201:

POWER > 54 o Crosstie unit CSTs

2. Core cooling - CORE EXIT o

Makeup from MUDS or TCs > 1200*F radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cocidown rate 134% FOR Auv- ** CNMT) AND Prepare to isolate secondary ivinL s- -9TER FLOW (500 o of 3 SG Gan AVAILABLE

4. Integrity - DECREASE >100*F CST LEVEL RFACHES 31:

IN LAST 60 MIisvrma AND RCS 1. Verify secondary side of COLD LEG innr _-ATURE <246*F 3 SGs isolated,

5. Containment - CNMT 2.

Switch AF suction to SX PRESSURE > 50 PSIG G5 TO 1RF 3 2 IF ANY U l Ivi ArE ) SG; Uncontrolled pressure o l decrease -oR-o completely depressurized MILESS needed for cooldown GO TO 15EP ES-1.3 IF: l l RNET level g_4,ig (0110E) APPROVED l MAR 241986 B. o. S. R.

i REY. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED e.............................. CAUTION IF RWST LEVEL DECREASES TO LESS THAN

• 46%, THE ECCS SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING 1 BEP ES-1.3, TRANSFER TO COLD LEG l

RECIRCULATION. I nemeneseeeeeeeeeeeeeeeeeeeeeeeeemenemenen mennesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. n..................... ennenemoneensenemmenneemannseenen........ e NOTE With procedure in effect, notify the

• Station Director who will evaluate for GSEP condition per BZP-200A1.

mammenomanneenneeeeeeeeeeeeeeeeemeenneene 1 RESET SI:

a. Depress both SI reset

a. IF SI reset can NOT pushbuttons be verified, THEN reset SI per

b. Verify SI ACTUATED 1 BOA PRI-5 CONTROL ROOM permissive light - NOT LIT INACCESSIBILITY.

c. Verify AUTO SI BLOCKED permissive light - LIT APPROVED MAR 241986 Page 3 of 34 (0110E/0011E)

B. O. S. R.

h REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 l l i SI REINITIATION: CFNT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as Close ICV 8110, ICV 8111 necessary II either: i e RCS pressure < 1370 PSIG l o RCS subcooling - NO" AGlEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC DMSFAY OR -AND-ATTACHMENT A, STEP A AfD SI actuated FIGURE ISCA 3.1-1 ODen ICV 8110, ICV 8111 -OR-- e RCS pressure > 2000 PSIG i o PZR level - CANNrff BE l MAINTAINED >4% (: 8% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Suberiticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR <4%

o Tsduce cocidown rate C344 FOR ADVERSE CNPT) AND o Prepare to isolate secondary

vim. ramuwATER FLot' < 500 of 3 SG GPN AVAILABLE

4. Integrity - DECREASE >100*F CST LEVEL REACHFS 31:

IN aST 60 MINUTES AND RCS COL) LEG TEMPERATURE (246*F 1. Verify secondary side of 3 SGe isolated

5. Containment - CNMT PRE 88URE > 50 PSIG 2.

Switch AF suction to SX Ce TB 'RF3 2 IF ANY U l Ivi st) SG: o Uncontrolled pressure decrease -OR-o Completely depressurized U4LE88 needed for cooldown 00 'EO 15EP E8-1.3 IF: l e RNST level < 46% I 1 I (0110E) l APPROVED i 1 MAR 241986 B. O. S. R.

i

t L 4 ? f REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT O8TAINED 2 RESET CONTAINHENT ISOLATION:

a. Reset CNMT Isolation Phase A

a. Roset per 1 BOA PRI-5 i

CONTROL ROOM } INACCESSIBILITY.

b. Reset CNMT Isolation Phase B

b. Roset per 1 BOA PRI-5 CONTROL ROOM INACCESSIBILITY.

I

c. Reset CNMT Ventilation Isolation ll d, Check SAC run lights - ANY LIT

d. Start one SAC per BOP SA-1 STARTUP OF A SAC.

e. Open instrument air containment isolation valves e

11A065 IIA 066 f~. Open service air containment isolation valves t 1SA032 1SA033

g. Open fire protection containment isolation valve l

IFPG10 l l l l f I\\ i APPROVED MAR 241986 (0110E/0011E) B. O. E R.

.-. c 1 a 4 +5 i REY. lA OPERATOR ACTION

SUMMARY

'1ECA 3 1 WOG-1 FOR 1BCA-3.1 .s I \\ SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as - necessary _I.Z either: Close ICV 8110, ICV 8111 RCS subcooling - NOT ACuwraBLE RCS pressure < 1370 PSIG o (< 1670 PSIG ADVn32 CNMT) VALFJE FROM IrNIC DISPLAY OR ATTM'imama-A, Siza A AND -AND-FIwas 1BCA 3.1-1 SI actuated _ s Open ICV 8110, ich8111 -OR-o PZR level - CANNOT BE RCS pressure i 2000 PSIG e MAINTAINED >4% (38% FOR ADVERSE Gma) RED PATH St"JtY:

1. Subcriticality - NUCLEAR CST LEVEL < 201; POWER > 54 o

Crosstie unit CSTs

2. Core cooling - CORE EXIT TCs > 1200*F o

Makeup from MUD 4 or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rata C34% FOR ADif -" CNMT) AND Prepare to isolate secondary \\ o i vrAL s-- - ' 'ER FLM < 5 0 0 of 3 SG own AVAIL *J CST LEVEL REACHER 31:

4. Integrity - DECREASE >100*F IN LAST 60 MIhvad AND RCS i

Verify secondary side 'of COLD LEO TEMP M.TURE <246*F 1. i 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PGIG 2.

Switch AF suction to SX 30 TO ' RF 3 2 IF ANY ( UA Ivi HTE1 Sfal s o Uncontrolled pressure decrease -OR-I' e o-Completely depressur.ized tarLESS needed for cooldown GO TO 1BIP ES-1,3 IF: i 4 e RNST level < 414 (0110E) l APPROVED l MAR 24 886 B. O. S. R. - - ^

s REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED semeeeeeeeeeeeeeeeeeeeeeemmeneesessmenee. CAUTION DO NOT EXCEED DIESEL GENERATOR LOADING REQUIREMENTS: o 5500 KW CONTINUOUS DUTY S 954 AMPS

• MAXIMUM.

o 5935KW CONTINUOUS FOR 2000 HOURS 4 1030 AMPS MAXIMUM. o 6050 KW CONTINUOUS FOR 2 HOURS 4 1050 AMPS MAXIMUM. 'l memenemmensammenneenemmenneesessenemannee seeeeeeeeeeeeeeeeeeeeemenesessen......... CAUTION PZR HEATERS SHOULD 3E LOADED ON ONLY

• ONE ESF BUS.

OTHER NON-ESF LOADS SHOULD BE LOADED

• ON OPPOSITE ESF BUS.
• emeenemmenenemmenemenenseeeeeeeeeeeemene 3

VERI:Y Al L AC BJSSES ENERGIZED BY OFFSIT E 10WE t:

a. ESF 4KV Busses:

a. Try to restore power to ESF busses with offsite power.

e SAT 142-1 Bus Alive Light - LIT H offsite power can NOT i e ACB 1412 - CLOSED be restored, e SAT 142-2 Bus Alive THEN notify System Light - LIT Load Dispatcher of e ACB 1422 - CLOSED existing conditions so an emergency AC restoration program can be implemented. E necessary, THEN verify the following equipment loaded on the ESF busses as applicable: Step continued on next page APPROVED L MAR 241986 (0110E/0011E) B. R. ce* -~ -,--we_v .w w w m----*m-----w---cwrwg cv w~nmw'-%-+w+vyw+- -'-'--M'v -x---m=-- wm--

REY. lA OPERATOR ACTION

SUMMARY

-1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CFNT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary Il either: e RCS pressure < 1370 PSIG o RCS subcooling - N7T ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VAI.UE FROM ICONIC :)ISPLAY OR -AND-ATTACHMENT A, STEP A AND SI actuated FIGURE IBCA 3.1-1 Open 1CV8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG MAIN'I'AI"" > 4 % ( : 8% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Suberiticality - NUCLEAR POWER > 54 CST LEVEL < 701:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radwaste

3. Heat sink - JLL SGs NR (4%

o Reduce cooldown rate f34% FOR ADV ISE CNPT) AND o Prepare to isolate secondary OTAL FEEDNA' 'ER FLCt ' < 500 of 3 SG GPM AVAILABL l

4. Integrity - DECREASE >100*F CST LEVEL REACHFC 31:

IN LAST 60 MINUTES AND RCS COLD LEG unrzmATURE (246*F 1. Verify secondary side of 3 SGs isolated,

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX 1"i TO 'RF3 2 IF ANY J dI m nitj SG: o Uncontrolled pressure decrease -OR-o Completely depressurized UNLESS needed for cooldown 00 TO 1EEP ES-1.3 IF: e RNST level $_4fl (0110E) APPROVED MAR 241986 B. O. S. R.

T REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 i ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED o CENT CHG pumps o SI pumps o RH pumps l o Control Room Chiller Unit I o CS pumps o CC pumps o SX pumpe I o AF pump 1A l o 480 volt ESF buses

b. NON-ESF 4KV Busses:

b. IF offsite power can NOT be promptly restored, SAT 142-1 Bus Alive Light -

THEN establish necessary e LIT NON-ESF loads to maintain e ACB 1432 - CLOSED plant conditions. SAT 142-2 Bus Alive Light - o LIT e ACB 1442 - CLOSED

1) Verify locally all breakers on Bus 143 and 144 - OPEN.

2) Pull-to-lock all non-running WS pumps.

3) Energize Bus 143 and 144 from ESF cross-tie breakers.

4) Open all 480 volt transformer LOW side breakers associated with Bus 143 and 144.

Step continued on next page l I i APPROVED 1 MAR 241986 (0110E/0011E) B. O. S. R. 1.

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary J,.g either: RCS pressure < 1370 PSIG e o RCS subcooling - M ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VAL 1JE FROM ICONIC DISPLAY OR -AND-ATTAcrmr. A, om A AND SI actuated FIG;RE IBCA 3.1-1 Onen ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAIN'Pm" Det (38% FOR RED PATH

SUMMARY

4 ADVERSE CNNT)

1. Suberiticality - NUCLEAR POWER > 5%

CST LEVEL < 701:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or

3. Heat sink - ALL SGs NR <4%

radweste i34% FOR ADV 3SE CNMT) AND o Reduce cooldown rate "OTAL r-- A TR FLOW <500 o Prepare to isolate secondary of 3 SG GPM AVAILABIJ :

4. Integrity - DECREASE >100*F CST LEVEL REACHF9 31:

IN "AST 60 MINUTEa, AND RCS ML) LEG TEMPERATt.RE <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX O TO 'RFS 2 IF ANY U i Ivil dTE) SG: o Uncontrolled pressure decrease -OR-o Completely depressurized UNLESS needed for cooldown GO TO 1BIP ES-1.3 IF:

• RNST level < 464 l

l (0110E) APPROVED 1 MAR 241986 B. O. S. R. 1

P REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

5) Re-energize PZR heaters:

a) Close 4160 volt PZR heater transformer's HIGH side breakers i' at 1PM01J. I b) Close 480 volt PZR heater transformer's LOW side breakers at IPM05J. c) Operate PZR heater controls as needed to control syst o pressure.

6) Start a station air compressor per BOP SA-1 STARTUP OF A SAC if necessary.

7) Energize other NON-ESF loads as necessary,

c. 6.9 KV Busses:

c. Try to restore power to busses with offsite power.

e SAT 142-1 Bus alive light - LIT IF offsite power can NOT e ACB 1572 - CLOSED be restored, e ACB 1592 - CLOSED THEN notify System Load e SAT 142-2 Bus alive Dispatcher of existing light LIT conditions so an emergency e ACB 1562 - CLOSED AC restoration program can e ACB 1582 - CLOSED be implemented. IF outside air temperature less than 40*F, THEN start SX make-up pumps OA and 08. l APPROVED MAR 241986 (0110E/0011E) B.O.S.R.

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary II either: e RCS pressure < 1370 PSIG o RCS subcooling - WW ACCEPTASLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC 3ISPLAY OR -AND-ATTM30ENT A, STEP A AND SI actuated FIGURE 18CA 3.1-1 ODen ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 701:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - JLL SGs NR <4%

o Reduce cocidown rate C34% FOR ADV RSE CNMT) AND o Prepare to isolate secondary "0TAL FEIDNA' ER FLON <500 of 3 SG GPM AVAILASLl ;

4. Integrity - DECREASE >100*F CST LEVEL REACHFR 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary side of 3 SGe isolated

5. Containment - CNMT 1

PRESSURE > 50 PSIG 2. Switch AF suction to SX E TC ' RF 3-2 IF ANY h IVf HTE) SG: I c o Uncontrolled pressure decrease_og_ l .o Completely depressurized UNLI58 needed for cocidown GO TO 1BEP ES-1.3 IF: e RNST level < 46% l (0110E) APPROVED MAR 241986 B. O. S. R.

I i REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 l WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 l ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeetenemmene CAUTION NaOH ADDITION TO THE CONTAINMENT SPRAY SYSTEM MUST BE TERMINATED WHEN

• j SPRAY ADDITIVE TANK LO-2 LEVEL LIGHTS ARE LIT.

i menenemoneeneenseeeeeeeeeeeeeeeeeeeeemene seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee j CAUTION IF CONTAINMENT SPRAY ACTUATION IS e DUE TO LOSS OF SECONDARY COOLANT, NaOH ADDITION MAY BE ISOLATED BEFORE

• l CONTAINMENT SPRAY TERMINATION REQUIREMENTS ARE MET.

eteenmeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen 4 CHECK I: CONTAI HENT SPRAY SHOULD 3E STOPPD: i

a. CS pumps run lights - LIT

a. Go to Step 5

b. Containment spray termination

b. Continue with Step 5 requirements - ACHIEVED:

WHEN containment l pressure is less than Containment prussure LESS 18 PSIG, and containment e THAN 18 PSIG spray has run at least two hours if applicable, spray operating time - (only THEN do Steps 4c e applicable to a LOCA) A_T through 4e. LEAST TWO HOURS

c. Reset containment spray signal i

d. Stop CS pumps and place in standby:

I e CS pump 1A e CS pump 1B

e. Close CS eductor spray additive j

isol valves: e ICS019A e ICS019B APPROVED 1 ' MAR 2 41986 (0110E/0011E) .. R.

1 REY. lA OPERATOR. ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 (FNT CHG PUMP MINIFLOW VALVES: SI REINITIATION: Manually operate ICCS pumps as-Close ICV 8110, ICV 8111 necessary JJ either: e RCS pressure < 1370 PSIG o RCS subcooling - NO" ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC D:: SPLAY OR -AND-ATTAGMENT A, star A AND SI actuated FIG.TRJ, 18CA 3.1-1 Onen ICV 8110, 1CV8111 -OR-e e RCS pressure > 2000 PSIG o PZR level - CA3GKff BE MAINTAINED >4% R8% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or

3. Heat sink - ALL SGs NR <4%

radweste I'34% FOR ADVERSE CNpT) AND o Reduce cooldown rate Prepare to isolate secondary 0TAL F""_TER F"D <500 o ( of 3 SG GPM AVAILABLE I I

4. Integrity - DECREASE >100*F CST LEVFL REACHES 31:

IN LAST 60 M. muwsis AND RCS COLD LEG TEPE M Tuns <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX Y TO 1RF 3 2 IF ANY J l I UM A I t-J SG$ o Uncontrolled pressure ' decrease -OR-o completely depressurized UNLESS needed for cooldown i GO TO 1BEF ES-1.3 IF: e RNST level < 46% (0110E) APPROVED l MAR 241986 B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION I RCS PRESSURE SHOULD BE MONITORED, IF

• f RCS PRESSURE DECREASES TO LESS THAN 300 PSIG (600 PSIG FOR ADVERSE CNMT),*

RH PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.* i 5 CHECK IF RH PUMPS SHOULD BE STOPPED:

a. Check RCS pressure:

a. Go to Step 6.

1) Pressure - GREATER THAN 300 PSIG (600 PSIG FOR ADVERSE CNMT)

2) Pressure - STABLE OR INCREASING

b. Stop RH pumps and place in l

standby j f e - RH pump 1A e RH pump 1B 6 IN:IATE EVALUATION OF PLANT STn"US:

a. Check Auxiliary Building

a. Try to identify and radiation:

isolate leakage.

1) Auxiliary Building vent stack effluent monitors 1

(1PR28J)' - LESS THAN i ALERT ALARM SETPOINT e Grid 2 Beta 1PA228 e Grid 2 Gas Low IPB128 i e Grid 2 Iodine IPB328 l e Grid 2 Gas High IPB428 Step continued on next page l APPROVED MAR 241986 (0110E/0011E) B. O. S. R.

REV. lA-OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 F0,R 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: i Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary ]Z either: e RCS pressure < 1370 PSIG o RCS subcooling - NCC ACur.naBLE (< 1670 PSIG ADVERSE CNMT) VALUE FRON ICON::C 0:: SPLAY OR -AND-ATTAuwamma A, S1'IP A AND SI actuated FIGURE IBCA 3.1-1 Onen ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PER level - CANNOT BE 1 MAINTAINED >4% (38% FOR RED PATH SUp9tARY: ADVERSE CMMT?

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 901:

2. Core cooling - CORE EXIT o

Crosatie unit CSTs TCs > 1200*F o Makeup from MUDS or I radweste

3. Heat sink - JLL SGs NR <4%

o Reduce cooldown rate C34% FOR ADY RSE CN ET) AND o Prepare to isolate secondary

,vraL 1--

-R 'em F"4 8 (500 of 3 SG GPM AVAILABL)

4. Integrity - DECREASE >100*F i

CST LEVEL REACHF9 31: IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRES 8URE > 50 PSIG 2.

Switch AF suction to SX T TO 1R 3 2 IF ANY l l I 2141 o SG: o Uncontrolled pressure decrease -OR-o Completely depressurized M needed for cooldown GO TO IBEF EM-1.3 IF: e INST level $_4_G (0110E) APPROVED MAR 241986 B. O. S. R. 1

REY. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINED 2') ECCS pump cubicles - LESS THAN ALERT ALARM SETPOINT RH/CS pump 1A Cubicle e (IPR 13J): t e Grid 2 Beta IPA 213 e Grid 2 Gas IPB113 l RH/CS pump 1B Cubicle e (IPR 14J): e Grid 2 Beta 1PA214 e Grid 2 Gas IPB114 e CENT CHG pump 1A Cubicle l (IPR 17J): e Grid 2 Beta IPA 217 e Grid 2 Gas 1PA117 e CENT CHG pump 1B Cubicle (IPR 18J): l e Grid 2 Beta 1PA218 e Grid 2 Gas IPB118

b. Obtain samples RCS activity e

e RCS boron concentration RCS hydrogen concentration e Ruptured SG(s) activity l I

c. Evaluate plant equipment:

l o CC System i o RH System o Other equipment as necessary

d. Start additional plant equipment to assist in recovery.

APPROVED i MAN Z4 586 Page 10 of 34 B. O. S. R. (0110E/0011E)

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3!1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG pump MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary J.E either: e RC8 pressure < 1370 PSIG o RCS subcooling - NO" ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC D:: SPLAY OR -AND-ATTAcarwdi A, STEP A AND SI actuated FIwaui 18CA 3.1-1 Onen ICV 8110, ICV 8111 o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATM

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR

> 54 CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste-

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C344 FOR ADVERSE CNPT) AND Prepare to isolate secondary o

,vraL ramuwATER FLot

<500 of 3 SG ways AVAILABLE

4. Integrity - DENME >100*F CST LEVEL REACHF9 M:

IN LAST 60 MINUTES AND RCS COLD LEG 2anrhATURE <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to 8X E TO RF3-2 IF ANY J l IUM HTE) SG o Uncontrolled pressure decrease -OR-o completely depressurised M needed for cooldown GO TO 1 BED ES-1.3 IF: e RNs? level 3,_16 (0110E) i t APPROVED MAR 24 686 B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 i ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 7 CHECK IF SGs ARE INTACT:

a. Check pressures in all SGs -

a. Verify all faulted SG(s) isolated unless needed NO SG PRESSURE DECREASING for RCS cooldown per 1BEP-2 e

IN AN UNCONTROLLED MANNER FAULTED STEAM GENERATOR t ISOLATION, Step 1. e NO SG COMPLETELY DEPRESSURIZED oneseeeeeeeeeeeeeeeeemeneeseneeeeeeeeeee. CAUTION ALTERNATE WATER SOURCES FOR AF PUMPS

• NILL BE NECESSARY IF CST LEVEL DECREASES TO LESS THAN 3%.

eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen 8 CHECK INTACT SG LEVELS: 4

a. Narrow range level - GREATER

a. Maintain total feed flow THAN 4% (34% FOR ADVERSE CNMT) greater than 500 GPM until narrow range level greater than 4% (34% FOR ADVERSE CNMT) in at least one SG.

b. Control feed flow to staintain

b. IF narrow range level in narrow range level between M any intact SG continues (34% FOR ADVERSE CNMT) and 66%

to increase in an uncontrolled manner, THEN go to 1 BEP-3, STEAM GENERATOR TUBE RUPTURE, 1 Step 1. l APPROVED MAR 241986 (0110E/0011E) .. R.

b 1BCA-3.1 OPERATOR ACTION

SUMMARY

FOR 1BCA-3.1 REV. lA WOG-1 f_FNT CHG Pt1MP MINtFt OW VA ICV 8111 SI REINITIATION: Close ICV 8110, RCS pressure < 1370 PSIG1670 PS Manually operate ECCS pumps as' e nec ssary JfF either: NOT ACQEPTABI.4 SI actuated (< -AND-RCS subcooling IQ DISPLAY OR VALUE FROM ICONSTEP A AN_D Onen 1CV8110, ICV 811'1 o ATTACHMENT Ar F h 15CA 3.1-1 ~ RCS pressure > 2000 PSI _G e -OR-RED PATH S M : PER level - CANNQT B54% (38% FOR

1. Subcriticality NUCLEAR o

MAINTAIN JED POWER > Si A_DVgean Cheq),

2. Core cooling - CORE EXIT

( 701: TCs > 1200*F C9T I EVFI

3. Heat sink - ALL SGs N Crosstie unit CSTs Makeup from MUDS or TptAL rr. aim'A" o

o GPM AVAI M 'l radwaste Reduce cooldown ratePrepare to isolate secondary DE_gtEASE >100*F 0

4. Integrity MINU"@ Elf AND RCSJRE <246*F l

o of 3 SG IN LAST 60 COLQ L5Q T G 53-C9T I FVFt RF AfMES_I5:

5. Containment - CNMT Verify secondary side of 3 SGe isolated P4 TO 1RFP ? TF ANY 1

Switch AF suction to SX iiNIROI ATFD Sli: Uncontrolled pressure 2. o decrease completely depressurisedUN -OR-o as-t.s Ir: Go to 1sEp RWST level M e APPROVED (0110E) MAR 241986

I REV. lA SGTR WITil LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ] I j NOTE As time permits during RCS cooldown,

• i check BGP 100-5 PLANT SHUTDOWN AND COOLDOWN to insure appropriate steps
• l for RCS cooldown are met.

1 NOTE Shutdown margin should be monitored i during RCS cooldown. l i e NOTE If sufficient cooldown rate cannot a be obtained with steam dumps only, consideration should be given to using SG PORV(s) on intact SG(s) as an additional steam release path. i NOTE If steam dumps are opened rapidly l with PZR pressure greater than 1930 l PSIG, Main Steamline Isolation will occur from Low Steamline Pressure SI.* l NOTE I When PZR pressure decreases to less than 1930 PSIG, Low Steamline Pressure SI should be blocked. 9 INITIATE RCS C00LDOWN TO 200*F:

a. Maintain cooldown rate in RCS i

cold legs - LESS THAN 100*F/HR l

b. Use RH System if in service Step continued on next page.

APPROVED MAR 241986 4 (0110E/0011E) B. O. S. R.

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 F0R 1BCA-3.1 I SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: l l Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 I necessary.IJ,either: e RCS pressure < 1370 PSIG l o RCS subcooling - Ny' ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC :):: SPLAY OR -AND-ATTAO MENT A, STEP A AND SI actuated FIGURL ISCA 3.1-1 Onen 1CV8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CMMT)

1. Suberiticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F l o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C34% FOR ADVERSE CNMT) AND o Prepare to isolate secondary. ( 0TAL rr.r.wiATER FLOW < 500 ( of 3 SG GPM AVAILASLE

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

Ig ,AST 60_ MINUTES AND RCS COL) LEG u,wi. MATURE < 2 4 6

• F 1.

Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX "O TO LBED 2 IF ANY J l IGt dTE] SG o Uncontrolled pressure decrease -OR-o completely depressurized M needed for cooldown GO TO 1BIP ES-1.3 IF: e RNET level < 46% l (0110E) APPROVED MAR 241986 i B. O. S. R.

-l REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED l

c. Dump steam to condenser from

c. Manually or locally dump

) intact SG(s): steam from intact SG(s):

1) Check condenser available Use SG PORV(s).

2) Place steam dump pressure IF NO intact SG available, controller in manual and THEN perform the following:

reduce demand signal to zero o Use faulted SG. I

3) Place steam dump mode selector switch in STEAM PRESSURE mode

-OR-

4) Manually adjust demand o

IF RH System NOT in to initiate cooldown

service, THEN use ruptured SG.

5) Momentarily bypass cooldown interlock upon reaching P-12 1

(550*F) l 10 CHECK RCS SUBC00 LING: i

a. RCS subcooling - ACCEPTABLE

a. Go to Step 24.

- using: o ICONIC DISPLAY 7 4R- ) o ATTACHMENT A, STEP A AND FIGURE 1BCA 3.1-1 11 CHEC C IF SURC Mi FD REC 0VERY IS A)PROPRIAT E: I

a. Check RNST level - GREATER

a. Refer to FIGURE IBCA-3.1-3 THAN 67%

to determine expected CNMT floor water level. IF CNMT floor water level Tess than expected, THEN go to 1BCA-3.2, SGTR MITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY j DESIRED, Step 1. Step continued on next page APPROVED i Page 13 of 34 l (0110E/0011E) B. O. S. R. .-,-,--,,,,..m--- ann-_w.--,-----n-,----,--, ,,---,e-,,nn,--.-_ ,,n,.,.,- ..,,,_-_n,---_,,-w.

\\ 9 i i REV. lA OPERATOR ACTION

SUMMARY

IBCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary J,Z either: e RCS pressure < 1370 PSIG o RCS subcooling - M r ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICON::C 1:SP.AY_QR -AND-ATTACiwas.mi A. S"EP A AfD SI actuated FIwas 1BCA 3.1-1 i Onen ICV 8110, ICV 8111 -OR-t e RCS pressure > 2000 PSIG o PER level - t ?_,_BE MAINTAINED >4 3L% FOR RED PATH SU39tARY: ADVERSE CBDIT)

1. Subcriticality - NUCLEAR PONER > 5%

CST LEVEL < 201;

2. Core cooling - CORI EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C34% FOR ADVERSE CNpT) AND o Prepare to isolate secondary isiaL c-- -ATER FLON < 500 of 3 SG w m AVAILABLE

4. Integrity - DECREASE >100*F CST LEVEL REACHF9 31:

IN LAST 60 MINUTE 1 AND RCS COLD LIG TEMPERATtRE <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - C3 GIT PRESSURE > 50 PSIG 2.

Switch AF suction to SX 1: TO 1RF 3-2 IF ANY JnI%'M a r u SG; i o Uncontrolled pressure decrease -OR-o completely depressurized ~ TArLESS needed for cooldown GO TO 1BIP ES-1.3 IF:

• RNST level f,,,ill e

i i (0110E) APPROVED MAR 241986 i B.O.S.R. L.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 I ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED h i b.-Check ruptured SG narrow

b. Consult TSC to determine if range level - LESS THAN recovery should be 96% (66% FOR ADVERSE CNMT) completed using 1BCA-3.2, SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED, Step 1.

i 12 CHECK IF ECCS IS IN SERVICE: Go to Step 20. i o Any SI pump run light - LIT -GR-o CENT CHG discharge to cold leg ction isolation valves - OPEN: o ISI8801A o ISI8801B 13 P LAC E A_L P7R 4 EATER SWITCHES I I WOFF 20SI"IOW: estatemeseseementennesteenesteetestemette CAUTION VOIDING MAY OCCUR IN THE RCS DURING l RCS DEPRESSURIZATION. THIS WILL j RESULT IN A RAPIDLY INCREASING PER LEVEL. mennesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene l ll4 DEPRESSURIZE RCS TO REFILL PZR: i

a. Use normal PER spray

a. Use one PZR PORV.

I_F NO PORV available, THEN use PER auxiliary spray valve. l

b. PZR level - GREATER THAN

b. Continue with Step 15.

21% (50% FOR ADVERSE CNMT WHEN level greater than 21% (50% FOR ADVERSE CNMT), THEN do Step 14c.

c. Stop RCS depressurization APPROVED MAR 241986 Page 14 of 34 (0110E/0011E)

B. O. S. R.

\\ REV. lA WOG-1 OPERATOR ACTION

SUMMARY

FOR 1BCA-3.1 1BCA-3.1 SI REINITIATICBf \\ Manually operate ECCS pumps as-CENT CMG PUMP MINIFLOIJ VALVE necessary Il either: Close ICV 8110, ICV 8111 RCS subcooling - NOT AG -vrA*L' RCS pressure < 1370 PSIG o e VAP.11 F8'*? I N IC DISPLAY OR (< 1670 PSIG ADVF**E Csnx) AT"ACnn.wr A. orar A A?J -AND- ~ i FIvuus 1BCA 3.1-1 SI actuated } -OR-Open ICV 8110, ICV 8111 PZR level - CANNOT BE RCS pressure > 2000 PSIG I o e MAINTAm" >4% (38% FOR ADvam5E CBDfT_) RED PATH Sf""."JY: CST LEVEL e 201;

1. Suberiticality - NUCLEAR POWER > 54 l

o Crosstie unit CSTs

2. Core cooling - CORE EXIT Makeup from MUDS or TCs > 1200*F o

radweste Reduce cooldown rate

3. Heat sink - ALL SGs NR <4%

o Prepare to isolate secondary, o 434% POR Auv--*" CBBtT) AND i of 3 SG 1 vraL r-- - ama FLON < 500 van AVAIf3 *' ' \\ CST LEVEL RFACHFM 31:

4. Integrity - DEN P.SE >100*F l

IN LAST 60 MImursi AND RCS 1. Verify secondary side of % 2f 7 9 3 SGs isolated senr==_A:KusE <346*F \\

5. Containment - CastT 2.

Switch AF suction to SX P**"f* * > 50 PSIG O To 'RF3-2 IF ANY_ U.iIqu;uei ss Uncontrolled pressure o decrease t -OR-Completely depressurised o UtiLESS needed for cooldown ) i 00 '!C IEEP ES-1,3 IF: l ENST level 3 'j (0110E) 4 APPROVED i i MAR 24 886 B. O. S. R.

REY. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 . ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINED ne..................neamenaeaseteenne ene CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THE AFFECTED RCP(S) SHOULD* NOT BE STARTED PRIOR TO A STATUS EVALUATION. e...... ent**eeeeeeeeeeeeeeeeeee......... esteetteetteteemetee.Atenentettetetenment CAUTION ON NATURAL CIRCULATION, RTD BYPASS i TEMPERATURES AND ASSOCIATED INTERLOCKS MAY BE INACCURATE.' $$eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen teetmanneteteneseeneneteteteteateteenesee NOTE RCP 1D or 1C should be run, if possible, to provide normal PER a spray. eammeneeeeeeeeeeeeeeeeeeeeeeeeeeeeeemanas i } 15 CHECK IF AN RCP SHOULD BE STARTED: l

a. All RCPs - STOPPED

a. Stop all but one RCP.

Go to Step 16.

b. RCS subcooling - ACCEPTABLE

b. Go to Step 24.

using: I o ICONIC DISPLAY -OR-j 1 o ATTACHMENT A, STEP A AND l FIGURE IBCA 3.1-1

c. PZR level - GREATER THAN 21%

c. Return to Step 14.

(50% FOR ADVERSE CNMT) Step continued on next page. l l 4 APPROVED MAN 241986 (0110E/0011E) B.O.S.R.

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 l SI'REINITIATION: CFNT CHG PUF0_HLNIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, 1CV8111 necessary JZ either:

• RCS pressure < 1370 PSIG o

RCS subcooling - NO" ACCEPTABLE (< 1670 PSIG A) VERSE CNMT) VAIHE FROM ICONIC D: 8 FAY OR -AM)- A"TACHMENT A, STEP A AMD SI actuated F:lG.7RE ISCA 3.1-1 Onen ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG MAINTAINED >4% (38% FOR RED PATH SUp9tARY: ADVERSE CNMT)

1. suberiticality - NUCLEAR POWER > 5%

CST LEVEL < '201:

2. Core cooling - CORI EXIT l

o Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - ALL 80s NR <4%

o Reduce cooldown rate C34% FOR ADVERSE CbOT) AND o Prepare to isolate secondary G@ild, r-- - ATER FW (500 of 3 SG GPM AVAILABLE I

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN LAST 60 IINUTES AND RCS COLD LEG TED PIRATURE (246*F 1. Verify secondary side of 3 80s isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX D TO 1RF 3 2 f F ANY J l IUM Art) SG; o Uncontrolled pressure decrease -OR-o letely depressurised needed for cooldown 00 TO 1BEF ES-1.3 IFt e RNST level 1_ill (01105) APPROVED MAR 24 886 B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 1 ' ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

d. Try to start an RCP:

1) Establish conditions for j

i starting an RCP per BOP e RC-1(2) STARTUP OF AN RCP l i

2) Start one RCP eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene l

NOTE l After stopping any ECCS pump, RCS I a pressure should be allowed to stabilize before stopping another a ECCS pump.

• • eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen seeme**en

..............eene nes...... NOTE The CENT CHG pumps and SI pumps should be stopped on alternate ECCS trains when possible. e..... NOTE If ADVERSE CNMT conditions exist and

• subcooling requirements cannot be attained for 8I flow reduction, contact SE for possible relaxation of subcooling requirements.

e....... ...................es... 16 CHEC C IF CE WT CHG PUMP (S) SHOULD I 1E RMLIGM ): l

a. CENT CHG pump (s) - INJECTING TO

a. Go to Step 17.

RCS COLD LEG 8 i Step continued on next page f APPROVED MAR 241986 Page 16 of 34 (0110E/0011E) B.O.S.R.

1 REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CFMT CHG Pt1MP MINIFLOW VALVES: Manually operate ECCS pumps as - Close ICVS110, 1CVS111 necessary J.E either: e RCS pressure < 1370 PSIG o RCS subcooling - NOT ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICON::C DISP AY OR -AND-At"NCHMENT A, $1'EP A AfD SI actuated F"GCRE 15CA 3.1-1 Onen 1CVS110, ICV 0111 -OR-e RCS pressure > 2000 PSIG MAIN't'Af =n > 4 % ( 38% FOR RED PATH

SUMMARY

1. Suberiticality - NUCLEAR PONIE > 5%

CST LEVEL < 701:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F { o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR (4%

o Reduce cooldown rate J34% POR ADVERSE OOtT) AND o Prepare to isolate secondary vxnL rammwnrma F"At <500 of 3 SG GPN AVAILABLE 1

4. Integrity - DECREASE >100*F l

CST LEVEL REACHES H: IN LAST 60 pINUTES AND RCS COLD LEG TEDPERATURE <246*F 1 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX Y T' 'RF3 2 IF ANY Jn Ivi din SG: o Uncontrolled pressure decrease -OR-o letely depressurized needed for cooldown GO TO 1BEF ES-1 3 IF 4 i e RNST level 1_iG (0110E) APPROVED MAR 241986 B. O. S. R. 1

I REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 4 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED i

b. Determine required subcooling I

from table: RCS SUBCOOLING (*F) 2 CENT CHG PUMPS ON 1 CENT CHG PUMP ON SI PUMP CNMT CNMT STATUS NORMAL (ADVERSE) NORMAL (ADVERSE) ANY RUNNING 55' (270') 40' (250*) WQNE RUNNING 85* (300') 55' (265') l

c. Check RCS subcooling - GREATER

c. DO NOT RE-ALIGN PUMP (S).

THAN REQUIRED VALUE using: Go to Step 24. i 1 { o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP B

d. PZR level - GREATER THAN 21%

d. Do not RE-ALIGN PUMP (S).

(504 FOR ADvamSE CNMT) Return to Step 14.

e. Realign CENT CHG pump (s) through normal charging:

1) Verify open CENT CHG pump (s)

1) Manually open valves.

t miniflow isolation valves: e ICV 8110 ICV 8111

2) Manually close ICV-121 to 51 1

3) Open charging line contain-ment isolation valves:

e ICV 8105 l Step continue ext page APPROVED MAR 241986 (0110E/0011E) . O. S. R. . - - ~

[ ( REV. lA OPERATOR ACTION

SUMMARY

IBCA-3.1 WOG-1 FOR 1BCA-3.1 l 1 SI REINITIATION: (FMT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary IE either: e RCS pressure < 1370 PSIG o RCS subcooling - N(yf AFCEPTABLE (< 1670 P81G ADVERSE CNMT) VALUE FROM ICON"C DISPMY OR -AND-A1'TACHMENT A, 81'EP A AfD SI actuatJd FMGURE ISCA 3.1-1 Ocon ICVS110, ICV 8111 -OR-e RCS pressure > 2000 PSIG MAINTAINED Dot C 8% FOR RED PATH SW9tARY: ADVERSE CNMT

1. Suberiticality - NUCLEAR I

POWER > 5% CST LEVEL ( 201: l

2. Core cooling - CORE EXIT i

o Crosstie unit CSTs TCs > 1200*F l o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C34% FOR ADVERSE CNMT) AND l o Prepare to isolate secondary {vinL ramuwATER FLON <500 of 3 SG GPM AVAILASLI

4. Integrity - Dgg p er >100*F CST LEVEL REACHES 31:

IN LAST 60 'INUTES AND RCS COLD LEG TE IPERATURE (246*F 1. Verify secondary side of 3 SGs isolateds

5. Containase'. - CNMT 2.

Switch AF suction to SX D TC 1RF 3 2 IF ANY J i Ivi Aru SG: o Uncontrolled preseure decrease -OR-o letely depressurized needed for cooldown GO TO ISEP ES-1.3 IF: e RNST level 1_i11 (0110E) APPROVED MAR 24 886 B. O. S. R. 1

i..

Its ( 1 a s C 'i ! x di REV. lA SGTR k2TH LOSS OF REACTOR COOLANT-o 1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 e [\\ y,, STEP j' [ ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINED i

4) Close CENT CHG pumps to o

s. cold. leg-injection ) i isolation valves: 4 e leis 301A l e 18:8801B. I t i

5) Throttle ICV-182 to maintain i

RCP steal injection flow I, between,8 and 13 GPM per pump i

6) Throttle CV flow using ICV-121 i

to maintain PER level - between i 'and(38% FOR ADVERSE CNMT) 4% i s 17 C4ECK I: M E fENT CHG PUMP SHOULD E STOP4E): j

a. CENT CHS pumps - TWO RUNNING

a. Go to Step 18.

b. Determins required subcooling from table:

i \\ 7 RCS SUBCOOLING (*F) 4 i ,5 SI PCMP l ,? STAT 08 NORMAL (ADVERSE) l 2 AI RUNNING 45' (260*) c. 1 81 RUNNING 75* (290*)

c. Check RCS subcooling GREATER

c. DO NOT STOP CENT CHG l

1 THAN REQUIRED VALUE using: pump. GO to Step 24. o IC0NIC DISPLAY 1 -OR-o ATTACHMENT A, STEP B step continued csn next page APPROVED MAR 241986 t Page 18 of 34 '(0110E/00 LIE) B. O. S. R.

s. i ~ 9 REV. lA $PER,tTORACTION

SUMMARY

WOG-1 FOR IBCA-3.1 1BCA-3.1

• ~:,,

i t 3, + SI REINITIATION: Manually operate ECCS pumps as-.. - CENT CHG PUMd MINIFLOW VALVES necessary R either: Close ICV 8110, ICV 8111 RCS subcooling - NOT ACCEPTASLE RCS pressure < 1370 PSIG o (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICON 1C DISPLAY OR ATTACvinda-A, 8"EP A AND -AND-FIGURR ISCA 3.1-1 SI actuated 'A OpenICIS11h',' ICV 8111 -OR- . [ o PZR level - CANNOT'8E RCS pressure > 2000 PSIG MAINTAINED >4% (38% FOR ADVERSE Cani) M ATH

SUMMARY

\\

1. Subcrit.icality - NUCIJEAR CST LFVFL < 201:

POWER > St o Crosstie unit CSTs

2. Core cooling,- CORE EXIT o

Makeup from MUDS or TCs > 1200',( radweste ( o Reduce cooldown rate

3. Heat sink - ALL SGs NR <4%

Prepare to isolate secondary C34% POR AFv- ** CNtT) AND o EsfAL c-- +hTER FLot of 3 SG <S00 ,Grn AVAIf m E CST LFVEL RFACHER 31:

4. Integrity - DECREASE >100'F IN lag 7 60 MINUTES AND RCS 1.

Verify secondary side of COLD LEO innr -ATURE (246*F 3 SGs isolated,

5. Nntainment - CNMT 2.

Switch AF suction to SX sP*?**"*? > 50 PSIG 3_ D TO 1RF 3-2 IF ANY 1 U n NiATE) SG; l o Uncontrolled pressure decrease -ORJ

o. Completely depressurized M needed for cooldown GO 'fD 1EEP ES-1.3 IF; RNST level W e

I. (0110E) APPROVED MAR 241986 B. O. S. R. ,,,-s-,,,..,-,,a. -n- -,,----.------------.,,.-,.m., -s---,. , - - - - ~ -,,

i l REV. lA SGTR WITH LOSS OF REACTOR COOLANT-WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 1BCA-3.1 STEP ACTION / EXPECTED RESPONSE -g RESPONSE NOT OSTAINED ia

d. PER level - GREATER THAN 21%

-(50% FOR ADVERSE CNMT)

d. DO NOT STOP CENT CHG pump.

Return to Step 14.

e. Stop one CENT CHG pump I

18 CHE*C IF ONE SI PUMP SHOULD BE STOA >ED:

a. SI pumps - TNO RUNNING I

i

a. Go to Step 19.

l

b. Normal charging - IN SERVICE

b. Go to Step 24.

I

c. Check RCS subcooling GREATER THAN 65'F (280*F for ADVERSE

c. DO NOT STOP SI PUMP.

CNMT) using: Go to Step 24. o ICONIC DISPLAY -OR-o ATTACHMENT A, STEP B

d. P3R level - GREATER THAN 21%

i l (50% FOR ADVERSE CNMT)

d. DO NOT STOP SI PUMP.

I Return to Step 14.

e. Stop one SI pump 19 4ECK I IEMAINING SI PUMP SHOULD E STOP)E ):

a. SI pump - ONE RUNNING

a. Go to Step 20.

b. Normal charging - IN SERVICE

b. Go to Step 24.

c. Check I'.C8 subcooling GREATER THAN 65'F (270* FOR ADVERSE

c. DO NOT STOP SI PUMP.

] CNMT) using: Go to Step 24. l I o ICONIC DISPLAY OR-o ATTACHMENT A, STEP B Step continued on next page APPROVED MAR 241986 (o13cgfocitz)

1. • 9' l' f 34 B. O. S. R.

i.-m mm ,-------y ..-,,-%3--w--w,,.,-w.erw,. m,, e

r_wa, c--.-----www..m-,

--,me.--mm... .,,y + ---. .,r ,-,,--w.,r-,

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CFNT CHG PUMP MINIFLOW VALVES: I Manually operate ECCS pumps as* Close ICV 8110, ICV 8111 necessary g either: I e RCS pressure < 1370 PSIG o RCS subcooling - 187' ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC ISPLAY OR -AND-ATT.IOGENT A, STEP A AND SI actuated i FIGCRE 18CA 3.1-3 l Open ICV 8110, 1CV8111 l -OR-e RCS pressure > 2000 PSIG MAINTAINED >4% (34% FOR RED PATH

SUMMARY

ADVERSE CNMT) l

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - RORE EXIT l

o Crosstie unit CSTs _TC,s > 1200*F j o Makeup from MUDS or radwaste

3. Heat sink - lILL SGs NR <4%

o Reduce cooldown rate C34% FOR ADV 28E CNMT) AND o Prepare to isolate secondary. " OTAL an.nuwA 'ER FLOW < 500 of 3 SG GPM AVAILASL l 4. Integrity - D M M SE >100*F CST LEVEL REACHES 31: IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE (246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CIDET PRESSUBS > 50 PSIG 2.

Switch AF suction to SX l E TB 1RF 8-2 IF ANY J t IVA ATE) SG: o Uncontrolled pressure l decrease -OR-o completely depressurized UNLEss needed for cooldown GO TO 15EP ES-1.3 IF:

• RNET level < 46%

1 (0110E) l l APPROVED t MAR 241986 l S. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 . ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED d.'PZR level - GREATER THAN

d. DO NOT STOP SI PUMP.

21% (50% FOR ADVERSE CNMT) Return to Step 14.

e. Stop remaining SI pump l

20 COWTROL CHA.t!3"N 3 FLOW TO MAINTAIN l PZt 1EVEL GltIEnT ER THAN 4% (38% FOR ADVE 1SE CNMi) l eenneen.eeeeeeeeeeee.eeeeeeeeeeen........ CAUTION i IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, AFFECTED RCP(S) SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION. eenemeneemameeeeeeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemeneesen. CAUTION ON NATURAL CIRCULATION, RTD BYPASS TEMPERATURE AND ASSOCIATED INTERLOCKS MAY BE INACCURATE. meeeeeeeemmenemmeeeeeeeeeeeeeeee........ enamentementesameneseemmetenemometeemenes NOTE RCP ID or 1C should be run, if possible to provide normal PZR 1 spray. eeeeeeeeeeeeeeeeeeeeeemenmaammenesseemste 21 CHECK RCP STATUS: l

a. RCPs - AT LEAST ONE RUNNING

a. Try to start one RCP:

l

1) Check RCS subcooling -

) ACCEPTABLE using: o ICONIC DISPLAYS -OR-o ATTACHMENT A, STEP A AND FIGURE IBCA 3 1-1 APPROVED Step continued on next page MAR 241986 (0110E/0011E) B. O. S. R. Page 20 of 34

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close 1CV8110, ICV 8111 necessary Il either: e RCS pressure < 1370 PSIG o RCS subcooling - NO" ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) ( VALUE FROM ICONIC DMSPLAY OR -AND-ATTACHMENT A, STEP A AND SI actuated FIGURE 18CA 3.1-1 Open ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Suberiticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup frce MUDS or redwaste

3. Heat sink - ALL SGs NR (4%

o Reduce cooldown rate C34% FOR ADVERSE CNMT) AND o Prepare to isolate secondary UfAL FIEDNATER FLOW (500 of 3 SG WM AVAII,ASLB

4. Integrity - DECREASE >100*F CST LEVEL REACHER 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary. side of 3 SGe isolated

5. Containment - CNMT PRESSURE > 50 P8IG 2.

Switch AF suction to SX E To 'RF3 2 IF ANY J l IUM dTE] SG: o Uncontrolled pressure decrease -OR-o completely depressurized UNLEss needed for cooldown GO TO 1BEP ES-1.3 IF: e RNET level i_iti (01105) APPROVED MAR 241986 B. O. S. R.

REV..lA SGTR WITH LOSS OF REACTOR COOLANT-WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 1BCA-3.1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT O8TAINED 1

2) Check PZR level -

GREATER THAN 21% (50% FOR ADVERSE CNMT)

3) Establish conditions per BOP RC-1(2), STARTUP OF AN RCP.

4) Start one RCP.

] IF an RCP can NOT be

started, i

THEN refer to Attachment B to verify natural circulation. IF natural circulation can NOT be verified, THEN increase dumping

steam,

b. Stop all but one RCP emenetamenenestemme...te....menementente.

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILI. RESULT IN A RAPIDLY INCREASING PER LEVEL. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ase Asteen eneeaeea$$eeetnetteeameneteeae CAUTION SI ACCUMULATORS SHOULD BE ISOLATED WHEN RCS PRESSURE IS BETWEEN 1000 PSIG AND 800 PSIG PER STEP 25 meneeeeeeeeeeeeeeeeeeeeeeeeeeeeee. eeeeeene 22 DEPRESSJRIZE RCS TO MINIMIZE RCS SUBCOOLING:

a. Use normal PZR spray

a. Use one PZR PORV.

-IF NO PORV available,

b. Cycle PZR heaters as necessary to limit level rise and to THEN use PZR auxiliary maintain PZR steam bubble spray valve.

Step continued on next page APPROVED MAM Z4 PJtfD (0110E/0011E) l l -,, -, - + -., - - ,.--+ -

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 l t I SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: i i Manually operate ECCS pumps as-Close 1CV8110, ICV 8111 l necessary II either: o RCS pressure < 1370 PSIG l o RCS subcooling - ND ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC D:: SPLAY OR -AND-ATTACHMENT A, STEP A AND SI actuated FIGL, tE IBCA 3.1-1 9 ODen ICV 8110, ICV 8111 -OR-o RCS pressure > 2000 PSIG MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CMMT)

1. Subcriticality - NUCLEAR CST LEVEL < 201:

2. Core cooling - CORE EXIT l

o Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - EL SGs NR <4%

C34% FOR ADV RSE CNMT) AND o Reduce cooldown rate [ o Prepare to isolate secondary M FEEDWA 'ER FLON < 50 0 l of 3 SG GPM AVAILABIJ l

4. Integrity - DECREASF >100*F CST LEVEL REACHFR 31:

IN ':.AST 60 MINUTES AND RCS COL) LEG AnnrzmATURE < 246

• F 1.

Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX E TO 'BFD-2 IF ANY J l IUM dTE) SG: o Uncontrolled pressure decrease -OR-o Completely depressurized UNLESS needed for cooldown 00 'IO 18E7 ES-1.3 IP: i e INST level < 46% (01105) APPROVED MAR 241986 B.O.S.R.

t REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

c. Depressurize RCS until either of the following conditions i

satisfied: l o PZR level - GREATER THAN f 76% (62% FOR ADVERSE CNMT) i f -OR-o RCS subcooling NOT ACCEPTABLE FROM ICONIC DISPLAY OR i ATTACHMENT A, STEP A AND FIGURE 1BCA 3.1-1 23 VERIFY ADEQUATE SHUTDOWN MARGIN:

a. Sample ruptured SG(s)

b. Sample RCS

c. Shutdown margin - ADEQUATE

c. Borate as necessary.

2/4 VERIFY ECCS FLOW NOT REQUIRED:

a. RCS subcooling - ACCEPTABLE

a. Manually operate ECCS using:

pumps as necessary, o ICONIC DISPLAY -OR-e o ATTACHMENT A, STEP A AND FIGURE IBCA 3.1-1 l t

b. PZR level - GREATER THAN 4%

b. Manually operate ECCS (38% FOR ADVERSE CNMT) pumps as necessary.

Return to Step 14. l i l I APPROVED MAR 24 886 (0110E/0011E) B. O. S. R.

REV. 1A OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary I.F either: RCS pressure < 1370 PSIG e o RCS subcooling - NO" ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC D:: SPLAY OR -AND-ATTAGMENT A, STEP A AND SI actuated FIGJRI;18CA 3.1-1 Open ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or

3. Heat sink - ALL SGs NR <4%

radwaste F34% FOR ADV 388 CNMT) AND o Reduce cooldown rate o Prepare to isolate secondary OTAL F""*.' 'ER FLON < 500 of 3 SG GPM AVAILABL l

4. Integrity - DECREASE >100*F CST LEVEL REACHFS 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary side of 3 SGs isolated,

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to 8X G" TB 'RFB 2 IF ANY U t I%l dTE) SG: o Uncontrolled pressure decrease -OR-o completely depressurized UNLESS needed for cooldown GO TO 1BEP ES-1.3 IF: e RNST level < 46% l l (0110E) APPROVED MAR 241986 B. O. S. R. l l

REY. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 C4ECK IF SI ACCUMULATORS SHOULD E ISOLATED:

a. RCS subcooling - ACCEPTABLE

a. R RCS hot leg temperatures VALUE FROM ATTACHMENT A, greater than 400*F, STEP A AND FIGURE IBCA 3.1-2 THEN go to Step 26.

H NOT, THEN do Steps 25b l' and 25c. I

b. Check power to SI accumulator

b. Restore power to isolation discharge isolation valves -

valves by closing the AVAILABLE following breakers: o MCC 131X2A A3 (ISI8808A) o MCC 132X2A A3 (ISI8808B) o MCC 132X2A A2 (ISI8808C) o MCC 131X2A A2 (ISI8808D)

c. Close all SI accumulator

c. Vent any unisolated discharge isolation valves and accumulator by performing l

Place out-of-service: the following: l e ISI8808A

1) Close the following e

ISI8808B nitrogen supply e ISI8808C isolation valves: e ISI8808D e ISI8880 e IRYO26A e IRYO26B

2) Open the following accumulator vent I

isolation valves as necessary o ISI8875A (Accumulator A) l o ISI8875B i' (Accumulator B) o ISI8875C (Accumulator C) o ISI8875D (Accumulator D) APPROVED Step continued on next page MAR 241986 (0110E/0011E)

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIELQW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary IF either: F e RCS Pressure < 1370 PSIG o RCS subcooling - NOT ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC DISPLAY OR -AND-ATTAG MENT A, STEP A AND SI actuated FIGURL IBCA 3.1-1 Open ICV 8110, ICV 8111 -OR-

• RCS pressure > 2000 PSIG

(; MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CMMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 205:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C34% FOR ADVERSE CNMT) AND o Prepare to isolate secondary XFFAL FEEDNATER FLOW <500 of 3 SG GPM AVAILABLE

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE (246*F 1. Verify secondary side of 3 SGe isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX 'I TO 1RF3-2 IF ANY D I M ATE) SG: o Uncontrolled pressure decrease -OR-o completely depressurised tMLESS needed for cooldown GO TO IBIP ES-1.3 IF:

• RNST level < 46%

(0110E) l l APPROVED l MAR 241986 l B. O. S. R. i

d. I i REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 I I i ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED q l

3) Open accumulator vent j

header control valve I l e ICV 943 } 26 CHECK I: DIESEL 3ENERATORS SHOULD BE STO YE]: l I

a. Verify ESF 4KV busses energized

a. Try to restore offsite by offsite power:

power to ESF busses. e SAT 142-1 Bus Alive I.F offsite power can NOT Light - LIT be restored, e ACB 1412 - CLOSED THEN notify System Load e SAT 142-2 Bus Alive Dispatcher of existing Light - LIT conditions so an emergency e ACB 1422 - CLOSED AC restoration program can be implemented..

b. Stop any unloaded Diesel Generator and place in standby i

CAUTION NOTIFY RAD CHEM PERSONNEL TO MONITOR RADIATION LEVELS IN CONDENSATE POLISHERS AREA. eemeseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemen 27 MIW::MI7E SECONDARY SYSTEM i COIW"AM : NATION: I i

a. Inspect Auxiliary Building and l

l Turbine Building for leakage ,1

b. Isolate or minimize leakage where possible.

DO NOT i isolate SI or charging path l

c. Ensure condensate polishers

} in service i APPROVED MAN Z 41986 f 4 B. O. S. R. (0110E/0011E) l t

N REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 l necessary IF either: e RCS pressure < 1370 PSIG o RCS subcooling - NOT ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC DISPLAY OR -AND-ATTAC vwma-A, STEP A AND SI actuated i FIGURE IBCA 3.1-1 Open ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PER level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH SIN 9EARY: ADvimEE CNMT)

1. Subcriticality - NUCLEAR PONER > 5%

CST LEVEL e 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - M.L SGs NR <4%

o Reduce cooldown rate o Prepare to isolate secondary. f34% FOR ADV = CNMT) AND

vial c----A 'ER FLOW ( 500 of 3 SG van AVAILABL1 l

4. Integrity - DECREASE >100*F CST LEVEL REACHFM 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <24V F i 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX D TO 1RF 3-2 iF ANY d n 15d'l A s t- ) SG: o Uncontrolled pressure decrease -OR-o completely depressurized UNLESS needed for cooldown 00 TO ISEP ES-1.3 IF: e RNET level < 46% (0110E) APPROVED MAR 241986 B. O. S. R.

REV. 1A SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 28 CHECK RCP COOLING: I

a. RCP seal injection flow -

a. Throttle ICV-182 as I

GREATER THAN 8 GPM: necessary to establish l seal injection flow e RCP 1A I e RCP IB i e RCP IC e RCP ID l t

b. RCP CC System flow - NORMAL

b. Establish normal CC l

WITH THE FOLLOWING cooling to RCPs* I ANNUNCIATORS NOT LIT: 1

1) Roset CNMT e

RCP_ THERM BARR CC Isolation Phase B, WTR FLOW LOW RCP_BRNG CC WTR FLOW LOW

2) Open appropriate CC e

System isolation RCP PUMP THERM BARRIER CC valves as necessary WTR TEMP HIGH e RCP PUMP THERM BARRIER CC l WATER FLOW HIGH LOW e RCP BRNG CC WTR TEMP HIGH 29 CHECC I: RCP SEil R ETURN FLOW SHOU J) BE ESTA R ISH ED:

a. Both of the following

a. Go to Step 30.

I SATISFIED: CC flow to seal water Hz (1FI-642 AUX BLDG 383' ELEV HX AISLE) j i e VCT pressure BETWEEN 5 PSIG AND 70 PSIG

b. Open RCP seal water return containment isolation j

valves to establish seal i return flow: e ICV 8112 e 1CV8100 Step continued on next page APPROVED MAR 241986 (0110E/0011E)

4 REY. lA OPERATbR ACTION

SUMMARY

WOG-1 FOR 1BCA-3.1 IBCA-3.1 SI REINITIATIONi necessary IE either: Manually operate ECCS pumps a CENT CM PUNP MINIFlo s-Close ICV 8110, o [TTAcamVALUE FECM ICawIC DISPLAY ORRCS su ICV 8111 RCS pressure < 1370 PSIG _(< 1870 PSIG ADVERSE CN FIGUR1 L,8CA 3 1-1er A. STEP A AND ~ -AND-SI actuated i -oR-Open 1CVS110, o PER level - CANNDP BE ICV 8111; MAINTA M " Myres" s>)4% (384 'FOR

• RCS pressure > 2000 PSIG RED PATH

SUMMARY

CST t FVFI

1. Suberiticality - NUCIEAR e 705:

39NER > St o Crosatie unit CSTs ~ o Makeup from MUDS or

2. Core cooling - CORE EXIT radwaste T_Cs > 1200'F o

Reduce cooldown rate ~ o Prepare to isolate secondary.

3. Heat sink - ALL SGs NR <4%

of 3 SG 1344 FOR Ivr=1 s-AiFvr;;? CNMT) AND Gen AVAIL 2*'"-fr.ama Ff>** <500] CST I FVFI RFATHFC 35:

4. Integrity - DECREASE >100*F 1.

Verify secondar IN LAST E0 Mimuana AND RCS 3 SGs isolated, y side of @LD LEG anni,--3.iums <2467 2. Switch AF suction to SX

5. Containment - CISIT PRESSURE > 50 PSIG GS70 vp-2 fF ANY LLI IM L FD SG; o

decreaseUncontrolled pressure -OR-o Completely depressurised UNLESS needed for cooldown 90 TO las* ES-1.3 I_F: e RNET level f._ill (0110E) APPROVED MAR 24

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED )) I c.' Verify seal return flow

1) Verify No. I seal leakoff

1) Manually open valves, isolation valves - OPEN:

e ICV 8141A e ICV 8141B l e ICV 8141C e ICV 8141D l 30 CHE:K I: Si tC E RAME DETECTORS SH0JLD 3E E n E RGIZF ); }

a. Check intermediate range

a. Continue with Step 31.

current - LESS THAN 5 X 10-11 WHEN current less than AMPS 5 X 10-11 AMPS, THEN do Steps 30b and 30c.

b. Verify source range

b. Manually energize source detectors - ENERGIZED range detectors.

c. Transfer NR-45 recorder to one source range channel and one intermediate range channel 31 SHU":)NN UNNECESSARY PLANT EQU

' N ENT: l

a. Shutdown all main feedwater pumps l

l

b. Shutdown all heater drain pumps

c. Shutdown all unnecessary condensate / condensate booster Pumps j

i Step continued on next page l i i i APPROVED I I MAN 241986 B. O. S. R. (0110E/0011E)

REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 l SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as' Close ICV 8110, ICV 8111 necessary.Il either: e RCS pressure < 1370 PSIG o RCS subcooling - NOT ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VAL 17E FROM ICONIC DISPLAY OR -AN:>- SI actuated , MENT A, STEP A AND ATTAC FIGJRI 18CA 3.1-1 Open 1CV8110, ICV 8111 -OR-o RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Keat sink - ALL SGs NR <4%

C34% FOR ADVERSE CNMT) AND o Reduce cooldown rate o Prepare to isolate secondary UfAL FEEDNATER FLOW <500 of 3 SG GPM AVAILASLS

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF duction to SX E TO 'RF> 2 IF ANY J l IUM dTE] SG; o Uncontrolled pressure decrease i' -OR-o completely depressurized tAILESS needed for cooldown GO TO 18EP E8-1.3 IF: e RNST level < 46% (0110E) APPROVED MAR 241986 B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

d. Defeat NDCT Turbine Trip '

Interlock:

1) Place all NDCT valve control switches in BYPASS OPEN position:

e 1CW004 e 1CW005

2) Place interlock fuses 6 and 7 in OFF position -

(0PM01J)

3) Reposition valves as necessary for temperature control and circulating water pump shutdown

e. Shutdown all unnecessary circulating water pump and associated NDCT valves l

l l l APPROVED MAR 241986 (0110E/0011E) i j

1 I I l l REV. 1A OPERATOR ACTION

SUMMARY

1BCA-3.1 i WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as' Close ICV 8110, ICV 8111 necessary Il either: e RCS pressure < 1370 PSIG o RCS subcooling - NOT ACwPTnBLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC DISPLAY OR -AND-l ATTACHMENT A, STEP A AND SI actuated i FIGURE IBCA 3.1-1 Onen 1CV8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG MAIN N m >4% (38% FOR RED PATH SUpBURY: ~ ADVERSE CNMT)

1. Subcriticality - NUCLEAR l

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS.or radweste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate 'J34% POR ADVERSE CNMT) AND o Prepare to isolate secondary UFAL FEEDNATER FLOW (500 of 3 SG GPM AVAILABLE

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN ".AST 60 MINUTES AND RCS COL 3 LEO TEMPERATURE (246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT l

P*?"""*? > 50 PSIG 2. Switch AF suction to SX E TO 'RFB 2 IF ANY J l IMI HTE) SG o Uncontrolled pressure decrease -OR-i o Completely depressurized UNLESS needed for cooldown GO TO IBIP ES-1.3 IF: e RNET level < 464 (01105) APPROVED i MAR 241986 B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-IBCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT 08TAINED emamenemmeneesme

• CAUTION FEED FLOW SHOULD NOT BE ESTABLISHED TO ANY RUPTURED SG WHICH IS ALSO FAULTED UNLESS NEEDED FOR RCS COOLDOWN.

menneenemoneeeeeeeeeeeeeeeeeeeeeeeeeeeeee 32 CH EC C RUPTURFD SG(S) NARROW RA WGiE L'EVEL:

a. Ruptured SG(s) narrow

a. Refill ruptured SG to 66%

range lev 61 - GREATER THAN (50% FOR ADVERSE CNMT) 4% (34% FOR ADVERSE CNMT) using feed flow. ~ I_I either of the fo1 lowing conditions occurs, THEN stop feed flow to the ruptured SG unless needed for RCS cooldown: o Ruptured SG pressure decreases in an uncontrolled manner -OR-o Ruptured SG pressure increases to 1090 PSIG. l 33 CHECK IF RCPS MUST BE STOPPED:

a. Check No. I seal differential

a. Trip affected RCPs l

GREATER THAN 200 PSIG I_I all RCPs are tripped, THEN verify natural e RCP 1A e RCP 1B circulation per Attachment e RCP IC B. e RCP 1D Step continued on next page APPROVED MAR 241986 Page 28 of 34 (0110E/0011E) B. O. S. R. v

REY. lA OPERATOR ACTION

SUMMARY

IBCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG Pt]MP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary JI either: e RCS pressure < 1370 PSIG o RCS subcooling - NOT ACur.naBLE (< 1670 PSIG ADVERSE CNMT) VALUE FRON ICONIC DISPLAY OR -AND-ATTACM A, STEP A AND SI actuated FIGJRt 18CA 3.1-1 Open ICV 8110, ICV 8111 -OR-

• RCS pressure > 2000 PSIG MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR PONER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - l:LL SGs NR <4%

Reduce cooldown rate 34% FOR ADV ISE CNMT) AND o o Prepare to isolate secondary "OTAL FEEDNA 'IR FLON < 500 of 3 SG GPM AVAILABL] l

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN.AST 60 MINUTES AND RCS COL) LEG TEMPERATURE (246*F 1. Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX E TO 'RF8-2 IF ANY J l IMI uTE) SG; o Uncontrolled pressure decrease -OR-o Completely depressurized 131LE88 needed for cooldown GO TO 15EP ES-1.3 IF:

• RMST level < 46%

(0110E) APPROVED l MAR 24 886 i B. O. S. R. I /

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ST EP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED

b. Check No. 1 seal leakoff' flow -

b. Trip affected RCPs GREATER THAN 0.2 CPM I_F all RCPs are tripped, o

RCP 1A THEN verify natural e RCP IB circulation per Attachment e RCP IC B. e RCP ID 3I4 C4ECC

F ICS CO3 OVER)RESSURE P 10T EC"Io e CAid t i ? LAC : ) IN S ERVICE:

a. RCS temperature - LESS THAN 380*F

a. Return to Step 8.

b. Place RCS Cold Overpressure Protection in service per BGP 100-5 PLANT SHUTDOWN AND COOLDONN 35 CHECC IF RH SYSTEM CAN BE PLACED IN SERVICE:

a. Check the following:

a. Go to Step 36.

RCS temperatures - LESS e THAN 350*F e RCS pressure - LESS THAN 360 PSIG

b. Consult TSC to determine if RH System should i

be placed in service. 36 CHECK RCS TEMPERATURFK:

a. RCS temperatures - LESS THAN

a. Return to Step 8.

200*F 37 EVALUATE LONG TERM PLANT STATUS:

a. Maintain cold shutdown conditions

b. Consult TSC APPROVED MAN Z 4 S85 (0110E/0011E) l

- ~ ~ - ~ ~ ' ~ ~

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary JZ either: e RC8 pressure < 1370 PSIG o RCS subcooling - NOT ACCEPTABLE (< 1670 P8IG ADVERSE CNMT) VALUE FROM ICONIC DISPLAY OR -AND-ATTACivw.sh A, STEP A AND SI actuated FIwm2 ISCA 3.1-1 Open ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT BE MAIN' PAT"" >44 (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radweste

3. Heat sink - lILL SGs NR (4%

o Reduce cooldown rate C344 FOR ADV ISE CMMT) AND o Prepare to isolate secondary EvraL s-- -3 ER FLOW <500 of 3 SG wra AVAILABL] l 1

4. Integrity - DECREASE >100*F CST LEVEL REACHES 31:

IN LAST 60 MINUTES AND RCS { COLD LEG aanrr. MATURE (246*F ] 1. Verify secondary side of i 3 SGs isolated,

5. Containment - CNMT PRESSURE > 50 PSIG Switch AF suction to 8X Y TO 'RF8 2 IF ANY UllsfM ar u SG:

o Uncontrolled pressure decrease -OR-o Completely depressurized UNLEss needed for cooldown GO '1'O 1EEP E8-1.3 IF: RNET level f_4(1 e (0110E) APPROVED MAR 241986 S. O. S. R.

r-REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 = s L 2600_....

;

2500 = 2400 IS-- - O NIIb5 p = = n!--- mp 2300 '- ---*b- - : ~~3bY 5 - 2200 f 2l00 M5b/E-9 2000 /-IN$U I900 / .b,b =i g L T-f E .1s00 / 1700 )=lEE-c = 'e 1600 i I i- " --'- 3 ACCEPTABLE I -~ ' - - - - - - ~ --- 1500 I I. -.:~ i

== Q L I400 3 I I ___C *._. ~. ; - 1500 ! I

y...

=. 1200 f f f e-m _ _. =. - w 1100 f f f E 1000 ~ / /

= =i- -

= . ADVERSE / / / 4=E.. e m 900 .CN,MT-5 i/ -- =. 4~.. T o m 800 B' ~~ _/ /:NOT ACCEPTABLE y 700 _f _f _. m. _ 600 ~ ~ ~ 500 _.f i 400 ~ NORMAL '-e 300 CNMT g. gATURATION ' = 200 g 10 0 100 200 300 400 500 600 700 TEMPERATURE (*F) c Liv b FIGURE 1BCA 3.1-1 RCS SUBC00 LING MARGIN APPROVED r MAR 241986 Page 30 of 34 (0110E/0011E) B. O. S. R. 5 m

REV. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary.I.I either: o RCS pressure < 1370 PSIG RCS subcooling - WW ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) o VALUE FROM ICON::C JISPLAY OR -AND-ATTAcivinsh A, S"EP A AND SI actuated FIGURE IBCA 3.1-1 Open ICV 8110, ICV 8111 -OR-e RCS pressure > 2000 PSIG o PZR level - CANNOT Sk MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 54 CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosatie unit CSTs TCs > 1200*F o Me.keup from MUDS or radweste

3. Heat sink - ALL SGs NR (44 F34% FOR ADV RSE CN ET) AND o

Reduce cooldown rate o Prepare to isolate secondary U1'AL FEEDWA' 'ER FLo f < 500 of 3 SG GPM AVAILASLl l

4. Integrity - DECREASE >100*F CST LEVEL REACHFS H:

IN LAST 60 MINUTES AND RCS COLD LEG TEMPERATURE <246*F 1. Verify secondary side of-3 SGs isolated,

5. Containment - CNMT l

PRESSURE > 50 PSIG 2. Switch AF suction to 3X j J l I m Art) SG: i o Uncontrolled pressure decrease -OR-o Completely depressurized M needed for cooldown 00 TO 1EEP ES-1.3 IF: e RNET level < 46% l l (0110E) l APPROVED MAR 241986 l B. O. S. R.

REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 2600....... ;;_ _ _. _ _ ;; _; =... __. ___.,.y.._. 2500 2400 l j._.._ _. W... 230o l l ._.M~~~ 2200 / f at00 l l ^--N_: ---lf.^ 20c-2 -f f .. : = ~,,, Is00 / / $5[E 1700 / / ,H__.-~.35~ 1600 i -?:~. a 1e00 l l t =T.4~ yqq j _2' . ACCEPTABLE i i ijh._1 lS00 .i = ~ l 1200 / / --~~ =:.. .. = = - - 1100 f f ..T~ ~~ ~E" 1. 1000 -~~-- j j ADVERSE '

I

/ --- E-- ~ 900 CNMT./ I -. _g. : a 800 / / -~ I / NOT ACCEPTABLE 700 = -. ~~ "'~~ ,~ 600 ./ 500 ~ 400 .-- T.T - ~ - NORMAL -- ~- ~ - - - - - 300 .CNMT.* SATURATION ~--- 200 ~~ 10 0 _ _ = _. 100 200 300 400 500 600 700 TEMPERATURE (*F) FIGURE 1BCA 3.1-2 RCS SUBC00 LING MARGIN +50*F APPROVED MAR 241986 1 4 (011os/co11g) B. O. S. R.

\\ REY. lA OPERATOR ACTION

SUMMARY

1BCA-3.1 WOG-1 FOR 1BCA-3.1 i SI REINITIATION: CENT CMG PUMP MINIFLOW VALVES: l Manually operate ECCS pumps as-Close ICV 8110. ICV 8111 necessary it either: j RCS pressure < 1370 PSIG e o RCS subcooling - NO ACCEPTABLE (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC D" SPLAY OR -AND-ATTAChness A, STEP A AND SI actuated FIwai 18CA 3.1-1 Open ICV 8110, ICV 8111 -OR-RCS pressure > 2000 PSIG e MAINTAINED >4% (38% FOR RED PATH

SUMMARY

ADVERSE CNMT)

1. Subcriticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUD 8 or radweste

3. Heat sink - EL SGs NR <4%

o Reduce cooldown rate (344 FOR ADV " CIO T) AND Prepare to isolate secondary ..vraL c -- -d 'ER FLot ' < 500 o of 3 SG wan AVAILABL] l

4. Integrity - DECREASE >100*F CST LEVEL REACHF9 31:

IN LAST 60 MIkuar AND RCS COLD LEO arnreeATURE <246*F 1. Verify secondary side of 3 80s isolated

5. Containment - CIDIT PRES 8URE > 50 PSIG 2.

Switch AF suction to 8X Y TO 'RF3-2 IF ANY d l IM OTE) SG: 1 o Uncontrolled pressure decrease -on_ o Completely depressurized UNLEss needed for cooldown GO TO 1EEP ES-1.3 IF: RNST level 1_ill e (0110E) APPROVED MAR 241986 B.O.S.R.

,+ '\\ REV. lA SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ? Eg. _ _-- ~EE-( IoC m g ~ eo- = ~- a = 51 h_. i-r e0-X EXPECTED ~ REGION m = = _=_ = = 18CA-3.1 g 3 al 8CA-3.E SUSC00 LED " SATUR ATED RECOVERY .t = u EE RECOVERY - : APPROPRIATE o --=. APPROPRIATE -J 5 ~- 20 ^ = =_ 5 10 15 20 25 lNDICATED CONTAINMENT WATER LEVEL ( INCHES ) (ILI-PC006/007) AF PROVED g 241986 FIGURE 1BCA 3.1-3 CONTAINMENT FLOOR WATER LEVEL VS RWST LEVEL l (0110E/0011E)

m, q, s i / REV. lA WOG-1 OPERATOR ACTION

SUMMARY

' i 13CA-3.1 N + FOR 1BCA-3.1 l= \\ SI REINITIATION: ~ \\ CENT CHG PtiMP MINIFLOW /t(fE: i Manually operate ECCS pumps as-nec00sary JZ either: CloppfICV8110, ICV 8111' RCS subcooling - NOT ACCEPTABLE RCS pressure (!1370 PSIG o VALUE FROM I M IC DISPLAY OR 11_}i70 PSIG ADVERSE CNMT) + ATTAChrir.ar A, ilar A AND ~ -AND-FIGURE 18CA 3.1-1 GI actuated h _ ICV 8110.J CV8111 o PZR level - CAleIOT BE RCN pressure > 2000 PSIG e b MAINTAINED >4% (38% FOR ADVERSE CNMT) RED PATH

SUMMARY

1.Suberitiedlity-NUCLEAR CST LFVEL < 201; POWER > 5% o Crosstle unit CSTs

2. Core cooling - CORE EXIT o

Makeup from MUDS or TCs > 1240*F radweste

3. Heat sink

'A"4 SGs NR <4% i o Reduce cooldown rate Prepare to isolate secondary (34% %OR ADVE ttB CNMT) AND ) o TvfAL rwswAT)'R FIAN <S00 of 3 SG GPM AVAILABL'~ \\ CST fFVEL RFACHF9 31:

4. Integrity - DECREASE >100*F IN LAST 60 MINUTES AND RCS 1.

Verify secondary side of COLD LEG TEMPERATURE <245'F 3 SGs isolated s

5. Containment - CNMT 2.

Switch AF suction to SX __P_R,_ ESSURE > 50 PSIG ~GO TO 'R~P-2 IF ANY (D ISOULT M: i j Uncontrolled pressure o decrease + -OR-Comspletely depressurized o UNLESS neeled fcr cooldown GO TO 1EEP 58-1.3 IF:.. i 1 e RNST level ( 46S. 10E) o I s. APPROVED MAR 241986 y B.O.S.R. s

g REV. 1A SGTR WITH LOSS OF REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED REC 0VERY DESIRED-UNIT 1 i k w 5 't ATTACHMENT A A. Determination of Post-Accident RCS Subcooling:

1. Check Containment for ADVERSE conditions:

o Containment prJssure greater than 5 PSIG = -OR-i, 3' 5 s o Containment radiation greater than 10 R/hr . 2. Check RCS pressure on wide range pressure instruments (IPI-403A/405)

3. Determine temperature for RCS pressure using NORMAL or ADVERSE CNMT curves front Figure referenced in procedure step.

4. Check average of ten highest core exit TCs from MCB indicators (ITI-001/002).

4 IF average of ten highest core exit TCs less than temperature 5 for RCS pressure, THEN acceptable subcooling exists. 1.. B. Determination of RCS Subcooling for SI Flow ~ Reduction:

1. Check RCS pressure on wide range pressure instruments 4

(1PI-403A/405).

2. Determine saturation temperature for RCS pressure using o

SATURATION curve from Figure 1BCA 3.1-1.

3. Check average of ten highest core exit TCs from MCB indicators (1TI-001/002).

4. Calculate RCS subcooling by subtracting average of ten highest core exit TCs temperature from saturation temperature.

+ 1

5. Compare actual RCS subcooling (Step 4) to required RCS subcooling.

s I APPROVED MAR 241986 Page 33 of 34 B. O. S. R. .~(0110E/0011E)

1 s REV. lA OPERATOR ACTION

SUMMARY

IBCA-3.1 WOG-1 FOR 1BCA-3.1 SI REINITIATION: CENT CHG PUMP MINIFLOW VALVES: Manually operate ECCS pumps as-Close ICV 8110, ICV 8111 necessary J.F either: o RCS subcooling - Nyf ACCEPTA8LE RCS pressure < 1370 PSIG e (< 1670 PSIG ADVERSE CNMT) VALUE FROM ICONIC :)ISPLAY OR -AND-ATTAQ masix A, orar A AND SI actuated FIuuaB 18CA 3.1-1 Onen ICV 8110, ICV 8111 -OR-RCS pressure > 2000 PSIG e MAINTAINED >4% (38% FOR RED PATH

SUMMARY

'AD FamEE 6 i)

1. Suberiticality - NUCLEAR POWER > 5%

CST LEVEL < 201:

2. Core cooling - CORE EXIT o

Crosstie unit CSTs TCs > 1200*F o Makeup from MUDS or radwaste

3. Heat sink - ALL SGs NR <4%

o Reduce cooldown rate C34% FOR Auv--** CNMT) AND Prepare to isolate secondary G@iaL r-- -ATER FLOW (500 i, o of 3 SG wan AVAILASLE

4. Integrity - DECREASE >100*F CST LEVEt REACHFR 31:

IN ".AST 60 MImussa AND RCS COL ) LEG aanr".TURE (24 6

• F 1.

Verify secondary side of 3 SGs isolated

5. Containment - CNMT PRESSURE > 50 PSIG 2.

Switch AF suction to SX D TC 1RF L2 IF ANY JtIviArEi SG: o Uncontrolled pressure 1 decrease -OR-o Completely depressurized M needed for cooldown GO TO 1BEF ES-1.3 IF: 1 RNST level f_ill e (0110E) APPROVED MAR 241986 i B. O. S. R. u

REY. 1A SGTR WITH LOSS 0 REACTOR COOLANT-1BCA-3.1 WOG-1 SUBC00 LED RECOVERY DESIRED-UNIT 1 ATTACHMENT B l The following conditions support or indicate natural circulation flow: RCS subcooling - ACCEPTABLE VALUE FROM EITHER ICONIC DISPLAY OR ATTACHMENT A, STEP A AND FIGURE 1BCA 3.1-1. SG pressure - STABLE OR DECREASING RCS hot leg temperatures - STABLE OR DECREASING e Average of ten highest core exit TCs - STABLE OR DECREASING RCS cold leg temperature - AT SATURATION TEMPERATURE FOR SG PRESSURE e l I l l l APPROVED 4 MAR 241986 Page 34 of 34 (0110E/0011E) FINAL B. O. S. R. _ - - -. - _.. -}}